ORNL-4628.txt

L

3 445k 0050L48 2 {?. 106

   
   

 

CRIGEN — THE ORNL ISOTOPE GENERATION
AMD DEPLETION CODE

M, 1 EBell

 

 
 

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National Technical Information Service
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5285 Port Roval Road, Springfield, Virginia 22151
Price: Printed Copy $5.45; Microfiche $0.95

 

 

 

 

This report was prepared as an accouni of work sponsorzd by the United
States Government. Neither the United States nor the United States Atomic
Energy Commission, nor any of their employees, nor any of their contractors,
subcontractors, or their employees, makes any warranty, express or implied, or
assumes any legal liability or respansibility for the accuracy, completeness or
usefulness of any information, appsratus, product or process disclosed, or
represents that its use would not infringe privately owned rights,

 

. ?
ORNL~-L4628
UC-32 — Mathematics and Computers

Contract No. W-7405-eng-26

CHEMICAL TECHNCOLOGY DIVISION

ORIGEN — THE ORNI, ISOTOPE GENERATION AND DEPLETION CODE

*
M. J. Bell

e A o R H .

MAY 1973

s
o o~ e e A XY e
A Sy B AR 6 e

 

3 .

2

* :
Present address: USAEC, Washington, D.C., .  -..-
A S s L

!.‘..1
.
4

OAK RIDGE NATIONAL LABORATORY
Oak Ridge, Termessee 37830
operated by
UNICN CARBIDE CORPORATICN cxe ]

o.0. o s comessros || INEIGTARAN

3 445k 0050L48 &2
iiil

CONTENTS
Abstract e e e e e e e e e e e
1. TIntroduction
1.1 References for Section 1 . . . .+ & v v v v v « « «

Description of Mathematical Method .

2.1 Computation of the Matrix Exponential Series

2.2 Use of Asymptotic Solutions of the Nuclide Chain
BEquations for Short-Lived Isobtopes . . . . . . . « . .

2.3 Application of the Matrix Exponential Method
for Nonhomogeneous Systems e e e e

2.4 Computation of Neutron Flux and Specific Power .

2.5 Construction of the Transition Matrix . . . . . .

2.6 References for Section 2 . . . v v v v v v v e e e 0.

Description of Nuclear Data Library . . . . . . . . .

3.1 MNuclear Properties of Cladding snd Structural Materials

3.2 Nuclear Properties of the Isotopes of the Actinide
Flements and Their Daughters . . . + « « + « « .

3.3 Nuclear Properties of the Fission Froducts

3.4 Photon Yield Library . . . . . . . . .

3.5 Miscellaneous Nuclear Properties . . . . . . . .

3.6 References for Section 3 . . . « v +v v v v 4 . o« .

Uszer's Manual for the ORIGEN Code

4.1 Description of ORIGEN Code Programs . . . . .

4.2 Description of Card Input to the ORTGEN Program . .

4.3 Input for Sample Problem . . . . .

L,

)i

Additional Programming Considerations . . . . . . .

.5 References for Section % . . . . . ¢ v v v v 0 e e ..

Page

 

12
13
14
18
19
19
5.
6.

iv

Glogsary of Warning and Error Messages .

AppendiX . . 0 v 4 e e e e e e e e e e

 
ORIGEN - THE ORNL T8OTOPE GENERATTON AND DEPLETION CODE

M. J. Bell

ABSTRACT

ORIGEN is a versatlle point depletion code which solves the
equations of radiocactive growth and decay for large numbers of
isotopes with arbltrary coupling. The code uses the matrix
exponential method to golve a large system of coupled, linesr,
irst-order ordinary differential eguations with constant coef-
icients, The general nature of the matrix exponential method
ermits the {reatment of complex decay and transmutation schemes.
An extensive library of nuclear data has been compiled, including

alf-lives and decay schemes, neutron absorption cross sections,
fission yields, disintegration energies, and multigroup photon
release data, ORIGEN has been used to compute the compositions
and radicactivity of fission products, cladding materials, and
f'uel materials in LWHs, LMFBRs, MSBRs3, and HTGRs. The applica-
tions are illustrated with calculated inventories and radiation
levels for spent fuel irradiated to a2 burnup of 33,000 MWd/metric
ton in a PWR spectrum.

o Hy

=

 

1.  INTRODUCTION

One of the problems commonly encountered in the field of nuclear
energy is the solution of eguations involving nuclear transmutation and
decsy. To a good approximation, these nuclide chain equations can bhe
represented as a simultanecus system of linear, homogeneocus, Tirst-order
ordinary differential equations with consgtant coefficients. In many
ingtances, the matrix of nuclear transmutetion ccefficients is triangular
and the system of equations can be zgolved using the method of Bateman,l
which has been employed in a number of computer codes. =2 However, each
of these codes has generally suffered from an inasbility to treat more than
a few specific types of transmutations snd from difficulties encountered

- ':é » -
in treating 'feedback," despite some vrogress in these areas.

 

""Feedback” is a term used to describe a reaction in which an isotope
decays to produce one of its precursors, as is encountered in alpha
decay of the actinides, Mathematically, the appearance of such terms
results in a transition matrix that is not triangular.
N0

An alternative approach to solving the same system of eguations
/’

utilizes the matrix expcnential method, which has been employed by Pease”

and others.TnlO

Although completely general, this method has been limited
in the past by the storage that 1s regquired to generate the malrix expo-
nential series and by computational inaccuracies, Computational difficul-
ties arise because the nuclide chain eguations constitute a classic example
of a set of "stiff" ordinary differential equaticns, that is, one in which
the eigenvalues of the characteristic equation for the system are widely
Separated.ll The matrix exponential method has been employed in the

ORTIGEN code in order to exploit its extreme generality. The limitation

cn the number cf nuclides that can be treated, which results from the
necessity to store large arrays, has been overcome by twe devices:

(1) ORIGEN stores only the nonzero elements of the normally sparse tran-
sition matrix and two vectors that are used to locate them; and {2) the
cxpansion of the matrix exponential function is performed using a recursion
relation which requires storage of only cne vector in addition to the
solution. Computaticnal difficulties arising from eigenfunctions with
very large eigenvalues (corresponding to nuclides with very short half-

lives) are avoided by using asymptotic solutions of the nuclide chain

equations for the conditions of secular and transient equilibrium.

The ORIGEN code has been designed to be extremely versatile in its
applications. It is capable of computing isotopic compositilions of fuel,
fission products, and cladding in both fixed and fluid fuel reactors.
The library of nuclear data that has been compiled for use with the code
is sufficiently extensive to treat 235U and 239Pu fuels in both Tast and

233

thermal spectra, and fission of U in thermal spectra. The library also
contains multigroup photon release rates for the Tission products and the
heavy metals, which permits the calculation of gamma-ray spectra in spent
and refabricated fuels. One other impcortant feature of the code is that
The matrix exponential technigue has been developed to sclve a nonhomo-
geneous systen of equations. This fealture makes it possible for ORIGEN

to be employed in calculating the accumulation of activity in processing

plants, in waste disposal operations, and in the environment.
The remainder of this report consists of three major sections, Section
2 develops the mathematical techniques used in the ORIGEN cowputations.
Section 3 summarizes the information that is contained in the library of
nuclear data. Section 4 examines the function of each subroutine in the
program, discusses programming considerations, describes the input for
the code, and givesg input for a sample problem, Output for a sample
calculation is included in the Appendix. The individual sections are
intended to be independent, so that Section U4 can be employed as a user's

manual without reference to preceding sectlons.

A complete code package has been deposited with the Radiation Shielding
Tnformation Center. Inguirieg or requests for the code may be mailsd to:
Codes Coordinator
Radiation Shielding Information Center

Oak Ridge National Laboratory

- - 5
Oak Ridge, Tennessee 37830 $ c Al
J

P

or telephoned to:

Area code 615, W83-8611, ext. 3-694k4, or
FTS XX - 615-L83-60LL,

Acknowledgments. — The author is deeply Indebted to a number of

 

individuals who contributed to the development of the ORIGEN code over

a period of several years. The program was initiated by J. P, Nichols,
who supervised the development of the code. Much of the nuclear data was
compiled by E. D, Arnold” with the assistance of H. P, Soard. The author
was assisted in the programming by R. S. Dillon "~ and Mrs. L. G. Knauer,*
and is deeply grateful for the efforts of Mrs. 1. G. Loope, who prepared
the manuscript. Editing was done by C. W. Kee, who now has the task of
data revisions and program modifications. TFinally, the author appreciates
the encoursgement and suggestions of a number of userz of the program who

have patiently awaited the publication of this report.

 

*
Pregsent address: Osk Ridge Gaseous Diffusion Plant.

Present address: AECOP, Oak Ridge, Tenmn.

TPresent address: Robertsville Junior High School, Cak Ridge, Tenn.
1.

z.

4=

i0.

11,

1.1 References for Section 1

H. Bateman, Proc. Cambridge Phil. Soc. 15, 423 (1910).

M. P. Leitzke and H. C. Claiborne, CRUNCH — An TBM-70L Code for
Calculating N Successive First Order Reactions, ORNL-2958

 

 

(Cet. 24, 1960).

D. R. Vondy, Development of a General Method of Explicit Solution
to the Nuelide Chain FMquations for Digital Machine Caleunlations,

 

 

ORNL-TM-361 (Oct. 17, 1952).

H. H. Van Tuyl, ISOGEN — A Computer Code for Radioisoctope Generation

 

Calculations, HW-83755 (1964).

R. 0. Gumprecht, "Computer Code RIBD," Trans. Am. Nucl. Soc. 12(1),
1h1-hb2 (June 1969),

L. Peage, DEEMS, A FORTRAN Program for Solving the First Degree
Coupled Differential Equations by Expansion in Matrix Series,
TSI-49 (October 1963).

 

H. H. Poynter and J. Suez, "Automatic Digital Set-up and Scaling of
Analog Computers,” Proc. 1963 Joint Automatic Control Conf., . 156.

 

B. H. Duane, in Physics Research Quarterly Report, Ccl.-Dec. 1963,
HW-30020 (196L).

 

H. B. Krug, J. E. Olhoeft, and J. Alsina, Chap. 8 in Supplementary
Report on Evaluation of Mass Spectrometric and Radiochemical Analyses

 

of Yankee Core T Spent Fuel, Including TIsotopes of Elements Thorium

 

through Curium, WCAP-56086 (August 1969).

S. J. Ball and R. K. Adams, MATEXP, A General Purpose Digital Computer
Program for Solwving Ordinary Differential Equations by the Matrix

 

 

Exponential Method, ORNL-TM-1933 (August 1907).

 

M. ®, Fowler and R. M. Warten, 1BM J. Res. Develop. 11, 537 (1967).
2. DESCRTPTION OF MATHEMATICAL METHOD

A general expression for the formation and disappearance of a nuclide

by nuclear transmutatlon and radioactive decay may be written as Tollows:

N v
I Lij?\jxj + ¢ Z IikUka - (?\i + qfioi).zs.i (1 =1,...N), (1)
J=1 =1,

where Xi ig the atom density of nuclide i, hi is the radioactive disinte-
gration constant for nuclide 1, S; is the spectrum-averaged neutron
absorption c¢ross section of nuclide i, and 4.. and fik are the fractions
of radicactive disintegration and neutron absorption by other nuclides
which lead to the formation of species 1. Also in Eg. (1), ¢ is the
position- and energy-averaged neutron flux, which is also assumed to be
constant over short intervals of time, Rigorously, the system of equations
described by Eq. (1) is nonlinear since the neutron flux will vary with
changes in the composition of the fuel. However, the variation with time
is slow and, if the neutron flux is considered to be constant over short
time intervals, the gystem of Eq. (1) is a homogeneous set of simultaneous
first-order crdinary differential equations with constant coefficients,

which may be written in matrix notation:

»

f-ax. (2)
Equation (2) has the known solution
X - exs (48) £(0) (3)

S

where %(O) is a vector of initial atom densities and A dis a transition
matrix containing the rate coefficients for radiocactive decay and neutron
capture. The function exp (At) in Eg. (3) is the matrix exponential

N

2
function, a matrix of dimension N7, which is defined as

(46)° D (at)”
exp (A) = L+ At + o+ ... = ) o ()
if one can generate this function accurately from the transition matrix,

then the solution of the nuclide chain equations is readily obtained,

2.1 Compuctation of the Matrix Exponential Series

Two principal difficulties are encountered in employing the matrix
exponential technique to solve large systems of equations: (1) a large
amount of memory is required to store the transition matrix and the
matrix exponential function, and (2) computational problems are encoun-
tered in applying the matrix exponential method to systems of equations
with widely separated elgenvalues. The generation and storage of the
transition matrix are explained in Sect. 2.5. 'The computation and storage
of the matrix exponential function have been facilitated by developing a
recursion relation for this function which does not require storage of
the entire matrix, Thus it is possible to derive an expression for one
nuclide in Eg. (3) which is given by

@©

n

Xi(t) = ) Ci 3 (5)

]

n=0Q

n . . .
where Ci 1s generated by use of a recursion relation

0
¢ = x;(0) (62)
N
ntl 0t ‘ n -
Cl Con+l E; aijcj 2
J=1

Here, aij is an element in the transition matrix that is the first-order

rate constant for the formstion of species i from species j. This algorithm
} N n . .y . i

requires storage of only one vector C° in addition to the current value

of the solution.

In performing the summation indicated by Eq. (5) it is necessary to
ensure that precision in the answer will not be lost due to the addition

and subtraction of nearly equal large numbers. In the past, this objective
has been accomplished by scaling the time step by repeatedly dividing
by 2 until the norm of the matrix is less than some acceptable small
value, computing the matrix exponentizl functicn Tor the reduced time
step, and repeatedly squaring the resulting matrix to obtain the desired

—

tine step.

Such a procedure would be impractical for a computation
involving large numbers of nuclides (many of which have short half-lives)
corresponding to large norms of the é} matrix. However, it is ,just for
these short-lived isotopes that the conditions of secular and transient
equilibrium are known to apply. Thus, in the compubtations performed by
ORIGEN, only the compositions of those nuclides whose diagonal matrix
elements are less than a predetermined value are computed by the matrix
eprnential method. The concentrations of the isotopes with large diagonal
matrix elements are computed using an analytical expression for the condi-

tions of secular or transient eguilibrium, as described in Sect, 2.2.
. h 2

Lapidus and Luu53 have shown fthat the accuracy of the computed mabrix
exponential function can be maintained at any desired value by controlling
the time step such that the norm of the matrix At is less than a predeter-
mined value which 1s fized by the word length of the digital computer
used in the calculations. They define a norm of the matrix é, denoted

by [AT, which is given by the smaller of the maximum-row sbsolute sum

, max E:
i 7
J

and the maximum~column absolube sum:

[A] = min {max >: ‘a .
. i
I3

 

 

aijl} ’ (7)

where Iaij’ denotes the absolute value of the element ajj' They show that
the maximum term in the summation for any element in the matrix exponential

n
- . n . .
function cannot exceed ai oo where n is the largest integer not larger than

[A7t, Consideration of the word length of the computer used to perform
the calculations will indicate the maximum value of n that can be used
while obtaining a desgired degree of significance in the results. Using
double precision arithmetic, the IBM 360 cperating system can perforn
operations retaining 16 significant decimal figures. In the ORIGEN code
the norm of the transition matrix is restricted to be legs than

[A] < -2 1n 0.001 = 13.8155, so that the maximum term that will be
celculated will be approximately 49,000. Thus, a value as small as
exp (-13.8155) = 10"6 can be computed, while retaining five significant
figures. A sufficient number of terms must be added to the infinite

summation given by FEg. (5) to ensure that the series has converged. The

 

m

mth term in the series for e[A] is equal to [i? , waich, for large values
-1/2

of m, can be approximated by (Léfifs)m(Bmfl) 1/ using Stirling's approxi-

mation. The value of the norm, [A], is calculated by the code; and m is

set equal to the largest integer in % [A] + 5, which has been determined

as a "rule of thumb" for the number of terms necessary to limit the error
to <0.1%. Thus, for [A] equal 13.8155, 53 terms will be reguired in the

summation., The absolute value of the last term added to the summation

in this case will be less than 6.4 x 10_10, which is sufficiently small

compared with 10"6. It has been observed that the norm is usually less
than its maximum value and, in most cases, 3C or fewer terms are required

Lo evaluate the series.

It has been mentioned that, in previous applicationgsof the malrix
exponential method, the restricticn of the size of the norm of the
transition matrix necessary to treat nuclides with large elgenvalues
was accomplished by repeatedly dividing the matrix by 2, and the final
value of the matrix exponential function was obtained by repeatedly
squaring the resulting intermediate matrix exponential function. In
the present application, the suggestion of Ball and Adamsh that the
transitions involving isotopes with large decay constants be considered
"instantaneous" was adopted; that is, if A » B - C and if the decay
constant for B is large, the matrix is reformulated as if C were formed
from A directly, and the concentration of B is obtained by an alternative
technique. Similarly, if the time constant for A is very large, the
transition matrix is rewritten as if the amcunt of isotope B initially
present were equal to A + B, and only the transition B - C is obtained
by the matrix exponential technique. This reduction of the transition
maltrix and the generation of the solution by the matrix exponential

method are performed by the subrcutine TERM (see Sect. 4.1).
2.2 Use of Asymptotic Solutionz of the Nuclide Chain
Equations for Short-Lived Isotopes

The numerical technigues described in Sect. 2.1 are applied only
to obtain the golutions for isotopes that are sufficiently long-lived
to satisfy the criterion thal the norm of the transition matrix be less
than 2 1ln 1000. Short-lived isotopes are treated by using linear combi-
nations of the homogeneous and particular solutions of the nuclide chain
equations that are computed using alternative procedures. The guantity
of a short-lived nuclide (originally present at the begimning of an
interval) that remains at the end of the interval is computed in subrou-
tine DECAY using a generalized form of the Bateman equations which treats
an arvitrary forward-branching chain. The generalized treatment is
achieved by searching thréugh the transition matrix and forming a queue
of all short~lived precursors of an isotope. The Bateman equation solution
ig then applied to this queue. The queue is terminated when an isotope
having no short-lived precurscrs is encountered. The algorithm also has
provisions for treating two isotopes with equal eigenvalues and for

treating cyelic chains.

Bateman's solution for the ith member in az chain at time t may be

 

written in the form:5
. ~ds b

Ni(t) = Ni(O)e

i-1 i-1 . -

Py omoy | ) 2yt e () Pt |
k — (d' - d') uj"}l)j ‘1‘ d]:-] - d-' ?
k=1 e 1 J n=k R J
J n#]j

where NJ(O) is the amount of isotope J initially present and the members

of the chain are numbered consecutively for simplicity. This method of
i-1

solution used the conventicn that T[]
n=kK

and that the empty product (x = 1) is equal

an+l,n is equal to the product

"k1,k, Tkie, kel P4,1.17

to unity. The notation a. 5 Lor the first~order rate constant is the
-2
10

il
1
w©

same as that described in Sect. Z.1, and di In the present

spplication, Egq. (8) is recast in the form

 

 

~dit
N, (t) = I, (O)e
-1 i1
qvfi i-1 Bil 1l * exp (mdjt) -
+ ZJ N (0) 1 2 E: d
k 9y ] (ds
k=1 n= jak
11
by multiplication and division by N d . The first product in Eg. (9)
n=k

has significance because it is the fraclion of atoms of isolope k that
follow a particular sequence of decays and captures. If this product
becones less than 10—6, contributions from nuclide k and its precursors
to the concentration of nuclide 1 are neglected. The inner summation in
Eq. (9) is performed in double precision arithmetic to preserve accuracy.
This procedure is unnecessary for evaluating the outer summation because
all the terms in this sum are known to be positive. The difficulties
described by Vondy in applying the Bateman equations for small wvalues of
dit do not occur in the present application since, when this condition
occurs, the matrix exponential solution is employed. The matrix exponen-
tial method and the Bateman equations complement each other; that 1s, the
former method is qguite accurate when the magnitude of the characteristic
values of the equations tc be solved 1s small, whereas the Bateman
solution encounters numerical problems in this range. TFor the case
where two isotopes have equal removal constants (d; = dj), the second

summation in Egq. (9) becomes:

i-1 ]
\ -d st i-~1 d,
E; d.t e I —— (10)
:{_ Il i
ik n { J

n#gj

An analogous expression is derived for the case when 4, = dj. These forms
of the Bateman equations are applied when two isotopes in a chain have
the same diagonal element or when a cyclic chain 1s encountered, in which

case & nuclide is considered to be its own precursor.
11

In the situation where a short-lived nuclide has a long-lived
precursor, a second alternative solution is employed. 1In this instance,
the short-lived daughter is assumed to be in secular equilibrium with
ite parent at the end of any time Interval. The concentration of the
parent is obtalined from subroutine TERM, and the concentration of the
daughter is calculated in a subroutine named EQUIL (see Sect. 4.1) by

setting Eq. (3) equal to zero:

[
S

N

. =0 = :

Xy ) E: aij Xj . (11
J=1

Equation (11), which is a set of linear algebraic equations Tor the
concentrations of the short-lived isotopes, is readily solved by the
Gauss-Seidel iterative technique.6 The coefficients in Eq. (11) have
the property that all the diagonal elements of the matrix are negative
: and all off-diagonal elements are positive. The algorithm involves
inverting Eq. (11) and using assumed or previously calculated values

for the unknown concentrations to estimate an improved value, that is,

N
+1 . i
& :....;.Ll . (12)
1 ciii :LJ J

3=1
JH

The iterative procedure has been found to converge very rapidly since,
for these short~lived isotopes, cyclic chains are not usually encountered

and the procedure reduces to a direct sclution.
2.3 Application of the Matrix Exponential Method
for Nonhomogeneous Systems

Certain problems that involve the accumulation of radicactive
materials at a constant rate and are of engineering interest require
the solution of a nonhomogeneous system of first-order linear, ordinary
differential eguations. I[n matrix notation, one writes

%: ,\X_,Jr%' (13)

Q=

This set of equations has the particular solution

x(t) = [exp (88) - 1A B (14)

~

¢

. ~1 . . . s axo s . -
provided that A = exists. Substituting the infinite series representation

for the matrix exponential function, one obtains

 

At (at)”
X(6) = [L+ Sr+ =+ .1 B (152)
A 2 \
=\ /) T ) B (15b)
m=0

The particular solution may also be expressed as the sum of an infinite

serles:

whose terms are generated by use of a recursion relation

1
Dy =bst, (17a)
N
a+1 t ja
Yoot o 43 DJ (170)
J=1
Once again, the algorithm isg applied only to long-lived nuclides, and the
concentrations of the short-lived nuclides are obtained by an alternative

technique. In this situation, Hg. (11) is modified to the form

N
¥, = 0 = 24 Ay Xs b, (18)
J=1

and is solved by the Gauss-Seidel method. After the homogeneous and
partlicular sclutions have been cobtalned, they are added to obtain the

complete solution of the gsystem of eguations.

2.4 Computation of Neutron Flux and Specific Power

In order to compute changes in fuel composition during irradiation
at constant power, it is necessary to take into account changes in the
neutron flux with vime as the fuel is depleted. At the start of the
computation, the known parameters are the initial fuel composition and
the constant specific power that the fuel must produce during a time
interval. The instantaneous neubtron flux may be related to the fuel
composition at a fixed time by the equation

P 3.20x 107 5, (19)

where P is the specific power, in MW per unit of fuel; ¥ is the macroscopic
fission cross section, in cm? per unit of fuel; and ¢ is the instantaneous
neutron flux, in neutrons per cm?-sec. The constant in Zg. (19) is derived
by assuming a value of 200 MeV per fission. An approximate expression for
the value of the neutron flux as a function of time is obhtained by expansion

in a Taylor series about the start of the interval:

6

. 2 o . 2 . 0_1
@) = 3.125 x 1017 p r|__z:(o)'l L 2O 5 (’*[2(0” - 2(0) MO)) bt (

$(0)7 5(0)°

or

s(t) = 9(0) {1 - t%%—%+§-—(—?ufil) ] (200)

2(0)2 -
14

The average neutron flux during the interval is obtained by integrating

over the interval and dividing by t:

7
]

2(0) . t2 /25(0)” - £(0)%(0)
L..l - ‘ 1(O2 " ‘é_' ( 2(0)2 )> * ...] : (21)

oo et

¢ = ¢(0)

[\/‘

Here, the notation £(0) is used for the macroscopic fission cross section
at the start of the time interwval, and i(O) and i(O) are the first and
second time derivatives evaluated at the start of the interval. The
values of é(O) and f(O) can be evaluated since %(O) = A X(0) and

%(O) = éfi%(o) = é? X(0). FEquation (10) is used in the computer program
in subroutine FLUXO to estimate the average flux during an interval,
based on conditions at the start of the interval. The term involving

the second derivative is only employed for the first time interval where,
for some isotopes, X(O) is zero but %(O) is nonzero. The average power
produced during a time interval for a fuel in a fixed neutron flux is
estimated from the initial composition using a similarly derived equation:

. .o z
P = 3.20 x 1077 px(0) [1+ £(0) £+ Ho) -+ ...] (22)

In order for the above procedures to estimate the average neutron flux

or average specific power correctly, the changes in neutron flux during
thie interval must be relatively small. If the average value of either

of these guantities differs from the initial value by more than 20%, a

message Will be printed out advising the user to employ smaller {ime

increments.

2.5 Construction of the Transition Matrix

An extensive library of nuclear properties of radiocactive isotopes
has been compiled for use with the ORIGEN code. {See Sect. 3 for details.)
The data are in the form of half-lives, fractions of transitions that
produce a given nuclear particle, cross sections, and fractions of

absorptions thatl yield certain particles. These data are read from
15

the library tape and processed into a form for use by the mathematics

routines in subroutine NUDATA (see Sect. 4.1 for description of NUDATA),

nuclides uvsing the present ccde., However, stralghtforward construction

of a generalized transition matrix would require the storage of an

800 x 800 array, which would tax the storage capacity of the largest
computers available today. On the other hand, the transition matrix is
normally very sparse, and storage requlrements can be reduced gubstantially
by storing only the nonzero elements of the matrix and two relatively

small vectors thatl are used to locate the elements. Subroutine NUDATA

is also used to generate the compacted transiftion matrix and the two

storage vechbors.

Subroutine NUDATA processes The library tape by reading a six-digit
identifying nuwber, NUCL(I), for each nuclide, Tollowed by the half-life
and the fraction of each decay that occurs by several competing processes.
A zecond card, which contains neutron absorphtion cross sections for (n,y),

o

(n,@), n,p), (n,2n), (n,3n), and (n,fission) reactions for one of four
reactor spectra, is then read. The six~diglt identifying number is equal
to Z * 10,000 + W * 10 + I3, where 7 is the atomic number, W is the atomic
welght (in integral atomic mass units), and I3 is either O or 1 to indi-
cate a ground state or a metastable state, respectively. This information

is processed into a compacted transition matrix, as described below.

first, the half-life is used to calculate the radiocactive digintegra~-

ct

ion constant, A. IFirst-order rate constants for various competing decay
processes are calculabted by multiplying A by the fraction of transitions
to that final state. The product nueclide resulting from each nuclear
transition is next identified by addition of a suitable constant to the
six-digit identification number for the parent nuelide. {(For example,
for a B decay, 10,000 is added to the parent identifier; for nsutron
capture, 10 is added; or for isomeric transition, the quantity -1 is
added.) Two arrays are constructed: the first, NPROD(J,M), contains

all the products which can be directly formed from any nuclide J by the
transitions considered in the library; and the second, COEFF(J,M), con-

tains the Tirst-order rate constants for the corresponding transition

93]
16

When these arrays have been ccnstructed, a search of the NPROD array is
conducted to identify all the parents of a given nuclide I. [Nuclide J

is a parent of I if NPROD(J,M) equals NUCL(I) for any reaction of type M.]
When a parent of nuclide 1 has been located, the value of the correspond-
ing coefficient aij in the transition matrix is equal to COEFF(J,M).
However, direct storage of aij in a square array would require an exces-
sive amount of storage. Hence, this procedure 1s avoided by incrementing
an index, N, cach time a ccefficient is identified. The coefficients

are stored sequentially in a one-dimensional array, A(N); the value of

J is stored in another one-dimensional array, LOC(N); and the total number
of coefficients for production of nuclide I are stored in a third array,
NANO(T). VWhen all of the coefficients for every nuclide have been stored,
the NfiNO(I) array is converted to indicate the cumulative number of matrix
coefficients for all the isotopes up to and including I [i.e., N¢NO(T + 1)
= NYNO(I) + N@NO(Ll + 1) for all I greater than 1]. After this procedure
has been executed, the NfiNO array is a monoctonically increasing list of
integers whose final value is the number of nonzero, off-dlagonal matrix
elements in the transgition matrix. This final value is preserved separ-
ately as the variable NON, TFor computational convenience, the wvalues of
the diagonal .matrix elements are stored in a separate vector, D(I). To

perform the multiplication of the transition matrix by a vector (e.g.,
N

ii = ¥ aijxj), as is required to execute the algorithm described in
h J=1

Sect. 2.1, the operations described in the flow chart given in Fig. 2.1

are employed.

Two types of data In the nuclear library require a departure from
the procedure Jjust descrived, In the case of neutron-induced reactions,
1t i1s necessary to specify the neutron flux before first-order rate
coefficients can be calcvlated as products of flux and cross sections.
At the time the matrix is generated, the neutron flux is unknown., Also,
to perform a fuel depletion calculation, the flux must be permitied to
vary with time. Thus, when the nonzero, off-diagonal matrix elements
for isotope 1 are stored, all those for formation by radicactive decay

are grouped first and are Tollowed by those for formation of T by neutron
17

ORNL DWG 72 -7938

 

I =1
N= 4
4
X(I) = D(IIx X(I) |e

 

 

 

 

 

 

 

 

 

 

 

« FALSE*

 

J= LOC (N}
X (1) =X {1} 4+A {N)n X {J)

3

NaN+1

 

 

 

 

 

 

 

  

 

  

<IFIN.LE.NON)

| «mALSE"

Pig. 2.1, Flowchart Illustrating Computational Algorithm Executed
to Perform the Matrix Caleoulation X = A X.

R
18

capture. Another vector, KD(T}, is also generated and used in a manner
analogous to NPNC(T). Tt initially is the number of radicactive parents
of isotope I, and the difference NPNO(i) - KD(I) represents the number of
coefficients for formation of 1 by neutron capture. The variables A,
LAC, NPNO, and KD are all generated in subroutine NUDATA and are stored
in labeled common /MATRIX/. They are used to perform calculations in
subroutines FLUXO, DECAY, TERM, and EQUIL (see Sect. 4,1 for description

of subroutines).

The second exception to the standard procedure for comstructing the
transition matrix involves the coefficients corresponding to the fission
product yields. The nuclear data library ccntains direct [fission yields
for the formation of fission product isotopes from several fissionable
nuclides. When these yields are multiplied by the fission cross section
for the fissile nuclide and the neutron flux, the result is a first-order
rate constant for production of fission product isotope I by fission of
nuclide J. Hence, for these data, the construction of The arrays NPROD
and COEFF and the subsequent search procedure are not reguired. The
coefficients are entered directly into the A vector, and the correspond-
ing value of J that identifies the fissioning nucleus is recorded in the

LYC array.

2.6 References for Section 2

1. B. H. Duane, in Physics Research Quarterly Report, QOct.-Dec. 1963,
HW-80020 (1964).

 

2. H. E. Krug, J. E. Olhoeft, and J. Alsina, Chap. 8 in Supplementary
Report on Evaluation of Mass Spectrometric and Radiochemical Analyseg
of Yankee Core 1 Spent Fuel, Including Isotopes of &lements Thorium
through Curium, WCAP-6086 (August 1969).

 

 

3. L. Tapidus and R. Luus, Optimal Control of Engineering Processes,
pp. 45-L9, Bleisdell Publishing Co., Waltham, Mass., 1967,

 

4., S. J. Ball and R. K. Adams, MATEXP, a General Purpose Digital
Computer Program for Solving Ordinary Differential Equationg by
the Matrix Exponential Metnod, ORNL-TM-1933 (August 1967).

 

 

 
19

5. D. R. Vondy, Development of a General Method of Explicit Solution
to the Nuclide Chain Equations for Digital Machine Calculations,
ORNL-1M-361 (Oct. 17, 1962),

 

6. L. Lapidus, Digital Computation for Chemical Fngineers, pp. 259-62,

 

McGraw~Hill, New York, 196%.

3. DESCRIPTICN OF NUCLEAR DATA LIBRARY

An extensive library of nuclear data has been compiled and recorded
on magnetic tape for use with the ORIGEN code, The tape consists of sgix
data files; three of these contain information on the decay schemes and
neutron absorption cross sections for then813 isotopes now included in
the library, and the other three contain multigroup photon production
rates that result from radiocactive decay of these nuclides., The first
data file catalogs the properties assocliated with the cladding and
structural materials; the second is comprised of nuclear data for the
heavy metals in the fuel; and the third file describes the nuclear
properties of the fission products. Data files 4, 5, and 6 contain
photon yields per disintegration for the éladding, fuel, and Tission
product nuclides, respectively. The Tollowing sections describe in
detail the type of data recorded on the tape and the format used, and

document the sources of the data.

3.1 Nuclear Properties of Cladding and Structural Materials

The nuclear properties for the individual isotopes in each of the
first three data filles are recorded on five card-image records. The
first card image contains information that is independent of the reactor
spectrfim (e.g., half-1life, disintegration energy, ete.). The subsequent
four card images contain neutron capture data for four reference reactor

spectra.
The first card image is read in the form:

60 READ(7,9034,END=260) NUCL(I), DLAM, IU, ¥FB1, FP, FPL,
FT, FA, FSF, (1), Fu{1), ABUND(T), wMPC({I), AMPC(T)

9034 FERMAT(IT, F9.3, 11, 5F5.3, 1PE9.2, OP2F5.3, F7.3, 286.0)
20

Tn this instruction, NUCL(L) is a six~digit identification number for

isotope I. The variable NUCL{1T) is egual to:
Z * 10,000 + W * 1O + 15,

where 7 is the atomic number, W is the atomic weight, and IS5 is equal to

0 or 1 for a ground state or metastable state, respectively. The variable
TLAM is the physical half-1ife of the radicactive nuclide in units desig-
nated by the key, IU, according to Table 3.1, The definitions of the

next six variables are given in Table 3.2. ‘The fraction of disintegra-

tions which are negalron emissions 1s obtalned by difference:
FBR = 1.0 - ¥P - FA - FT - FSF,.

1 . : L . .
The tables of Lederer et al, constitute the principal source of information

on half-lives and decay schemes of the isotopes.

The variable Q(I) is the total amount of energy released by radio-
active decay as recoverable heat, in MeV per disintegration. It does not
include the energy of the neutrinos released in beta decay transitions.
The variable FG(T) is the fraction of the total energy that is associated
with gamma radiation. Only photons of energy greater than Z00 keV are
considered to contribute to the fraction of gamma energy; lower-energy
vhotons are included in the total energy, however. The energy per dis-
integration associated with alpha decay and photon emission is obtained
directly from the decay schemes given in ref. 1. The amount of energy
released in a beta decay evenl is calculated from the abundance and
maximum beta energies given in ref. 1 by using the results of the SPECTRA
code of Arnold.2 This code computes the average beta energy based on the
maximum negatron or positron energy and the degree of forbiddenness of
the transition, using the Fermi theory of beta decay. Alsc included in
the fraction of gamma-ray energy is the contribution from bremsstrahlung
radlation. This quantity is calculated, again using the SPECTRA code,

for beta decay taking place in a uranium dioxide matrix.

The varisble ABUND(I), the percent abundance cf naturally occurring
isotopes, is obtained from vef. 1. The variables WMPC(1) and AMPC(I) are
the radiocactivity concentration guides (RCGS) for continuous ingestion in

unrestricted areas as given in Table II, columns T and II, of Part 20 of
21

Table 3.1. Key to Use of Variable IU to Indicate
Units of Half-Life in Nuclear Data Library

 

b
\_,4
5
e
d—
o]

 

hr

days
years
stable
103 years

P
O
107 years

W @ N Ovwu Fow o

107 years

 

 

 

Table 3.2. Definitions of Variable Names Used in Nuclear Data Library
Name of
Variable Definition
FBL Fraction of beta decay transitions that result In a
preduct nuclide in an exclted nuclear ctate
P Fraction of transitions that take place by positron
emission
Pl Fraction of positron emissions that result in a
product nuclide in an excited nuclear state
FA Fraction of transitions that take place by alpha
particle emission
FT Fraction of disintegrations from an excited nuclear
gtate to the ground state
st Fraction of disintegrations that take place by

spontaneous fission

 
22

Title 10 of the Code of Federal Regulation53 (10 CFR 20). The values
included in the library are the lower of the wvalues given for soluble

and insoluble compounds of the nuclides, Several heavy metal isotopes
not listed in the tables are of sufficient importance in radiocactive
waste disposal that values for their RCGs have been estim.atedu by using
the methods given in ICRP Publication 2 (ref, 5) for occupational workers
and dividing the results by 10. The RCGs for all other isotopes not
listed in the tables are set equal to unity, which is equivalent to

excluding these isotopes from the calculations.

A second card image, which contains data for neutron-induced reactions
for one of four reactor spectra, is now read. The form of the READ state-

ment is:

READ(7, 9035) SIGTH, FNGl, FNA, ¥NP, RITH, FINA, FINP, SICMEV, FN2NL,
FFNA, FFNP, IT.

9035 FPRMAT(7X, F9.2, 3F5.3, F9.2, 2¥F5.3, F9.2, 3F5.3, T80, Il)

The notation used in this instruction is described in Table 3.3 for the
case of a thermal reactor. 1In the thermal reactor libraries the 2200-m/sec
cross sections are taken from the compilation of Stehn et al.,” the infi-
nite dilution resonance integrals {rom Stehn 93_2},6 and Drake,7 and the
fission-spectrum-averaged cross sections for (n,&) and (n,p) reactions

from Alter and Weber,B Fission-spectrun-averaged cross sections for

9

(n,2n) reactions are obtained from Pearlstein,” or by integrating the
energy-dependent cross sections given in ref, 6 over a Cranberg fission
spectrum. For thermal reactors, effective thermal neutron cross sections
are obtalned by weighting these three energy-group cross sections with
spectral indices. For example, the total neutron absorption cross section

1s calculated as:
TfiCAP = SIGTH * THERM + RITH * RES + SIGMEV * FAST.
Here, THERM, RES, and FAST are defined as follows:

. . ) 1 X
THERM = ratio of the neutron reactlion rate for a ? absorber with

a population of neutrons that has a Maxwell-Boltzmann
Table 3.3.

23

Names of Variables Used in Reading Spectrum-Dependent

Data for Cladding and Structural Materialg in Thermal Reactors

 

 

Name of
Variable Description
STGTH Total 2200-m/sec neutron absorption cross
section, barns
FNGL Fraction of thermal neutron cgptures that
produce a product nuclide in an excited
nuclear state
FNA Fraction of thermal neutron abscrptions that
are (n,d) reactions
FNP Fraction of thermal neutron absorptions that
are (n,p) reactions
RITH Rescnance integral (above 0.5 eV) for all
epithermal neutron absorption,
[as]
e l - .
J T GU(E) dR, barns
0.5
FINA Fraction of rescnance absorptions that are (n,x)
reactions
F'TNP Fraction of resonance absorptions that are (n,p)
reactions
STGMEV Flssion-spectrum-averaged cross section Tor all
reactions with a threshceld above 1 MeV, barns
FI2IL Fraction of (n,2n) reactions that result in an
excited isomeric state of the product nuclide
FI'NA fraction of high-energy reactions that are of
(n,a) type
FENP Fraction of high-energy reactions that are of
Vo4
(n,p) type
1T An dindex indicating the reactor spectrum over

which cross secticns have been averaged

 
2

distribution of energies at absolute temperature, T, to

the reaction rate with 2200-m/sec neutrons

T

RES = ratic of the resonance flux per unit lethargy to the

thermal neutron flux.

FAST = 1.L45 times the ratio of flux above 1 MeV to the thermal

neutron Tiux,

These definitions arise from three assumptions: (1) for thermal neutron
energies, the absorption cross section for an isotope variles wita the
reciprocal of the neutron speed; (2) for the resonance region, the
neutron flux varies as the reciprccal of the neutron energy; and (3) in
the region above 1 MeV, the neuntron spectrum has the same cnergy depend-
ence as the fission spectrum. It is pointed out that the high-energy
group includes only reactions with thresnolds above 1 MeV, Reactions
with components at lower energies are included in the thermal and
resonance group. When the average cross section is defined in the

manner described above, the appropriate flux to be used for calculating
neutron reaction rates is the Total thermal flux, The total thermal flux
is the value calculated and printed out by the program when initial com-
positions, specific power, and spectral indices are specified and the
flux is computed by the code. The variable 1T distinguishes between
reactor spectra and has a value of zero, or 1 through 4. The numbers

1 through & indicate that the dala are Tor a particular spectrum, as
designated in Table 3.4. A value of zero for T indicates that the nuclide

is not included in the library for a given reactor type.

For the ILMIBR library, IT is equal to 3 and tThe varlables 1in Table
3.3 have a somewhal different meaning. In this instance, SIGTH is the
spectrum~-averaged (n,Y) cross section; the varisble RITH is not used;
and the variable SIGMEV is the sum of the (n,2n), (n,x), and (n,p) cross
sections, averaged over a fast reactor spectrum. The spectral indices
have no meaning in this case and are equal to 1.0 (the reference flux

is then the total neutron flux). The spectrum-averaged neutron capture
25

Table 3.4, Value of the Variable IT Corresponding
to Fach Reactor Type

 

 

iT Reactor Type
1 HTGR

2 LWR

3 IMEBR

) MSER

 

crogs sections that are given in the library for isotopes with atomic
numbers less than 22 were computed by integrating numerically the data
of ref. 6 over the fast reactor spectrum of Kusters and Metzenroth,lo
Spectrum~-averaged neutron capture crogs sections for isotopes with atomic
rumbers greater than 21 were estimated by Arnold,ll wno used correlations

developed by Macklin and Gibbons 2’13

to extrapolate cross-section data
over the energy range of interest and then integrated the data over an
approximation to the spectrum of Kusters and Metzenroth, which was con-
structed from the sum of eight Maxwellian functions of different average
energies, Tae spectrum-averaged cross sections for (n,2n), (n,x), and
(n,p) reactions were obtained either by integrating numerically the
energy-dependent cross sections (if given in ref. 6) or by assuming that
the high-energy portion of the neutron spectrum had the same energy
dependence as the fission spectrum and weighting the fission-spectrum-

: - . 3
averaged crosg sectlons of Pearlstelng and Alter and Weber.

Two steps are used in reading the nuclear data; first, a card image
containing the permanent information is read and, then, a second-card
image that contains spectrum-~dependent information is read, depending
on the value of an input variablie, NLIBE. If the value of the variable
IT on the second-card image 1s equal to NLIBE, the data on both cards

are processed in the manner described in Sect. 2.5, If IT is equal to
26

zero, the nuclide is ignored and data are read for the next nuclide on
the tape. This procedure is repeated until an end-of-file (EOF) mark
is encountered, at which time contrcl is transferred to another part of

the program.

3.2 Nuclear Properties of the Isotopes of the
Actinide Elements and Their Daughters

The nuclear properties of the isotopes of the actinide elements are
read in a manner similar to that described above for the light elements.
First, permanent data are read from a card image in the previously
described format (Sect. 3.1), using the same variable names. However,
for the heavy metals, the field containing the isctopic abundances 1s
ignored. Neutron absorption cross sections are read from one of four
card images, depending on the recactor type. The instruction used to

read these data 1s:
READ(7,9037 )SIGNG, RING, FNGl, SIGF, RIF, SIGFF, SIGNZN, FN2N1, SIGN3N, IT
9037  FORMAT{7X, 2F9.2, F5.3, 4rg9.2, FL.3, F9.2, T80, 1)

The names of the variables used 1in this instruction are defined in
Taple 2.5 for the case of a thermal reactor. The variable IT has a
value of zero or of 1 through U4, depending on the type of reactor, and

is used as described above.

For the thermal reactor libraries, Tission and capture cross sections
for 2200-m/sec neutrons were obtained from the compilation of Stehn et al.,
and infinite dilution rescnance integrals were taken from the latter and

30
Trom Drake.7 The 2200-m/sec cross sections for the isotopes 235U, 83"“Pu

)
o2 237NP 2l a 243

through Pu, 5 Am, an Am were corrected for nonml/v behavior

using the tabulation of T/\J'escott,"uIL and the infinite dilution resonance

5 )
235 238U, 239, 2L0

integrals for the isotopes and Pu were corrected

for self-shielding using the data of Hansen and Roach.15 In the HIGR

232

: : . 236
library, these parameters for the isotopes Th through 3 U have also

been modified to obtain agreement with reactor mass balances for an

6 _
1160-MW(e ) HTGR.l For the PWR, the cross sections and resonance inte-
L/

grals have been adjusted to obtain agreement with fuel mass balances;
Table 3.5.

of Variables Used to Read Spectrum-Dependent Data

for Isotopeg of Actinide Elements in Thermal Reactor Libraries

 

Name of

Variable

Definition

 

RTNG

FNGL

FNZN1

SIGN3N

Thermal neutron {(n,7) cross section, barns
Resonance integral for (n,y) reactions, barns

Fraection of (n,y) absorptions that result in an
excited nuclear state of the product nuclide

Thermal neutron (n,fission) cross section, barns

Resonance integral for (n,Tission) reactions,
barns

Fissicn-spectrum-averaged (n,fizsion) cross sec-
tion for isotope having a high-energy threshold
for fission reaction, barns

Fission-spectrum-averaged (n,2n) cross section,
barns

Fraction of (n,2n) reactions that result in the
formation of a product nuclide in an excited
nuclear state

Fission-spectrum-averaged (n,3n) cross section,
barns

 
28

and the data in the MSBR library have been adjusted to agree with reaction
rates calculated by Baumann for the reference 1000-MW(e) MSBR.18 Fission-
spectrum~averaged cross sections for nucllides having a high-energy thresh-
old (& > 1 MeV) for the fission reaction were obtained by integrating
numerically the differential cross sections given in ref. 6. Cross
sections for {(n,2n) and (n,3n) reactions were obtained from Pearlstein.
Reactor-spectrum-averaged cross sectlons were obtained by assuming that
the reactcr spectrum for neutron energies greater than 1 MeV had the same
energy dependence as the fission spectrum, and by multiplying the fission-
spectrum-averaged cross sections by the ratio of the fraction of the
neutron flux zbove 1 MeV for the two spectra. (This ratio is contained

in the parameter FAST that was defined in Sect. 3.1.)

The variables RING, RIF, and SIGFF are not employed for the LMFER
library. Reactor-spectrum-averaged capture, fission, and (n,2n) cross
sections were generated by averaging the 18-energy-group AI/ENDF CTOSs

19

sections™” over the spectrum of ref, 10. Cross sections for (n,3n)
reactions were estimated by ratiocing the values given in ref, 9. The
procedure for reading this information frowm the tape for the actinides
is identical to thatl described Tor The cladding and structural materials

in Sect. 3.1.

3.3 Nuclear Properties of the Fission Prcducts

The nuclesar properties of each fission product isotope are contained
in five card-ilmage records. The first card contains data of a permanent
nature in the formatl described previocusly, again with the exception that
the field containing the isctopic abundances is ignored. The remaining
four cards consist of neutron absorption and fission product yield data
for the four reactor types described above. The form of the instruction

used to read these data is:

READ(7,9038)SIGNG, RING, FNGl, Y, IT
9038 FORMAT(7X, 2F9.2, F5.3, S5F9.2, T8C, I1)

All of the wvariables in this instruction except Y have tThe definiticons

given in Sect. 3.72. Radiative capture i1s the only neutron absorption
event that is treated for the Tission products. The 2200-m/sec cross

sections and infinite dilution resonance integrals for the thermal

'’

€1 2

, . 6 ,
reactors were oblained from Stehn et al. and from Drake;' those for
e 1l . o . _
the LMFBR were estimated by Arnocold, The variable RING is not employed
in the fast reactor library, and the variable SIGNG isg a spechtrum-averaged

1t 5" and

value‘in this instance. The variable Y is an array of dimension
contains energy-dependent direct Tission preduct yields for a number of
fissionable isotopes. Table 3.5 describes the information contained in
the Y array for each of the resctor spectra. Thermal fission yields and
fission yilelds for fast-neutron-induced fission of 232Th ware generated
from the compilation of Katcoff“o‘by conservatively assuming that all of
the direct yileld was to the first member of a chain when experimental
data were not avallable. DUirect figsion yields for fast-neutron-induced

2.58UJ ang 257

235 . . .
figsion of “)U, Pu were obtalned from Meek and Rider.

The data of Meek and Rider for thermal-neutron fission yields of dJ’U

. and 2390u were tested against the values in the ORIGEN library by com-
paring the calculated postirradiation properties of the fiszsion products

. computed using the two sets of yields with the afterheat values of Shure.
For postirradiation times less than 300 sec, use of the yields in the

ORIGEN library results in belter agreement with Shure's afterheat curves

Table 3.56. Fissionable isotopes for Which Direct Fission Yield Dats
Are 1ncludea in the ORIGEN Library for Various Reactor Spectra

 

 

 

s :
Reactor v(1)® v(z)*P 7(3)° ()P 1(5)%P

& RE o
HIGR 23354 235y 2380 p 2Py s 29pyt

* - ?/
LWR 2334 23544 235 ¢ 2 39py -
TMPRR 230 ¢ 238 ¢ -t

- e : .- 3 |
MSER 233y 23504 2320, _p 238 ¢ 239t
: %4 indicates that the yvield 1s for thermal-neutron~induced fission.

b, . .. . . . e
T indicates that the yield is for fission-spectrum-ensrsy neutrons.,
30

than does use of Meek and Rider's yield data. Hence, the present set of
fission product yields has been retained since, for the fission product
isctopes and properties in the ORIGEN library, they result in calculated
postirradiation properties that agree more closely with accepted values,
The disagreement is on the low sidej; and there is speculation that the
data of Shure may underpredict actual afterheats, which would aggravate
the disagreement. A later and more extensive compilation of fission

23

product yields by Meek and Rider -~ could not be considered at the present

writing, but may result in better agreement of the afterheat values.

In a light water reactor fueled with low-enrichment uranium, a few

s : o o 241 .
percent of the fissions will occur in the isotope Pu; in an LMFER,

fission will take place in both ZHOPu and ZulPu, Hence, estimates of
direct fission yields for fissicn of these isotopes are required to

treat such fuels. Bxtensive measurements of direct fission yields for
these isotopes have not bheen made, and calculations that have been made2
involve arbitrary corrvection factors which have not been verified experi-
mentally and have been the subject of criticism by wah1.25 Therefore,

in the present ORIGEN code, the direct fission yields Tor these isotopes

239

are taken to be equal to those for Pu. Although this approximation is
believed to be sufficiently accurate for computing properties of mixed
fission products, it may introduce substantial errors in estimates of
concentrations of individual isolopes, particularly for chains whose

yields fall on the edges of the low mass peak.

3.4 Photon Yield Library

Data files 4, 5, and 6 contain multigroup photon production data,
for the cladding and structural materials, heavy metal isolopes, and
fission product isotopes, respectively. Both files Lt and & contain 12
energy groups, in the PHOEBE group structure,26 The lower energy bound
and average energy in each of these groups are given in Table 3.7. For
the isotopes of the actinide elements, the lowest ecnergy group has been
divided into seven smaller groups with energies down to 20 keV, resulting

in an 18~encrgy-group structure. This modification was made in order to
31

Table 2.7. Lower Fnergy Bounds and Average Group Energies for
12 Photon Energy Groups in the ORIGEN Library

 

 

Lower Energy Mean Energy
Group (MeV) (MeV)
1 0.2 0.3
2 0.4 0.63
3 0.9 - 1.10
L 1.35 1.55
5 1.6 1.99
6 2.2 2.38
7 2.6 2.75
8 3.0 3.2
9 3.9 3.7
10 4.0 L. 22
11 .5 L 70

12 5.0 5.25

 
32

enable the user to compute the x-ray source strength in refabricated
fuels. The bounds and average energies for these low-energy groups are
given in Table 3.8, For the isotopes of the actinide elements, groups
8 through 18 have the same energy bounds and average energies as groups

2 through 12 for the fission products.

The photon abundances and energies accompanying a disintegration
event are based entirely on the tables of Lederer g&mgl.l Arnold has
used the SPECTRA code2 to calculale the contributicn tc the gamma-ray
source from breunmsstrahlung radiation produced by beta decay in a uranium
dioxide matrix. His results for several of the more important fission
products are given in Table 3.9. These values have been zdded to the
pnoton yields in the nuclear data library, which are recorded in the
form of an equivalent number of photons per disintegration having the

average energy of a given group.

Table 3.8. Lower Energy Bounds and Average Group Fnergies
for X~-Ray Groups in Actinide Photon Idibrary

 

 

Lower Energy Average Energy

Group (MeV) (MeV)

1 0,02 0.03

2 0.035 0.0k

3 0.050 0.06

b 0.075 0.1

5 0.125 .15

6 0.175 0.2

7 0.25 0.3

 
33

Table 3.9. Estimates of Bremsstrahlung FPhotons Resulting from Beta
Decay of Several Fission Products in a Uranium Dioxide Matrix

 

 

Photon Energy Photong per Beta
Isctope Group Digintegration
S or H3es 1 1,01 x 1072
2 h.2h x 1072
Pg 1 4,69 x 10"2
2 k.39 x 107
90y 1 k.ol x 1072
2 1.62 x 1072
3 2,48 x 10‘3
4 2.48 %= 1077
5 1.36 x 1077
_
1%2m 1 1.529 x 107F
2 6.4h52 % 10772
3 1.617 x 1072
It 3.886 x 1073
5 1.231 x 10‘3
6 3.687 = 1077
T 3401 x 1072
8 h.2h8 x 107"
kb, 1 7.528 x 1077
o 2.55 ¥ 1072
3 8.672 x 10723
L 1.236 x 107,
5 2.770 x 107!
6 3.962 x 1072
7 L.00 x 10™
£ -
o, 1 7.583 x 1077
2 9.722 x 1077
o 1 6.733 x 1074

 
3h

In computing the x-ray source strength in refabricated plutonium
fuels, one source of photon radiation that is to be considered is (Q,y)

18 21

radiation originating from the reaction O(a,n) "N 1in oxide fuels.

238

Since Pu is the plutonium iscltope of highest specific alpha activity
that is present In quantity in recycle plutcniuvm fuels, the photon pro-
duction from this scurce has been included in the pholon production data

238

for Pu. The spectrum of photon radiation resulting from alpha decay

of 238Pu in an oxide matrix was obtained from the compilation of Stoddard

af

and Albenesius.

3.5 Miscellaneous Nuclear Properties

The CORIGEN code treats several olfher sources of radiation that are
nct included in the nuclear data library but, instead, are programmed
into the code. Bpecifically, these are photon and neutron production
from spontaneous fission of the Transplutonium isotopss, and neutron
production by (Q&,n) reactions of alpha particles with o and l80 in
oxide Tuels. The spontanecus fission photon spectirum was Taken to be
the gsum of the prompt gamma-ray photon spectrum of 235U given by Peele
and MaienscheinES and the equilibrium fission product photon spectrum
used by Stoddard.29 These data were converted Lo the 18-energy-group
structure shown in Table 3.10, using flat weighting within energy groups.
This information, which is stored in the array SFCAMA (defined in sub-
routine GAMMA), is employed to compute the photon spectrum resulting

from radiocactive decay of the isotopes of the actinide elements.

Spontaneous Tission of lsotopes of the actinide elements is accom-
panied by the release of neutrons, which present an additional socurce of
penetrating radiation. The average number of neutrons released, v, in
the spontaneous fission of a number of isotopes has been summarized by
Arnold.3o The values of v for isotopes of mass 238 through 244 increase
approximately linearly with 1ncreasing atomic weight, A, and, within the

scatter of the data, are well represented by the eguation

v = 2.8k + 0.1225 (A - 244) . (1)
Table 3.10. Thoton Yields per 235y Fission Tor 18-Energy-Group
otructure Imployed in ORIGEN Library

Prompt plus equilibrium fission product x~ and y-rays

 

Average Fnergy

 

Group (MeV) Photons/Fission Mev/Fission
1 0.03 0.08h 0.00252
2 0.0k 0. 03k 0.00336
3 0.06 0.14 0.0084
L 0.1 0. h6 0.0U5
5 0.15 O, 64 0.096
& 0.2 0.99 0,108
7 0.3 2.01 0.603
8 0.63 9.15 5.76
9 1.10 1.87 2.06

10 1.55 1.27 1.97
11 1.99 0,67 1,3k
12 2,38 0. 3k 0.80
13 2.75 0.16 0.43
14 3.2 0.097 0. 31
15 3.7 0.062 0.23
16 L 22 0.039 0.16
17 L, 70 0.019 0.087
18 5.25 0, 017 0,061,

Suun / 18.09 14,17

 
36

This function is used in subroutine GAMMA to compute the specific neutron
generation rates in spent fuels. The ORIGEN code calculates only the
total neutron production ratesg; however, the energy dependence of the

spontaneous fission neutron spectrum for several isotopes has been found

5 20
to be similar to that of 2-°y, 27

n some applications, neutrons produced by (&,n) reactiocns of high-

energy alopnha particles with light elements constitute an important source

27 ,29,50

of penetrating radiation. Theoretical estimales have been made

of the quantity and spectra of neutrons produced by reactions of alpha

238 2kz
particles from 38Pu, Cm, and 2l

238

PuO, , have been found to exceed experimental values

Cm with oxygen atoms in oxide fuels
and, in the case of
by a factor of 2, TIn the ORIGEN code, the number of neutrons produced

per alpha disintegration in UO, fuel is calculated from the relationship:

2

 

neutrons B ~10 _3.65
alpha disintegration 1.0 x 10 o ? (2)
where Ea igs the alpha particle energy in MeV. This expression results

in source strengths that are approximately 50% of theoretical, in agree-
ment with the experimental results for 238?&. Equation (2) is employed
to compute neutron production by all alpha emitters, including those Tor

which data have not previously been available,

2.6 References for Section 3

1. C. M, Tederer, J. M, Hollander, and 5. Perlman, Table of Tsotopes,
6th ed., Wiley, New York, 1967.

 

2. E. D. Arnold, Handbook of Shielding Reguirements and Radiation
Characteristicg of Isotopic Power Sources for Terrestrial, Marine
and Space Applications, ORNL-3576, Appendix A (1964 ).

 

 

 

o

Code of Federal Regulations, Title 10, Part z0O.

+]
=

vV Radiation Concentration Guideg for the Actinides from

h,ooM,
2 ORNL~1M-I1 32 (in preparation).

. il e a«
DBEs Lo

R

 

erne ,
207y

5. Report of Committee TL on Permissible Dose for Internal Radiation,
Chapter TV, Pergamon Press, 1959,

 

6. J. R. Stehn, M. D. Coldberg, B. A. Magurna, and Renate Weiner-Chasman,
Neutron Cross Sections, 24 ed., Suppl. 2, BNL-325 (1964).

 
10.

11.

lz.

13.

1l

37

M, K. Drake, Nuclecnics 2L, 108-5h4 (1966).
H. Alter and C. B, Weber, J. Nucl. Mater. 16, 68-73 (1965).

S. Pearlstein, Analysis of (n,2n) Cross Sections for Nuclei of
Mass A > 30, BNL-897 (1964).

 

H. Kusters and M. Metzenroth, The Influence of Some [mportant Group
Constants on Integral Fast Reactor Quantities, ANL-7120 (1965),
. 431,

 

 

W. E. Unger, BR. E. Blanco, C. D. Watson, D. J, Crouse, and

A, R. Irvine (compilers), Aaueous Procesging of LMEBR Fuels,
Progress Report, March 1969, Mo, 1, ORNL-TM-2552 (April 1969),
pp - ,_%8 ”J+ ]._ -

 

 

R. L. Macklin and J. H. Gibbons, Rev. Mod. Fhys. 37, 166-74 (1965).

R. L. Macklin, J. H. Gibbons, and T. Inada, Phys. Rev. 129, 2695-97
(1963).

 

4
C. H. Wé@gott, Iffective Cross bection Values for Well-Moderated
Thermal Reactor Spectra, 3id ed. (Corrected), CCRP-GO0 (1960).

 

 

G. E. Hansen and W, H, Reach, 8ix and Sixteen Group Cross Sections
for Fast and Intermediate Critical Assemblies, LAMS-2543 (1961),

 

 

J. P, Nichols, Osk Ridge Natiocnal TLaboratory, personal commmnication
(Aagust 1972).

D. E. Deonigi, Battelle Pacific Northwest Laboratory, unpublished
mass flow data for light water reactors (May 1972).

MSR Program Semiannu. Progr. Rep. Feb, 28, 1970, ORNL-4548, p. 53.

 

K. Buttrey, 0. R, Hillig, P. M. Magee, and B. H., Cttewitte, liquid
Metal Fast Breeder Reactor (IMFBR) Task Force Fuel Cycle Study,
NAA~SR-MEMO-1200L (1968,

 

8. Katcoff, Mucleonics 18, 201-8 (1960).

M.FE. M% k angrB. . Rider, Sumpary of Fission Product Yields for
235y, 23077, 239py and Py at Thewmal, Fission Spectrum and 14 MeV
Neutron BEnergies, APED-5398-4 (Rev.) (1968).

 

 

K. Shure, Bebttis Technical Review, WAPD-RI-24 (December 1961), p. 1.

 

M. HE. Meek and B. F. Rider, Compllaticn of Fisslion Product Yields,
Vallecitos Nuclear Center, 19772, NEDO-12154 (January 19772).

 

 
38

24, E. A, C. Crouch, Calculated Independent Yields in Thermal Neutron
5. 239 . 2 ’
233y, 235, 239, ahl 23?Th} 238,

 

Fission of

and Zuopu, ABRE-R-6056 (1969).

e

, and in Fission of

 

 

25, A. C. Wahl, A, E, Norris, R. A. Rouse, and J. C. Williams, 'Products
from Thermal Neutron Tnduced Fission of 232U: A Correlation of
Radiochemical Charge and Mass Data," pp. 813-43 in Physics and
Chemistry of Fission (Proc. Symp. Vienna 1969), IABA, Vienna, 1969.

 

 

26. E. D. Arunold, PHOEBE - A Code for Calculating Beta and Cawmma Activity
and Spectra for 239U Fission Products, ORNL-3931 (July 1966).

27. D. H. Stoddard and E, [. Albenesius, Radiation Froperties of 238

Produced for Isotopic Power Generators, pp-a8l (1965).

Pu

 

 

28. R. W. Peelle and F. C. Maienschein, The Absolute Spectrum of Photons
Fmitted in Coincidence with Thermal -Neufron Fission of Uranium-235,
ORNL-4L57 {April 1970).

 

 

29. D. H. Stoddard, Radiation Properties of 2

Power Generators, DP-339 (1964).

Cn Produced for Tsotopic

 

 

30. E. D. Arnold, "Neutron Sources,’ pp. 30-35 in Engineering Compendium
on Radiation Shielding, Vol. I, ed. by R. G. Jaeger, Springer-Verlag,
New York, 1968,

 

 

It, USER'S MANUAL FCR THE ORIGEN CODE

The ORIGEN computer code is a collection of programs that: (1) proc-
esses a library of nuclear properties to construct a set of first-order,
linear, ordinary differential equations describing the rates of formation
and destruction of the nuclides contzined in the library; (2) solves the
resulting set of equations, for a given set of initial conditions and
irradiation history, to obtain the isotopic compositions of the discharged
fuel components as a function of postirradiation time; and (3) uses the
igsotopic compositions and nuclear properties of individual nuclides to
construct tableg describing the radicactivities, thermal power, potential
inhalation and ingestion hazards, and photon and rneutron production rates
in the discharged fuel. At present, The nuclides in the library are
divided into three classes: (1) cladding and structural materials;

(2) isotopes of actinide elements and their radioactive decay products;

and (3) fission products. In the output tables, the three classes of
39

materials are presented separately; as a result, certaln isctopes are
repeated. Thus, tritium and helium that are formed from spallabion
reactions of the light elements are distinguished from fission product
tritium or from hellum produced in alpha decay. Also, ischbopes of
several elements, notably zirconium, are consldered both with the
cladding and structural materials and as fission products. This dis-
tinction between the sources of the isotopes enables the user to treat
problems such as the effects of exposure on cladding embrittlement and

on changes in the isotoplc composition of structural materials.

The first output that the program produces consists of a swmmary of
the nuclear data library. A dictionary that explaing the abbreviations
used in the column headings in the library is included at the beginning
of the library. The code then prints a table containing the isotopic
composltion of the fuel as a function of exposure time. The compositions
will be given in units of g-atoms per unit of fuel charged to the reactor.
The unit of fuel considered 1s an input variable and may be any consistent
quantity (e.g., a metric ton of uranium, an entire fuel agsembly, or

235,
100 atoms of '35u).

The code next prints tables showing the properties of the discharged
fuel. The following properties are computed for the unit of fuel that
was specified to be charged to the reactor:

(1) g-atoms,

(2) grams,

(3) curies,

(L) total B+y watts,

(5) ¥ watts,

(6) cubic meters of air required to dilute the radicactivity to

RCG,, and
(7) cubic meters of water required to dilute the radioactivity to
RCGW.
A1l seven types of information are first computed for the cladding and
structural materials, then for the heavy metal isctopes, and finally for
the flssion products. Four tables are printed for each property; the

first gives the properties of every individual isotope considered in the
4o

library, the second gives the prcoperties as a function of each chemical
element, the third summarizes the properties for only the most important
individual isotopes and is designed to Tit on an 8-1/2 x 11 in. page,

and the fourth summarizes the properties of the chemical elements. Thus,
84 tables can be printed - four tables for seven properties of three
clagsses of isotopes. By proper selection of input variables, it is

possible to eliminate certalin of these tables as described in Sect. L.2.

Following the tables of the properties of the isotopes and elements,
tables of the penetrating radiations emanating from the spent fuel are
printed out. The first table gives, as a function of postirradiation
time, a lZ-energy-group spectrum of gamma radiation emitted from the
fuel as the result of the activity induced in the cladding and structural
materi als. The data are presented as the number of photons of a given
average energy which are produced per second per unit of fuel as charged
to the reactor. A second table is also printed that gives, as a function
of postirradiation time, the number of megavolts per sccond per watt of
average power produced in a unlit of fuel which are released as photons
into the 12 energy groups. Subsequently, two tables that provide the
same information for the fission products are printed out. Following
the tables of vhoton release rates for the fission products is a table
summarizing the most important contributors to the photon producticn

rate in each of the 12 energy groups.

The final tables contain information generated concerning the pene-
trating radiations produced in the isotopes of the aclinide elements and
their radicactive decay daughters. First, a table 1s printed that gives,
for each alpha radicactive isotope as a Tuncilon of postirradiation time,
estimates of the number of neutrons released per second from a unit of
fuel as the result of (&,n) reactions. This is followed by a table which
gives estimates of the number of neutrons released per second from a unit
of fuel by isotopes that undergo spontaneous fission. TIn each of these
tables, only the total number of neutrons of all energles released at a
given time is calculated., However, the energy speclrum cof neutrons

emitted in spontaneocus figssdion of several nuclides has been found to be
b1

. 235 .
similar to that for ij,l and estimates of the spectrum of neutron

energies arising from (&,n) reactions have heen mede for several of the

. 1,2
more important (o,n) sources.’

The final table that is printed containg estimates, using an 1L8~energy-
group structure, of the spectrum.of photons produced by decay of isobopes
of the actinide elements and their radicactive daughters, as a function
of postirradiation time. The data in this table also include the contri-
butions from the prompt gamma rays accompanying spontansous fission and
from the gamma rays released by the equilibrium fisgion products that are
formed in spontaneous fission. Every table in the output is concluded by
a row of totals representing the sum of the properties for the isotopes
in that table. To obtain the total contribution from all isotopes (clad-
ding, fuel, and fission products), it is necessary to add the contributions

from the separate tables.

.1 Description of ORIGEN Code Programs

The names of the various subroutines, their major functions, and the
important variable names In each routine are described below in the order

in which they are employed in the code.

MAIN. ~ This is the program that supervises the execution of tasks by
the other routines. With the exception of the nuclear data, all input is
read by the MAIN program from the card reader (Unit 50). The code solves
the set of first-order, linear, ordinary differential equations

X =A X+ B, given X(0) , (1)

oo
where X(0) is a set of initial concentrations, X(t) is the time-dependent
solution that is desired, A is a matrix of first-order rate coefficients,
and B is a forcing vector. The solution X(t) is obtained at intervals

tysboee by

The constructlon of the matrix A is performed by other subroutines that

and it 1s required that A and B be constant between intervals.

are described below. The vectors A and B are assigned valueg in the pro-
gram MATN either by reading data from cards or by manipulation of data

generated in a previcus calculation that is stored in an array. In the
W2

code, the variables A and B have the names A and B, the variable %(O) has
the name XZER¢, and the solution has the name XNEW. These variables are
stored in labeled common blocks /MATRIX/ and /EQ/.

NUDATA. - Subroutine NUDATA processes the nuclear data from the
library tape and constructs part of the transition matrix:é. 1t reads
two cards from the card reader. The first one contains a title for the
library that will be printed with the output, as well as an integer,
NLIBE (in column 75), that designates the reactor spectrum over which
the cross sections are to be averaged. The second cne contains welghting
factors for the reactor spectrum, a Tleld for the date, and switches to
suppress part of the output. The subroutine reads the data from the
library tape and prints out the library of data to be used in the calcu-
lations. The nonzero, off-diagonal terms of the matrixfié are stored in
the variable A. Three integer vectors, L¢C, N@NO, and KD, are also
constructed to be used to locate the matrix elements. These variables
are stored in labeled common block /MATRIX/. Table k.1 lists other data
(from the nuclear library) that are stored by subroutine NUDATA and will

be required in subseguent calculations.

HALF. - This subroutine computes the radiocactive decay constant in

 

uwnits of sec"l, when the half-life of the radionuclide is given in units

designated by the variable IU (see Sect. 3.1).

E@&fi ~ This subroutine constructs a Chree-word alphameric symbol for
an isotope from its six-diglt ldentifying number. The three words consist
of the symbol for the chemical element, the atomic weight, and either a
blank or an "M" to designate a ground or metastable state, respectively.

These symbols are used only when printing output tables.

BLQCK DATA. - A BL@CK DATA subroutine is used to initialize the
variables in labeled cowmon block /LABEL/. These varisbles consist of
an array of chemical symbols, ELE, and a variable to designate the isomeric
state of a nuclide, STA. These arrays arc used in conjunction with sub-

roubine N@AI.

~
43

Table Y4.1. Definitions and Storage TLocations of Important
Variables Assigned Values in Subroutine NUDATA

 

Variable Common Block Definition

 

ABUND

/gur/

Isotopic abundances of the cladding
and. structural materials, at. %

ATPHAN /guT/ Number of neutrons produced per
alpha disintegration by heavy metal
1sotopes

AMPC /MPC/ Radicactivity concentration guide for
continuous inhalsation in unrestricted
areas, uCi/em

DIS /FLUKN/ Radioactive decay constant, secql

¥G /¢UT/ Fraction of radioactive decay energy
that resulis from photons of energles
above 200 keV

FI35 /FLUXN/ opectrum-averaged fission cross
section, barns

NUCL /¢UT/ Six~diglt integer constant used to
identify isotopes

Q Jgur / Radioactive decay energy released as
recoverable heat, MeV/disintegration

SP@NF /gut/ Spontaneous fission rate for heavy
metal isotopes, fissions/sec-atom

T¢CAP /FLUXN/ Total spectrum-averaged neutron
absorption cross section, barns

WMPC pirc / Radioactivity concentration guide for

continuous ingestion in unresgstricted
areas, uCi/cm

 
L

PHPLIB. - PHPLIB reads the multigroup photon production data from
the nuclear library tape and stores the informaticn in the arrays GAMGRP
and ACTGRP. The array GAMGR? contains 1Z2-energy~group photon production
data for the isctopes of the cladding and structural materials and of the
fission products, while the array ACTGRP contains 18-energy-group data
for isotopes of the actinide elements and their radiocactive decay daughters.

This subroutine also prints a table containing the data in the library.

FLUX®. -~ This subroutine uses a Taylor series expansion about the
start of a computational imterval to estimate: (1) the average flux
during the interval, when the reactor power is given; or (2) the average
power generated by the fuel during the interval, when the neutron flux is
given. Once the flux has been obtained, it is multiplied by the cross
sections to generate first-order rate constants for production and destruc-
tion of nuclides by neutron-induced reactions. The subroutine also con-
structs the diagonzl matrix element for each isotope from the negative of
the sum of the disintegration constant, the product of the spectrum-
averaged total absorption cross section times the flux, and the rate
coefficient for other removal processes that are proportiocnal to the
jinstantaneous concentration (e.g., leakage or first-order chemical
reaction). The diagonal matrix elements are stored in the array D in

labeled common block /EQ/.

DECAY. - This subroutine solves the Bateman equations for nuclides
that occur at the beginning of decay chains and have half-lives that are
short with respect to the time interval for the calculation (time interval
greater than 10 half-lives). The concentrations of the short-lived
nuclides at the end of the interval arec contained in the array XNEW,
and the concentrations of any long-lived or stable daughters at the start
of the interval are augmented by the amount that the short-lived precursor
has decayed, The variable XTEMP is used {to contain the adjusted initial
concentrations of the long-Jlived and stable materials. The variables are

stored in labeled common block /3Q/.
TERM. - The subroutine TERM has two principal functions, Tt con-
structs a reduced coefficient matrix that involves transitions between
only long-lived or stable nuclides. By way of explanation, if a chain
A= B - C exists, and if isotope B is short-lived while iscbopes A and C
are long-lived, a matrix element is created for the event A - C directly
and is entered inte the array AP. The array AP is a local variable that
is uged in subroutine TERM. The second function of subroutine TERM is to
solve the reduced system of equations that results when the short-lived
nuclides are excluded. The equations are solved by the matrix exponential
method, using an algorithm which involves use of a recursion relation to
generate the matrix exponential function, ag described in Sect. 2,1. The
sclution that is obtained for the concentrations of the long-lived and

stable nuclides at the end of the time interval is contained in the array

XNEW.

FEQUIL. - Subroutine BEQUIL is used to place short~lived daughters in
secular equilibrium with long-lived parents. The subroutine uses the
Gauss~Beidel succegsive substitution algorithm to solve a set of linear
algebraic eguations. The resulting concentrations are contained in the

array XNEW.

@UTPUT. ~ As 1ts name indicates, this subroutine produces tables of
output containing the properties of irradiated maberials, fiUTPUT has
available fto it the array XNUW, which containsg the concentrations of the
fuel as a function of time, and other arrays containing the radiocactive
decay constant, the heat per disintegration, etc, From these, it computes
inventories, radiocactivities, thermal powers, and other properties of
interest., It prints tables of properties of individual isotopes and of
chemical elements, and prepares summary tables of the most important

contributors.,

GAMMA. - This subroutine prepares tables of penetrating radiation
sources in spent fuels., Using the isoteopic compositions in the XNEW array,
the photon release dats in labeled common block /PHéTfiN/ > and the neutron
production data in labeled common block /PUT/, GAMMA compiles tables of
miltigroup vhoton release rates and neutreon production rates as a function

of time.
L6

4.2 Description of Card Input to the ORIGEN Program

The first two input cards are read by the subroutine NUDATA, ‘These
cards furnish a title for the library of nuclear data, identify the nuclear
data library that is to be read from the tape, provide spectral indices

for the reactor, and select certalin options.

A. READ (50, 9011, END = 920) (TITLE(T), T =1, 18), NLIBE
Q011 FERMAT (18ak, I3)

TITLE is a TZ2-character alphameric title which will be printed as

the heading on the printout of the nuclear library.

NLIBE is an integer that identifies the library to be read from
the tape.

for HTGR

for LWR

for TMFBR

for MSBR

N

= ow

B. READ (50, 9001) THERM, RES, FAST, ERR, NMy, NDAY, NYR, MPCTAB, INPT, IR
0001 FERMAT (LF10.5, 612)

% . \ . . 1 .

THERM® = ratio of the neutron reaction rate for a Z absorber with
a population of neutrons having a Maxwell-Boltzmann
distribution of energies at absclute temperature, T, to

the reaction rate with ZZOO—m/sec neutrons

T[TO

=] T L= 293.16°K

RES = ratio of the resonance flux per unit lethargy to the

thermal neutron flux.

 

¥

THERM, RES, and FAST have meaning only for thermal reactors. For the
IMFBR, the cross sections on the tape are already spectrum averaged,
and THERM, RES, and FAST are equal to 1.0.
L7

FAST = ratio of flux above 1 MeV to the fraction of the fission

spectrum above 1 MeV, divided by the thermal neutron flux.
ERR = a truncation error limit which will be considered to be
zero by the code (10-2) recommended ).

WMB, NDAY, = month, day, and year when case is run, to help in

NYR identifying output,

MPCTAB = an output coption, If MPCTAB = O, the output tables will
include the quantities of alr and water that could be
contaminated Lo the radicactivity concentration guide
(RCG) values for inhalation and ingestion by each of the

radionuclides. Otherwise, the tables are omitted.

TNPT = an input option, If TINPT = O, the entire nuclear data
library will be read from tape on data set reference No. 7.
It TNPT % O, the photon library iz read from cards on data
set reference No. 50, Note that the three groups of iso-
topes in the photon library must be separated by blank cards.

(See the FORTRAN listing of subroutine PHOLIB for detalls.)

IR = an output option. If IR # 0, the code will write out all
the elements of the transitlon matrix that it constructs
from the nuclear data library. This is a debugging tool,

and IR is usually egual to zero.

\ S
C. 70 READ (50, 9008, END = 590), MMN, MZUT, NJBLND, INDEX, NTABLE,
MSTAR, NG, MPRHS, MFIED

9008 FPRMAT (1615)
MMN = number of time intervals during irradiation period <10.

MAUT = total number of time intervals for irradiation and post-

irradiation periods =10,

i

NZBLND = number of materials to be blended =10. HEnter O or 1 if

ne blending is to be done.
L3

TNDEX = an input indicator. Tf INDEX = O, PPWER(M) will be read on
s subsequent card. If INDEX = 1, FLUX{M) will be read. IT
MMN = O, INDEX is not used by the code in this step.

NTABLE = an output indicator. If NTABLE = O, all isctopes and all times
will be given in the output. If NTARLE = 1, only summaries of

most important isotopes will be given.

MSTAR = another output indicator. When summarizing the most important
isotopes, the code eliminates the isotopes whose values are

below some threshold (see card type I) in time periocd M = M3TAR.

NG = an indicator which tells the code whether the calculation will
be continued in a subsequent set of times, or whether a new
calculation will be done. NG¢ < O indicates a new calculation
with new initial conditions using the same nuclear data. A
card of type C will be expected following card K or N. NCG@ = O
indicates a new calculation with a new set of nuclear data.

A card of type A will be expected following card K or IN.
NGP > O indicates the present calculation will be continued.

A card of type ¢, following card K or N, will be expected,

MPRZS = an indicator for continuous chemical processing option.
MPRZS = number of groups of chemical elements processed.

MPRPS

11

0 for no chemical processing.

MFEED = ccontinuous feed option for fluid fuel reactor. MFEFED = O for

no contlnuous feed; >0 for continuous feed.

D. READ (50, 900L) TITLE
900L FPRMAT {20AL)

TITLE = a title for the calculation containing up tc 80 alphameric

characters.
49

Cards of type E or F are included only if MMW is greater than zero,

F(
1 a

G.

H.

TP (INDEX.EQ.0) READ (50, 9005) (PPWER(M), M = 1, MMN)

9005 FERMAT {(10E8.2)

POWER(M) = specific thermal power of fuel in irradiation period M

(MW/unit of fuel). ‘here may be periods of zero power;
however, there may not be two consecutive zero-power
intervals, and the final Irradiation period may not have

ZeT0 power.

17 (INDEX.EQ.1) READ (50, 9005) (FLUX(M), M = 1, MMY)

FLUX(M) = thermal-neutron flux in irradiation period M

(neutrcns/cm?-sec), or the total neutron flux for s
fasgt reactor. There may be periods when the flux is
zero during the irradiation periocd; however, there may
not be two cconsecutive periods of zero flux, and the

final irradiation periocd may not have zero flux.

READ (50, 9005) (T(M), M = 1, MpUT)

T(M) = elapsed time since the beginning of the calculation

(measured in terms of TUNIT).

READ (50, 9013) BASIS, TCONST, TUNIT

Q013 FPRMAT (10AL, F7.0, A3, ¥10.3)

BASIS

TCONST

TUNTT

B

i

!

a U4O-character alphameric title that is the wnit of fuel
on which the calculation is based and that will be printed
out as the basis for the calculation (e.g., "Metric Ton

of Fuel Charged to Reactor”).

a factor to convert the input values of T(M) dnto seconds
(e.g., TCONST = 3.155E7 if values of T(M) are input in
terms of years).

an alphameric designation for the input units of T(M)

(e.g., "D for days).
o0

I. READ (50, 900&) CUTPFE

9006 FPRMAT (8F1C. 3)

CUTPFF(MS )

a threshold value for output summary tables. Any isotope
whose value in the time period MSTAR is less than
CUTPFEF(MS) will be omitted from the summary table of
property MS.

MS =

g-atom table

- gram table

- curie table

Bty power table

-~ ¥ power table

Ch 1 w o
1

- relative inhalation hazard
' - relative ingestion hazard
A value of 0.00l is recommended for Tables 1 to 5, and

a value of 1.0 is reccommended Tor Tables 46 and 7.

J. TF (N@BLND.GT.1) READ (50, 9006) (FACT(N), N = 1, NPBLND)

9006 FFRMAT (8E10.3)

FACT(N)

atom [raction of each material in a calculation for

a blended Tfuel.

K. 110 READ (50, 9007, END = 200) (INUCL(I), XC@MP(I), T = 1, 5), NEXT

9007 FERMAT (5(716, E9.2), I5)

INUCL

XC@MP

NEXT

nuclide identifier for an iscotope in fresh fuel.

= ATOMIC NO. * 10000 + ATOMIC WT ¥ 10 + 1S5, where IS =0

i

for ground state, = 1 for excited state.

concentration of nuclide INUCI, in fresh fuel (expressed

as g-atoms per unit of BASIS).

an indicator giving the type of the five isotopes on
the card. Thus all five must be of one type.

1 for isotopes of c¢ladding and structural materials
7 Tor heavy metal isotopes

3 for fission product isotopes

4 for elements of cladding and structural materials
L.

51

All cards of this type should be followed by a single
blank card, When the program encounters the blank card,
it continues to the next part of the input. If it
encounters & blank INUCL field, it skips the rest of
the information on that card and returns to statement

110.

The following cards (L and M) are read only if MPRES

V
O

READ (50, 9011) (PRATE(M), NSPRES(M), M = 1, MPRES)
9011 P@RMAT (8 (EB.2, I2))

PRATE(M) is a first-order removal constant for chemical processing

. -1
by processing stream M, sec

N¢PR¢S(M) is the number of elements removed by stream M,

READ (50, 9012) ((NZPRPS(M,N), N = 1, N@PR4S (M)), M = 1, MPRAS)
9012 FPRMAT (201h)

NZPRfiS(M,N) = atomic number of element N in processing stream M.

The following card (N) is read only if MFEED > O.
READ (50, 9007, END = 330) (INUCL(1), ¥CpMp(1), I =1, 5), NEXT

XC@MP is the continuous feed rate of isotope INUCL (in g-atoms
per second per unit of fuel). The unit of fuel is

given by the wvariable BASIS.

INUCL and NEXT folleow the same conventiocns as described for

cards of type K,

END OF INITIAL INPUT
5a

The program will now calculate the isctopic compositions for all
MOUT time periods and write output. After writing output, the program
will either be ready to start a new problem (if NG¢ < 0) or continue the
present one (NG¢ > O). 1In the latter case, the input for the continuation

of the calculation has the form:

Q0. READ (50, 9008) MMM, MPUT, N@BLND, INDEX, MSUB, MSTAR, NGO,
MPRPS, MFEED

MSUB = the time period in the last calculation considered as the
start of the new calculation; also used to indicate that

batch chemical processing occurs if the value is negative,

MFEED = an input indicator for continuous feed.

O, no Teed

i

= >0, continuocus feed at the same rate as for the previous

calculation,

A1l other variables have their former meanings.

This card is followed by cards of type D, E, F, G, and H or H'
(see below) to complete the input for the continued calculation.
This procedure may be repeated as desired, The calculation will

stop when a blank card is read in place of a card of type C.

When continuing a calculation that was started in a previous set
of time periods, a card of type H may be modified to include cne

additional piece of information.

H7. READ {50, 9012) BASIS, C@NST, TUNIT, TMp

The firat three variables have their previcus meaning, while
the variasble TMp is the time to which the times read on card type
3 are referenced. Thus it is possible to calculate the pestirra-
diation properties of a fuel, say, for ten years after discharge
in ten time periods, and then to calculate the properties for ten

subsequent time periods by setting MSUB equal to 10 and TM¢ equal
53

to ten years. The array TIME will have the values 11 through 20,
and the ccde will calculate the properties for the elapsed time
since the tenth year. Postirradiation properties are calculated

with respect to the time of discharge if TMP is not given a value.

A negative value for the varizble M3UJB indicates that batch
chemical processing is asgsumed to occur at time T(-MSUB), and that
dats giving processing information are reguired to be read. When
MSUE has a negative wvalue, cards of the type P are expected to

follow card H'.

P. 500 READ (50, 9003) LEMENT, FREPRP(LEMENT)
9003 FPRMAT (16, LX, F10.3)

The variable LEMENT is the atomic number of a certain chemical
element to be removed, and FREPRfi(LEMENT? is the fraction of the
material that remains after processing. The array FREPRZ is ini-
tially set equsl to 1.03 thus, if no data are read for an element,
processing does not affect its concentration. Cards of type P are

expected to be read until a blank card iz encountered.

M™is is all of the card input that is required to perform a variety
of calculations with the ORIGEN ccde. An example of the card input for
a sample case that illustrates many of the features of the code 1s given

below.

4,3 TInput for Sample Problem

The use of the ORIGEN program is illustrated with the example of a

235

pressurized water reactor, in which fuel with an initial U enrichment
of 3.3 wt % was assumed to be exposed for a period of 1100 days at a
constant averasge specific power of 30 MW per metric ton of uranium
charged to the core at the start of an equilibrium cycle. The isotopic
compositions of the Zircaloy cladding and nconel spacer grids were
computed, along with the composition of the heavy metal isotopes and

the fission products. The postirradiation properties of the spent fuel
5L

were calculated for decay times up to 10 years. These results were
followed by a caleculation of the properties of the waste that was gen-
erated when the fuel was reprocessed at a postirradiation time of 150
days and 100% of the Xe and Kr and 99,5% of the uranium and plutonium
were removed. The input required Lo perform these calculations is given
in Table 4.2, The letters typed in the leftmost column of Table L, 2
correspond to those given in the description of input in the previous

section and do not actually appear on the cards,

Card A containg a title for the library, and the numeral "2" in
column 75 indicates that the LWR library is fo be used for the calcula-
tion. Card B does the following things: (1) gives the values 0.632,
0.333, and 2.0 Tor THERM, RES, and FAST, respectively; (2) indicates
that concentrations less than 10777 g-atom per unit of fuel will be
neglected; (3) supplies the date; and (L) indicates that hazard tables
will be calculated, that the photon library will be read from tape, and
that the matrix that is constructed will not be written out. Card C
indicates that: (1) ten irradiation periods will be calculated, (2) there
will be no blending of fuels, (3) the specific power will be read on card
E, (L) full output tables will be written, (5) the sequence of calculations
will be coatinued (NGC = 1), and (6) there will be no feed or processing
of fuel. Card D is a title card for this part of the calculation., Card E
indicates that the specific power is constant at 30 MW per unit of fuel
throughout the ten irradiation steps. Card G gives ten irradiation times
in equal increments of 110 days. Card I designates the unit of fuel as
a metric ton of heavy metal charged to the reactor and indicates that the
unit of time for this part of the calculation is days. Card | gives lower
limits for the summary tables that will be printed during the postirradia-
tion calculations, Cards of type K give the isotopic concentrations of

the cladding and fuel at the start of the irradiation period.

These are all the cards required Lo perform the first step in the
calculations. The code will compute the isotopic concentrations at the
ten times given on card G and will print tables containing this informa-
tion. When this task is completed, the code will read card fi, which

indicates that: (1) the properties are desired at ten postirradiation
= o =39 aow e

N o S o 0 d W A R W XN R AR R R A AR R H

=

W dv < T

55

NUCLEAR DATA LIBRARY FOR REFERENCE PWR 2
0.632 0.333 2.000 1.0E=25 32073 0 0 O
10 1o o 0 0 0 1 o 0 o
REFERENCE PWR EQUILIBRIUM FUEL CYCLE = 3.3 0/0 ENRICHED U
30,0 30,0 30,0 30,0 30,0 30.0 30.0 30,0 30.0  30.0
110, 220, 330. 440, 550, 660, 770. 880, 990, 1100,
MT OF HEAVY METAL CHARGED TO REACTOR  B6400, D
1.6~3 1.E~3 1.6-3 1.£-3 1.E~3 1.E 6 1.E 4
60120 1.5 130270 4.0 140280 607 140290 034 220460 ,304 1
220470 ,277 220480 2,771 220490 ,204 220500 .200 240500 5,040 1
240520 57.423 240530 6,415 240540 1,574 250550 327 260540 4,037 1
260560 61,018 260570 1.439 260580 .310 270590 ,915 280580 111,862 1
280600 41,783 280610 1.869 280620 5.645 280640 1,609 400900 1421.122 1
400910 306.725 400920 462.239 LOO9LO 460,074 400960 72.50 410930 10.253 1
420920 957 420940 532 420950 ,926 420960 ,953 420970 546 1
4209580 1,357 421000 540 501120 .321 501140 ,219 501150 113 1
501160 4.681 501170 2.470 50118 7.729 501190 2.739 501200 10,392 1
501220 1.467 50124 1.823 1
922350 1 ,L4OLE 2922380 4.062F 3922340 1,13 2
{Blank Card)
o 10 o0 o 10 6 1 o 0 0
REFERENCE PWR EQUILIBRIUM FUEL CYCLE =~ FUEL DECAY TIMES
10.0 30,0 60,0 90,0 120.0 160,0 270.0 365.0 1096.0 3652.5
MT OF HEAVY METAL CHARGED TO REACTOR  86400. D
0 10 0 0 =6 4 - O ¢ 0
REFERENCE PWR EQUILIBRIUM FUEL CYCLE = WASTE DECAY TIMES
1.0 3.0 10.0 30,0 100.0 300.0 1000.0 3000.0 1.0E & 1.0E 5
MT OF HEAVY METAL CHARGED TO REACTOR 3.156£7 ¥
36
54
92 0.005
94 0,005
(Biank Card)
times, (2) the initial compositions for the decay calculation are the
discharge compositions from the vrevious calculation (MSUB = 10), (3) the
nuclides whose properties are below the cutoff values in the sixth decay
period will be omitted from the summary tables (MSTAR = 6), and (&) a
third sequence of calculations is reguired when The present set is com-

pleted (NGO = 1). Card D is a title for the postirradiation tables.

Card G contains the ten postirradiation times al which the properties

are desired. Card H gives the unit of fuel, which must be the same as
designated previously, and the unit of time, which is permitied to change.
At this polnt, the postirradiation properties are computed and another

set of output tables is printed.

Another card of type ¢ is read, indicating fthat ten decay periods
will be treated and that the initizal composition for the calculation will
be fuel aged 150 days (after discharge) to which some batch chemical
vrocessing has been done (MSUB = 6). ‘The value MSTAR = 4 indicates that
the summary tables will exclude isotopes whose properties are below the
CUTOFF's at time period 4, and that, at the end of the present calculation,
a new calculation will be initiated using a different sel of initial
composiltions and exposure history. Card D is a title for the step in
the sequence of calculations, and card G gives postprocessing times at
which the properties of the remaining isotopes are desired. Card H gives
the unit of fuel and the unit of time. Cards of type P indicate that =ll
of the xenon and krypton and 99.5% of the uranium and piutonium have been
removed from the fuel at the time of processing. Part of the output that

results from this set of input data is given in the Appendix.

4,4 Additional Programming Considerations

The ORIGEN code was designed for use on the IBM 360 Operating System.
It is written in IBM FORTRAN H and is usually compiled using full optimi-
zation on the H-level compiler. Ior convenience, 1t employs several I1IBM

feastures that are not standsrd.

The normal word length on the IBM 360 Operating System is four hexa-
decimal bytes. TIn order to decrease storage requirements, a number of

integer variables are defined as INTEGER*Z and several logical variables
o7

are defined as LfiGICAL*l. In addition, to preserve accuracy in the
calculations, several variables in subroutines DECAY and TERM are
defined as REAL*¥8. In other computing systems with longer word lengths,
the lengths of these variables may be changed without affecting the
operation of the code or significantly affecting the accuracy of the
results, However, an incresse in the amount of storage that ig required

willl result.

The numerical technigues that are employed in the code are designed
so that the maximum relative error in the concentration of any single
nuclide that results in one time interval will be less than 0.1%. Tt is
possible that the relative error in the concentration of a given nuclide
could reach a Tew peréent at the end of a long sequence of calculations
involving dozens of time intervals. However, in most applications, errors
of this magnitude are acceptable and are within the limitations of the
uncertainties in nuclear dats and in the neutron spectrum. In most cases,
the accuracy of the aggregate properties of a spent fuel, such ag the
totsal thermal vower or activity level, is limited only by the accuracy
of the nuclear data itself. As more complete experimental information
on the fission yields and decay schemes of the short-lived fission products
becomes avallable, the code should be sble to represent quite accurately

the postirradiation properties of a variety of Tuel types.

The magnetic tape supplied to users usually contains two complete
copies of the FORTRAN listing of the ORIGEN code and of the nuclear data
libraries. The data are contained in 14 files; files 8-1U4 are duplicates
of files 1-7. The tape is written in card~image form, in EBCDIC, DCB =
(RECFM = FB,LRECL = 80, BLKSIZE = 3200). Files 1 and 8 contaln the
FORTRAN listing of the code, and files 2-7 and 9-14 contain nuclear data

in the proper format for use by the code.

The code is programmed to read card input on data set reference No.
50, and tape input on No. 7. Output written on the printer refers to
dats set reference No. 51; punched output refers to No. 52Z2. Instructions
built into the code call for it to punch a number of cards on data set
reference No., 52, and a data set definition card for this data zet must

be included in the job control language. 1t should normally be dummied oub.
58

The code requires about 32C k bytes on the IBM/360 system without
OVERLAY. By use of the overlay attribute of the IBM linkage editor, it
is possible to reduce the REGION used to less than 270 k., The overlay
structure is quite simple, using only one segment into wnhich the sub-
routines NUDATA and HALF are placed first; next, PHOLIB, TERM, DECAY,
and BEQULL: and finally, OUTPUT and GAMMA. TNormal running time on the

360/91 is about 1 min for the sample problem contained in the Appendix.

For a number of applications, the program does not have to be
executed with the entire library of light elements, aclinides, and
fission products. If, for example, the isctopic composition of the
fuel material after a given irradiation history is desired, the light
elements and fisslon products need not be included in the calculatlon.
Wnen the IBM/36O operating system is used, these may be omitted by
referencing DUMMY data sets for the first and third files read by
subroutine NUDATA. In this example, the fourth data set to be read

wceculd then be the actinide photon library.

4.5 References for Section 4

2Ll

1. D, H. Stoddard, Radiation Properties of Cm Produced for Isotopic
Power Cenerators, DP-939 (196h).

 

 

2. D. H, Steddard snd E. L. Albenesius, Radiation Properties of 238Pu

Produced for Tsotopic Power Generators, Dr-98l (15657,

 

 

5.  GLOSSARY OF WARNTUG AND FRROR MESSAGES

Several potential problems have been anticipated, and the program
contains built-in tests for common errors. Some of the messages issued
by the code under conditions where an error may have occurred are dis-
cussed below. The anticipated error 1s described and, where possible,

remedies for the problem are suggested.

The program MATIN contains the two warning messages: "MMN or MPUT
EXCEFDS DIMENSICNS," and "MMN SHOUTD NOT HXCHED MPUT." The variables
MMN and MAUT have a maximum value of 10, and MAUT must be greater than

or equal to MMN,
The subroutine NUDATA will issue one of several error messages
hat are self-explanatory. For example, assume that the number of
isotopes of light elements, actinide elements, fission products, or
total number of isotopes exceeds a dimension. 1In the case of the light
elements, the dimension of the variable ABUND has been exceeded. For
the actinides, the dimensions of the variables FISS, SP¢NF, and ATPHAN
, have bheen exceeded. In the case of the fission products, only the
dimension of the wvariable YIELD has been exceeded, If the total number
of muclides exceeds 800, the dimensions of a large number of arrays
throughout the program would be exceeded and extensive medifications
to the program would be required. One possibility in this case would
be to run the problem in two parts, obtaining the concentrations of the
actinides and fission products in the first calculation, and computing
the properties of the light elements in a second calculation by making
use of the fluxes obtained from the first calculation. It should be
noted that, to obtain concentrations of fission products being produced
from fissions, it is necessary to include both actinides and fission

products in the calculation.

Two additional messages are produced by subroutine NUDATA, These
are: WARNING, M OUT OF RANGE IN NUDATA," and "NN HAS EXCEEDED 2500,
EQUAL TC." Either of these messages indicates that, in making modifi-
cations to the livrary, the user has increasged the number of reactions
to cause a dimension to be exceeded. In the first message, the subscript
M counts the number of transmutation products that can be produced through
all the competing channels for removal of a nuclide. These were not ex-
pected to exceed T, and did not do so in the original library. If this
condition occurs, the dimensions of the variables C@EFF and NPRED will
be exceeded, If these dimensions are to be increased, the EQUIVALENCE
statement gt the start of NUDATA must be altered. The alternative would

be to neglect some minor pathway.

The second message indicates that the dimensions of the variables A
and LOC in COMVPN /MATRIX/ have been exceeded. These may be increased,

or the problem may be partitioned as described above,
60

Warning messages are also issued by subroutine PHfiLIB if an error is
encountered in the order of the photon release data. These messages are
most likely to be encountered when an addition or deletion is made to the
isotope library (files 1 through 3) without a corresponding change in the

photon library (files M through 6).

Subroutine FLUX@ will issue = warning message if the estimated
depletion of the fuel material during a time ianterval in an irradiation
calculation exceeds 20%. Corrective action is suggested in the message.
This message 1s frecuently generated as the result of an input error in

the fuel compositions or in the time intervals.

Subroutines DECAY and TERM both employ the Bateman equations to
solve the chain equations for short-lived nuclides. The algorithm that
is adopted anticipales both cyelic chains and the cccurrence of two chain
members with nearly equal half-lives, Tf more than two chain members
have nearly egqgual half-lives, il is posgsible that the algorithm might
result in an erroncous negative concentration. A test is buillt into the
program to identify this condition and to provide information helpful
for correcting the problem, Subroutine TERM writes the message: "'BATE
I5 NEGATIVE IN TERM. THERE ARE MORE THAN TWO SHORT-LIVED NUCLIDES IN A
CHATN WITH NEARLY EQUAL DIAGONAT, ELEMENTS. L, IM, BATE, BATM =", where
L is the sequence number of the nuclide in error, IM is the number of
precursors in the chain in which the error occurred, BATE is the erron-
eous negative contribution that was calculated in the summation for
nuclide I, and BATM is the current value of the sum. The negative value

is not added to the summation, however,

If the problem occurs in subroutine DECAY, the message 'L, 1, BATHE,
XTEM, XTEMP(J1), AKDJQ =" is written along with the values of these
variables., TIn this instance, L i1s the sequence number of the nuclide
whese concentration is in error, I is the number of nuclides in the
chain in which the error occurred, the product XTEMP(J1 )*¥AKDJQ*¥BATE is
the erroneous negative contribution that was calculated in the summation
for nuclide L, and XTEM is the current value of the sum giving the con-
centration of nuclide L, Again, the negative contribution to the chain

is not added to the summation since 1t 1s known to be in error.
If this condition occurs, it is thus possible to identify the nuclide
in error and the chain in which the errvor occurred. A comparison of the
magnitude of the term in error to the calculated concentration indicates
the relative magnitude of the error involved in neglecting the contribu-
tion from a particular chain. 1f the error appears appreciable, it may
be possible to eliminate the error by changing the size of the time step
for the calculation or by altering the removal constants, This type of
error is most likely to cceur in a calculation where rapid removal of
many materials at the same rate occurs as, for example, in the calcula-
tion of the inveptory remaining in a tank that is being decontaminated
by treatment in an external purification system. 1If the time interval
tfor the calculation is large conpared with the time required to process
one tank volume through the purification system, the problem may be
encountered. Tor certain problems of this type, the program may not
be suitable, Nevertheless, difficulties should not occur in normal

m

caleulations of the properties of dilscharsged scolid fuels.
™

The subroutine EQUIL employs the Gauss-Seidel successive iteration
technique to calculate the concentrations of short-lived nmaclides with
long~-lived precursors or with external sources. In calculations involving
isotope buildup and decay in fixed fuelg, this algorithm has been found
to converge very rapidly. However, in systems involving fluid fuels with
recycele, the methed converges slowly, if at all. There is a variable
in subroutine EQUIL that counts the number of iterations and, when 100
iterations are reached withoubt convergence, causes the calculation to
be terminated and the Tollowing message to be printed: "GAUSS-SEIDEL

TTERATION DID NOT CONVERGE 1IN ®QUIL,™
63

&, APPENDTX

The following tables show some of the information printed as output
by the ORIGEN code. TYor brevity, many of the longer tables have been

omitted, and only the summary tables have been included.
TaBLE A-1, HucLEar DaTta LiBRARY FOR Rererenck PWR CaLcULATION

WOCLEAR TRANSMUTRTION DATR PEVISED 3/20/773

MUCL = NUCLIDE = 10000 * ATONMIC NC + 70 * MASS MO 4 ISOMS®TC STATE (0 OR 1) DLAWM = DFCRY CONSTANT (1/SEC).
®B, TP, Fi, P" = PRACTTONAL TFCAY BY BEFE, POSITEON (OR FLFCTPOX CADTUPE), ALPHE, THTFPNAL TBANSITION, PR = } -~ PP = FR = PT
FBt, PE1, PNG1, TE2N1 = FREACTION OF BPTR, POSTTRON, N-GAMME, N-2¥ TRANSTTTONS T0 FXCTTED STETF® OF DRODUCT NUCLTIDE
STGTH, SIG¥G, SIGF, SIGNR, STGNP = THERMAL CROSS SECTTONS (BAPNS) FOR ABSOPPTTON, N-GAMMA, FTSSTON, %¥-ATPHE, N-PPOTON,

STGNG = SIGTH * (1 - FNA -FNP), SIGNA = SIGTH * FNA, SIGND = STGTH * FNP, TFPNA, PNP = PRACTINY THFRMAT W-ALPHE, N-PROTON,
RTTH, RYNG, ®I¥, PTNR, RPINP = RPSONIWCE TXTEGRRL POR ABSORPTION, W=-GRKMA, FTSSTON, N-ALPHA, N-DROTOR.

BFTNG = FYITH * (1 -~ PINA - FTHP}, PINA = RI™F * PYN¥A, BTND = PITH % PTNP, PINA, FTNP = FRACTTON TFSONANCE E-ATTH1, N-DROTON,
SIGHEY, SIGFP, SIGK2N, STGNAF, SIGNEF = ®PAST CPOSS SFCTTONS (BARNS) FOP ABSORP™TON,FISSTON, N-2F, N-21DPHE, N-DROTON,

STGN2K = STGMEV * (1 - FFE} - FFNPj, SIGNARF = SIGMEV * FFNA, STGNOF = STGMRV % PFND, TPFNR, PPNDP = PPACTTON PAS™ N-RYDHA, W-D,
Y23, ¥25, Y02, ¥28, Y89 = PISSTON YIFLD (DEPCENT) TROX 233-U, 235-0, 232-7TH, 238-y, 239- PO,
Q = HEAT PER DISIRTRGVATION., FG = FRACTION OF HEAT™ TN GRMMAS OF ENERGY GREATE® THEN 0.2 MEY,

EFFEFCTIVE CPROSS SECTIONS FOR R VOLUME RYERAGED THEPMAL (1™ 0,876 EV} FIUX AR* 2S FOLLOWS,

¥-GAMMR - SIGNG * THFRM + RING * RES. :

FISSICK = STGF * THERM + RIP # BFS 4+ SIGFF * FisT, THERM = 1/V COPRECTION FO® THEFRNMAL SPECTRUM AND TEMPFPITUPE,

N-2% ~ SIGNZF * FAST, RES = RRTYC OF FRSOWAWCE FITX PEP LETHRARGY ONIT 70 THRSMAL PLUX,
W~-ALPHE - SIGHA * THERM + RINL ¥ PRS + STIGNARF * FRST, FIST = 1,45 %  FATIO OF PAST {67 1.0 MEV} PO THERMAL PILOX

N~-PROTON -~ SIGKP * TEERM + ETHP * BES + STGNPF % FAST,

REPERENCES
HML® TIVES, DECAY SCHEMES, AND THFRXAL DPONWER
¥ LEDERER, J K HOLLANDER, AKD T PERLMAZN *TABLY OF TSCTOPES - STXTH EDITTON! JOWN RILEY 2KD SONS, INC (196T)
S DZEELFPOV AND L K PEKER *DECHY SCHFMES OF PADIGACTIVE WUCLREY' PETGANMON DPPFSS (1961}
T GOLDMAX AND JAMES ® POSSEP *CHAPT OF THF NUCILIDESY NINTR ZOITION GEREWAL ELECTRIC €O (JULY 1966}
D ERNOLD !'PTROGRAN SPECTEAt APPPNDTY A OF ORNL-3576 (RPEIL 1964)
CPOSS SECTIONS AFD FLUX SPRECTPR
® PPTHCE 'NRUTRON PEACTTON PATES TH THF WSRE SPECTPUMt ORNL-U118, PP 79-83 (JULY 1967)
¥ PRINCE 'NEUTRON PNERGY SPECT®R TN MSPE END MSEP* OPNL-G191, PP 50-58 (DEC 1967)
D GOLDBEPG BT AL 'NEOTEON CROSS SECTIONSY BWL-325, SPCORD %D, SUPD KO 2 (MEY 4964 - ADG 1966) 21LSO BAPLIEP PDITIONS
T KFPR, UNPUBLISHED EPC COMPILATION (PEB 1968)
¥ K DRAKP 'A COMPILATTON OF RPSORANCE INTRGRALS! NWUCLEONICS, VOL 24, %0 8, PP 108-111 (RUG 1968)
BNWL STAFF 'INVESTIGATION OF N-2N CEOSS SPCTICNS' BWHC-98, PT Bu-98 (JUNE 1965)
# ALTER AND C F WPBFR 'PRODUCTTION OF H AND HE TH METALS DUPING PRACTOR TERADIATION! J NWUCL MATLS, VOL 16, PP 68-73 (1965)
1 1L BEYEETT ?'PECOKXENDED FISSION PRODUCT CHAINS FOR USE TN FRACTOR EVRALUZTTON STUDTES! OPNL-TH-1658 (SEDT 1966)
FTSSIOF PRODUCT YTELDS
M F MEFK END B P RTDER, fSUMKAERY OF PISSTON PRODUCT YIPLDS FOP U-235, U-233, PU-239, AND PU-281 BT THERMAL, PISSTION SPFCTRUX AND
14 ®EY FEUTRON ENERGTESY ADPED-5398<-A{REV.}, (OCT, 1968) '
S KATCOPF ' PTSSTION PRODUCTYIELDS FROM NPUTRON YSDUCED FISSION! HUCLPONICS, VOL 18, X0 11, (NOV 1960)
¥ D DUDEY ' PEVIEW CF LOW-MASS ATOK PEODUCTTON TN PAST REACTORS' ANL-7834,(ADPRIL 1968)

g O}

xR ww

THEF M= D.63200 RES= 0.33300 FRST= 2.00000
NPUTRON SOURCE= 922330 9223%0 Q42810 922380 352390 ¥LIBP= 2

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FTOF PTSSTON PRODUCTS

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PHOTORS/DISINTEGRATION POP TFISSIONWN PRODUCTS

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A-2 (conTInwED)

TABLE

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Tasike A-3, Isotoeic ConcenTRATIONS (G-ATOM/METRIC Ton OF U) OF CLADDING AND STRUCTURAL MATERIALS AS A FUNCTION OF
IrraDIATION TiME (DAYS)
REFERENCR DPWR FPQUITIBFTUM POEL CYCLE ~- 3.3 0/0 FNRICHRD J
DORER= 30.00MW, BURNUD= 33000, MWD, TLUY= 2,92F 13N /CH %2 =877
HOCLTDE CONCENTPATTONS, GPAM ATOMS
HrETS = M7 OF BEFEVY METAL CHAEGED TC FFACTOR
CHAPGT 140, D 220, D 330. D 540, D 550, N §60. D 770, D 880, D 990. D
1 0.0 7.157-03 1.43F=02 2.16E-02 2,91m=-02 3,69%-02 L,u9E-02 5.30F-02 6.219-02 7,12%-02
2 0.0 5. 329-07 9.30F-07 2.92E~06 3,B5E-06 6.39F~06 9,21F-06 1.30E-05 1,767-05 2.32E-05
30,0 5. 54m-13 G.25F-12 1.L0F-11 3.302-1% €,45E=1% 1,12%-10 1,B0F-10 2,73F-10 3,95F-10
0.0 5 44p-33 2.07F=32 1.36%-31 3,93r-3% §,93F-3% 1.74T-30 3,058-30 L.97E~3D T,63E-30
3 0.0 5. 03E=15 2.72F-1% 1.17%-13 3.22F-13 6.90E-%3 1.27F-12 2.,70E-32 3,23E-12 U, 702-12
5 0.0 S LOR-CL  1.08E-03 1.628-03 2,38%-03 2.76%-03 3,36E-03 2,98F-93 L.62F-03 5.299-03
6 0.0 5. 4GE-18 L,39F-18 7T.659P-18 §.07E~-17  1,80E-17 1,78E-17 2,208-37 Z,87F-17 3,19%-17
6 0.0 9.58P-12 3.63F-11 7.85F-11 1,352-10 2,06%-1¢ 2.908-10 3,87F-10 4, 97E-10 &, 18F-10
7 0.0 §.00%-21 4.187-19 5.20E-19 1.51P-18 3.43%F-18 6.6%7-18 1,17F-17 1,91F-17 2,93E-17
8 0.0 £.51F-33 9.16F-32 4.27E-3% 1.28E-30 3.01®-30 6.09F-30 1, 11E-29 1.89F-29 3,022-29
8 0.0 1.80m-33 3.19F-33 4.912-33 6,82F-33 8.96E-33 1, 14E-32 1,61E-32 1,71F-32 2,04°-32
g 0.0 3.31P-07 6.62F-07 1.008-06 1.35%-06 1.71%=08 2.08E-06 2.LBF-06 2,.686F-06 3,318-C6
10 0,0 1.79%-32 7.96F-12 t.638=11 2,97P-11 &,77%=-11 7.10%8-1%1 1, 00F-10 1.36E-10 ¥,797-10
11 0.0 3.0 0.0 0.9 0.0 0.0 0.0 0.0 0.0 0.0
10 0.9 &.178-20 2.855F~10 §,3LE-19 4,780%-18 3,03B-%8 4,70%-18 6,77E-18 9.207-18 1.21E-17
11 0.0 L. 43F-2L  7,69F-23 3.66E-22 1,19P-21 3,02F-2% 6,55E-21 1,27E-20 2,29E-20 3.36%P-20
12 0.0 1.057-38 1.68F=37 E.837-37 2.968F-36 T ,B0E=3§ 1, 76F=-3%5 3I,%6F-35 6,66F-33 1, 17 E=-30
12 1.B0T 0D 1.50F 00 J.50F 00 1.50FE 00 1.50% 00 1,507 00 1,50 OGC 3.50® 00 1.50E 00 1,507 00
13 0.0 1.03F=06 2.05E-05 3,10%-06 &,18F-06 S,30%-06 6.%6F-06 7,67E-06 B, 9UF-06 1.03F-05
1w 0,0 2.458-14 2.86F-13 5.53E-13 1.19%=12 1.91F-12 2.B4E-12 U4,00F-12 5,83¥-12 7.35E-12
13 0.0 0.0 9.0 0.0 0,0 0.0 0.0 0.0 5.0 )
1 0.0 8.68F-19 6.95%-18 2.3€F~17 5.66E-17 1.12R=16 1,98F-16 3.22F-16 $.93E-16 7,21B-18
15 0.0 2. 53P-24 4.05F~23 2,00¥-22 6,81E-22 1.73F-21 3.75%-21 7,28P-2% 1.3YE-20 2.218-20
15 0.0 >.0CF-35 3.35F-3% 1.76%-33 6.07F-3% 1,63¥-32 3,7UE-32 7.76E-32 1,89F~37 2,697-31
16 0.0 0.0 5 0OF-35 3.56E-34 2. 14P-33 B8.21F-33 2,55P-32 6.39E-32 1.39%-371 1, 487-25
17 0.0 0.0 4. 0GF-25 1.25B-24 4,557-24 1,21R-23 2,70F-23 5.39F-23 9,95%¥-23 1,73P-22
18 0.0 2.,97®-1%86 2.39%7=-15 B.,2L4E~15 2.027=18 4, 9%F-1L T, L46F-90 1, 25F= 13 1,97F-13 2,98F-13
19 0,0 G.06F-29 3.26%-28 1,158-27 2.90E-27 6,12¥-27 1,162-26 2.02F-26 3.32F-28 5,22%-26
19 0,0 5. 34F-24 1.70%-23 1.938-22 6,37%-22 1.€5%-21 3,688-21 7,25F-21 1,33F-20 2,31%-20
20 0.0 3.848-26 1.42F-25 3,30E-25 &.18F-25 1.03%-28 1.59F-28 2,3LF-24  3,31F-2¢ L, K42-24
20 0.0 3 fEF-21 6.65F-20 1,95E-19 L,77F-10 0,72%-19 1,76¥-1§ 2.96F-18 U, 67F-1R 7.06%-18
21 0.0 B.oELF-13 1.86F-12 L, 26B~12 T.74F-12 1.2LE-13  1,85F=11 2.632-11 3,53F-17 4, 65F-1]
22 0.0 9.18%-13 13.68P-12 8.39%-72 71.52F-11 2,85F-11 3, 68F-11 5,10P-11 6.98F-%1 9, 18F-1]
23 0.0 8.068-19 1,79F=18 2,77%-16 3,84F-18 5,05F-18 6,LiE-18 7.93F-18 9.63F-i8 1, 15F~17
22 0.0 0.0 9.0 0.6 6.0 8,0 8.0 0.0 5.0 9.0
23 0.0 7. 85F=14  3.%4P-13 7.178-13 31.308-12 2.09%-12 3, 12F-312 L. 50F-12 5,967-12 7,852
2L 0.0 1. QUE-08 1.08F-08 1.07E-08 %, 10T=-08 .13F-0R 1, 18¥-06 3.23F-08 1. 29%-08 1, 34F-08
2 0,0 2 ggw-18 3.93F-18 6.06E-18 B8.41F-18 1, 11F=17 1,80%-%7 1,78F=-17 2,11%-17 2,52F-17
20 0,0 1.267-06 2.5LF-06 3.BUE-06 5,17E-06 6.56B-06 B8,00T-05 9.53F-06 1,117-0F 1,27P-05
25 0.0 3. 20F=07 L.B1E-07 6.66E-07 8,97P-07 1,16F-06 1,39F-06 1.65F-06 1.927-06 2,20E-06
26 0.0 1. 07F-07 2.13F-07 3.228-07 4.35FP=07 5.51%-07 §.73E-07 7,99F-07 9.31F-07 1,07E-06
27 0.0 5 9§F-10 5.27F-10 5.379-10 5.5L®-10 5,7uF-10 5,978-310 6,22F-10 6.L8F-30 6,76F-10
57 L.00F 90 4.00F 00 4.00F 00 GL,00F 00 4.00% 00 4,007 DO 4.00F OC 4,007 00 L.00F 00 4,00F 00
28 0.0 n.377-00 4.329-09 L,L1E-00 L, S4E-09 G4,71E-09 u,90F-09 5,11F-09 5,32B-09 5.54F-09
20 0,0 2.798=12 2.74F-32 2.77P-%2 2,85%-12 2.96B-12 3,08F-12 3.21E-12 3,34F-12 I, UB®-12
28 $.,07 €.07P-01 5.07F-01 6.087-0% &,08E-01 &,08P-0%1 €,0RE-01 6.08F-0% 6.09%-0% 6,29E~01
29 3,40 3. 00P-02 3, L50F-02 3.20T-02 3, 40E-02 3,407-02 3.80B-02 3.40F-0Z 3.L1E-02 3.41=-02
30 0.0 1. uEP-NE 2.95F-06 L,26E-06 6.01E-06 7.62F~06 9.30F-06 1,10¥~-05 1.298-0% 1.UL8E-0S
31 0.0 3. 60®=14 7.21E-1&  $.11B-13 1.50F-13 2.03%-13 2,587-13 3,19P-13 3.87F-13 0U.63F-13
31 0.0 1.26E-11 5.037-11 1.158-16 2.,09E-10 3.35%-10 4,99F-10 7,084%F-10 6,55F-10 1,26E-09
32 0,0 6. 05P=17 2.9GE-16 7.16E-16 1,38F-15 2,3tE-15 3,67F-15 5,80F=-15 7,74E-15 1,07F=14
33 0.0 0.0 0,0 0.0 0.0 0.0 0.0 0,9 0.0 n.0

1100, D
8.07E~02
2.98¥7-05
5.51E=-10
1.12F=29
6,5LF-12
5.987-02
3.77%-17
7.51F-10
4,307
4.62F7-29
2.41¥9-32
3.75F-06
2.30F-10
0.0
7. 5UE-17
6. 22F-20
1.96F-3L
1.50% 00
1. 16705
9, 797-12
0,0
1.02F-15
3.587=-20
U.fi}v_—S'}
£,037-25
2.85E-22
b,3ar-143
7.91F=-2¢€
30815"’20
6. 07F=-24
1. 037=-17
5.97F~-11
7., 18710
J.36%-17
0.C
1.03P-11
1.397-58
2.97E-17
1. 04%-05
2.50F-06
1.217-06
7,03F-10
L,00% 00
%.,77F-09
3.63F-12
6. 09F-01
3.217-C2
1.67%7-05
5.467-13
1.62%-009
1, 43F-14
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TapLe A-3 (CONTINUED)

REFTFRENCE PWR EQUTLTBRIUM FUEL CYCLE -~ 3.3 0/0 FHRICH®D

POWER= 30.00MVW, BURNOP= 33000.HWD, FLUX= 2.92F 13XR/CH*x*2-SEC

WUCLTIEE CONCERTRRTTONS, GREM ATOMS
BASTS = MT OF HEAVY MRTAL CHARGED
CHAPRGE 110, D 220. D 330. 1 480, D 550. » 660, D
3a 2.9 7.328-30 5,87F=-29 2,06E=28 5,21%=28 1.10E=-27 2,0BE=-27
32 0.0 9.828~-17 9.,518-16 3.56E-t5 9,10%-15 1.90%-14 3,51E-14
33 0.0 0.0 .0 0.0 0,0 0.0 0.0
34 0.0 8,732~-25 1.56FE-23 B8,11¥-23 2.68F-22 6.92E-22 1,537-2%
35 0.0 0.0 0.0 0.0 0.0 0.0 0.0
36 0.0 0.0 0.0 0.0 0.0 0,0 0.0
17 0.0 9,14E=-22 3,66F-21 8,538E-2% 1,60E-20 2,66¥=20 &4, 11R=-20
35 0.0 0,0 0.0 0.0 0.0 0.0 0.0
36 g¢.0 0,0 .0 0.0 0.0 0.0 0.0
37 0.0 6£.618-18 5,30F-17 1.82E-16 U4, 4TFR=-16 9,11E-16 1,65E-15
38 0.0 $.518+-25 1.2%F-20 4,25B-2L 1,07%-23 2,26F-23 4,27F-23
386 0.0 ¢.0 0.0 0,0 0.0 0.0 0.0
37 0.0 G.,C 0.0 0.0 0.0 0.0 0.0
38 6.0 1«118-22 1t,78¥-21 9.25E=-21 3,06F-20 7,89E-20 1,75R-19
3% ¢.0 5.568-23 7.,98F¥-22 3,70r-21 1,09r-20 2,.51%-20 4,85g-20
40 .0 2.038-13 8.13E~-1%3 1.86E-12 3,37E~-12 5,82%-12 B,06E~-12
51 6.0 1.28F=17 2.57F=17 3.,96%=17 5,50F=17 7,.23%=17 9,18E-17
39 0.0 0.0 8.0 1.498-24 6,75%-28 2,.01E-23 #,83E-23
40 0.0 8.0 0.0 ¢.0 0.0 0.0 G.0C
4t C.0 €E.01E=-15 2.57E-18 5.86B-1¢ 1.07F-13 1.71%-13 2,5%5E-13
42 g.0 3.778-19 1,32¥-18 2.67E~-18 4,38F-1R 6,U840P-18 B,RLE-1R
L3 0,0 2,018«-15 4,03%=-15 €,218~-15 8,62F=15 1, 13E=-14 1, 404F=-18
hu 0.0 5,87TE=18 1.1BF¥=17 1,8%1E=-17 2,52F=-17 3,30%=-17 4, 197=17
40 0.0 0.0 ¢.0 0.0 £, 0 0.0 0.8
a1 ¢.0 0.0 G.0 0.0 0.0 0.0 0.0
a2 0.0 1.812-17 1.,38%-16 4,30F~-16 9.53E=-1€ 1.76B=15 2,90F=-15
u3 0.0 9.,B6E-0B 1.9%97E-07 2,98F-07 4,02B-07 S5.09F¥-07 6.21E=-07
40 0.0 T.47E=-07 1,89F-06 2,28%-06 3,042-06 3,86%-06 4,70E-0%
4e 0.0 1.20E-068 1.96F-08 2,46F7-08 2,81%-08 3,07%-08 3,29F-08
46 .0 8.16E-0B 1.€5F=07 2,31E-07 3,L1E~07 L,36F=-07 35,36%=-07
L G.0 2.588~-12 2,81E~-12 3,118-12 3,07E~-12 3,88F-12 4,35F=-12
48 0,0 0.0 6.0 0.0 0.0 .0 0.0
49 .0 0.0 G.0 0.0 C.0 a0 0.0
Y 0.C 2,99F=09 1,08E=0f 2,06F=-08 3,27E-08 U,61B-08 6,06FE-02
t§ 2.0 1.26E-06 1,77E=C€ 2.00F-06 2.138-06 2,23B-06 2,32E-06
L7 .0 1.348-07 - 1,35%-07 1,378=-07 1. 41E-07 1,U8TF-07 4,52P-07
48 0.0 €.8u48=-09 &,BUF-09 £.97E~09 7.17E=-09 7,U43%7=-09 7,TV1E=-09
ag 6.0 1.238-1C 1.25E-10 1,29%-10 1,35E-10 1,43E=-10 1,51E-10
5¢ 6.0 7.69E-14 T7.69F-1L T7.B5E-14 §,09F-18 #,39%-14 8,TEE-14
Lg 3,08F-01 3,0uF=-0% 3.02F-G1 3.04¥-01 3.04P-01 3.08%=-01 3. 04E-01
47 2!’772-’)1 2.773-01 2077E_01 24773"01 2.‘?7P”01 2 7-?3_01 2.773'01
48 2,772 00 2,77k 00 2,76E 00 2.76% 00 2,7€® OO0 + 75% 00 2,75% 00
L5 2,042-01 2,078-01 2,11E~-01 2,14E=-01 2,18FE=01 2,21E=01 2,25R~01
50 2,80F-0% 2.00F-0% 2.00E-01 2.00E~0% 2.00E-01 2,00F=0%1 2,00E-01
51 0. 2,31E-10 2.32¥-10 2,36F-10 2,84E~-10 2,.353E-10 2.63F-10
49 0.0 g.¢C 0.0 0.0 .0 0.0 0.0
50 0.0 €.22E-05 1,28E=-04 1,85%-00 2,48F-04 3,11FE-08 3,77F-008
51 0.0 B.75F-03 2.17¥~02 3,51E-02 4,87%~02 6,29E=-02 7,758-02
52 0.0 B.96E-10 1,20%-09 1{.54%-09 1,92E-09 2,35%-0% 2,83F-09
£3 €.0 $.688~12 5,67%-12 5,78®-12 5,94FE~-12 §,15E-12 &, 38E-12
54 0.0 2.E1E=-14 2,54F=-11 «72E=14  2,88F-14 2,98%-14 3, 13B-14
50 £.08% ¢0 S5,CL3% 00 5,01F 00 5,008 00 &,99F G0 4,379 00 #,.86F 0D

TO PPALTOR

770, D
3,62F=-27
5.95F-14

- 5 = e
o
t
1
b
—h

Ut
531
1
[
>

-3
o
4
—
m

67-23

-

DDA OO NDDO WD
-
DO E QOO OOOA0

3.47E-19
8,78%=-20
1. 14E=-11
1. 14E~ 186
1.01¥-22
0.0

3.60%-13
1, 16R-17
1| 782-13
5. 19E~- 17
0.0

0,0

!1. LLBF- 15
7.38E-G7
5. 59E-0%
3.bBE- 0B
60 Q3F"0-7
4,88F=-12
0.0

Oso

7.59E-08
2,42E-06
1. 59E=-07
BOOBE‘*OQ
1, 607=-10
9, 11E=-14
3.0uF-01
2. 77E~-01
2.75F 00
20 29E“01
2, 018-01
2, F4E- 10
0.0

4- QBE-OH
9, 26F-02
3- 37?‘09
6. GuE‘ 12
3.31E~-18
4,94E 00

880. D
Bs 37E=27
G,48E=-14
9.0
5.618-21
1.57E~25
0.9
8,55R-20
0.0
0.0
k,37w-15
1. 23F-22
0.0
0.0
6: 39E' 19
1. U E-1g
1.56F-11
1. 38E~- 16
1, 898-22
0.0
0, 83E-13
1.877-17
Z, 16F=1L
6,30%=-147
C.0
0. G
6,41E-15

. BOE=07
6. S1E-D06
3.66E-08
7. 558-07
S LAB-12
0.C
0.3
9,20%-08
2.53E-06
1. SSE-G.T
B.36¥%-098
1. HE=-10
9- go&“‘fl
3.0uE-01
2. 7”3‘01
2.74E 00
20 33}3‘01
2,018-01
2.86E-10
0.0
. 12FE-00
1. 088=-01
3' QSF-GQ
6.217-12
3. 49B=-104
4,938 00

990, D
9,398-27
1. 440F-13
0.0
9, 7T1E-21
3. 22B-25
0.0
1. 178-19
1.36E=-25
0.0
6.60%-15
1. 938-22
0-0
0.0
1- 11E‘1B
2.23F=18
2.03r-11
1. 65E=~= 1€
3. 30m-22
c. ¢
€. 42E-13
1. 828-17

. SSE‘?B
7.538-17
5.0
0.0
B,BBE-15
9, BEE=07
T UEE- D6
3.83E-08

. 758-07
6, 13¥8-12
0.0
¢. 0
1. 098-07
2.63R-06
‘o"ZE-O-’
Ba SQE‘GQ
1. 801"‘10
g. 903‘1&
3.047=-01
2, 7TE-01
2,78% 00
2. 3BE-01
2. 018B=-01
2.988-10
0.0
5. 818-04
1.28%8=-01
4, 628=-09
7. 18%=-12
3.68E-14
4,912 00

1100, D
1,827=26
2. 118-13
0.0
1.60F-20
5.86%-25
0.0
1.578-19
S, 27E-25
¢.0
9.62F~15
2.93E-22
0'0
0.0
1.83F-18
3,298-19
2.61E=-11
1.95F=16
5. U2E-22
1. 50E-25
B.258E-13
2.21?‘.‘"
3. Qfl?-‘fi
8.88R%-17
8.0
0.0
. 197~ 14
1.12F=06
B.LE¥=-08
4,007-08
1. 00906
5.B8%E8=-12
8.0
.0
1.262-07
2.7LE-06
1- 79?‘0-’
9003?-09
1. 91E=10
1,03%-13
3.04%-01
2,76%-01
2.73% 00
2.027=-01%
2.0?53-01
3. 117=10
4.0

. 522"0“
1.“2?'—01
5.338-0%
TLU5F=12
3.888-14
k,.89% 00

1oL
TaBLE A-3 (CoNTINGED)

DPFFRFPENCR PYR FOUILIERTGHM PUTL €CYCLE -- 3.3 §/0 ENPICHED U
POWFE=  30.00m%, BUP¥ODP= 33000, MWD, FLOUOXs 2,927 13N/C8N*%*2-5EC
NUCIIDF CONCENTPRTIONS, GPRM ATOMS
BASTS = MT OF AFAVY METRL CHARGED TO PEACTOR

CHARGE 110. D 220. D 330. O Lup, D 550, D 650, D 770. D geg. o 980. D 1900. D
CF 51 2.0 4,.52E-03 L.E1F-03 4,90%-03 S.0U8F-03 65.20%-03 5.40E-03 5.80r-03 5,82F-03 6,052-03 6£.,277-03
cr 52 5,74 01 S,74® 0% 5,747 0% 5,747 01 5.7ULE D1 5.74® Ot 5,78F 01 5,74F 09 5,74® 0% 8, ME 1 S.73E 0%
Cr 53 E.,0%F 00 5,408 00 6.39% 00 6.38F 00 &.,37F 00 5,.3I6F 00 6,357 00 &§.34F 00 6.32F 00 6.3%E D0 5.29F OO
TR S5t 1.,57% 00 1.89% 00 1.681FE OC 1.63F 00 1,65% 00 ¥,67% 00 1,897 00 1.71F 00 1.73%7 00 758 20 %,77F 0O
c® 55 0,0 2.998=-09 3.43F-09 3,%2B-09 3,257-09 3,41E-09 3,59%F-09% 3.79r-09 u.00F-09 2,228-09% L,6457-0%9
ME 504 0.0 1.168-06 2,06F-Dk 2.7BF-04 3,38%E-08 3.8%E-04 4,33E-080 4,73R-04 5,%02-04 S5,44%m-0%  5,77F-01
KN 55 3,27P-0%  3,26F-01 3.285F-01 3.25BE-0% 3.20P-0% 3.23F-0% 3,23F-0% 3.23E-07 3,23%-01 3.23%w-01 3.227-01
BN 56 .0 1.82F-06 1,82F-06 1.B85E-06 1.90%-06 1,96E-08 2,04F-06 2,12F-06 2,20F7-08 2,292-05 2,377-06
MN 57 0.0 4,46F=12 4,53F-12 U4,70%-12 H4,92F-192 S5,18%-12 S,U8F-12 5,81F-12 6.16F-12 6.54F-12 6.93%-12
MN 58 0.0 1.5%8-1%4  1,.56%-10 1,62F-14 1,69E-14 1, 78E-4 «BRE=-4 1.99E-14 2, 11F-14 2. 247°- 2.37m-11
F2 504 8,0LF D0 4.03% 00 4,03F% 00 4,037 00 4,.03F 00 4.03F 00 4,02F 60 L,0Z2 00 4,028 00 4,029 GO 4,917 0D
FE 5% 0.0 .75%-93 3,37E-03 U,90F-03 £,37E~03 7.79%-023 9,17F-03  3,05F-02 1,19%-02 1.32E-C2 %,45F7-02
Ty 56 6,108 01 6.10% D1 6.310E 0% 5.%0F 0% 6,09%F 0% 6,097 91 6,097 01 6.097 01 6,087 01 6A,08% 03 £.08F 01
¥F 57 1.4U7 00 1.LSE 00 1.49F 00  $.S4F OC 1,537 GO 1.56F OC 1.58E 00 1.61E €GO f.548% 00 1.67E 00 4,70F 00
?F 58 3,107-01 3,73P-01 3,17F-0% 3.22BE-0% 3,272-0% 3.327-0% 3,387-9% 3,0U3P-07 3.49F-0% 3.55F-01 3.61E-01
¥E 59 0.0 4,217-05% G6.05E-05 5,3%e-0% 5,6%1B-0% §,C0318-05 6,28F-05 6,60%7-0% 7,00F-05 7T,81E-0S5 T.HLER-05
co 58% 0.0 0.0 0.0 0.0 0.0 0.¢ D.0 9.0 0.0 0.¢ 0.0
CO 58 0.0 3.237-03 3.98¥-03  4,208-03 &,32E-03 U4,83F-03 4,56F~03 4.69%E-03 L,82F-02 4.95E-G3  5,0%F-013
co 59 9,15F-01 9.0%®-(01 B.96F-01 §,87F-0? B8.77F-01 8.68%9-071 8.597~01 B.L9F-0%1 B.39F-0% §&,29FE-0%1 B,187-01
co 60M 0.0 g.,u4P-07  5,39F7-07 S5,458~07 5.55g-07 .692-07 5.86E-07 £,03F-07 €,22F-07 £.U40F-07  E,57F7-07
co 60 0.0 04P-02 2,03F-02 2.99%-02 3.937-02 UL,B8RE~02 5,79P7-(G2 6,71E-02 7T,63%-02 8.55E-02 G,47F-02
TO 81 0.C 1.028-08 1.85F-08 2.74B-0& 3,627-08 Uu,64F7-0f 5,583-08 6.83F-08 BH.087-02 G,UIF-08 1.08F-07
TO 62 0.0 3.50r=11  3.49E-11 3,56E-%1 3,€6€7-1% 3.78F-1 3,927-%% L.08F-1Y  L.2LE-71% LoLR-9Y 0 L.RT7E-9%
NT 5§ 1,328 02 1.92®m 02 1.92%F €2  1.%12F 02 1.%27 02 1,¥1E 02 1,11% 02 1.%31FE 92 .17 02 . 1I1E 92 1.%1%m 02
¥T 5% G.0 T.63P-02 1.537=07 2.30%E-01% L10E=01 3.63%-0%1 L,79F-01 5.%59F-071 6.637-01 T.60R-0% R, E1F-{1
NT &0 L,18F 09 4,.%8F 0% L,%8F 01 0,972 63 L.37F U1 G.1TR 0% 4.97F 0% L PF G Lo%6F 01 UL 16T 04 167 01
nT 51 1,877 Q0 .&9“ 00 1.G0F 00 1.92F 00 1.94F 00 1,9%F €0  1,97F 00 %,99% 00 2,01F 00 2,037 00 2.05F 00
NT 82 S5.B8LF G0 L6537 50 5,€2F 00 S5.61F 00 S5,59% (0 3,.%BE Q0 3,57F Q0 5.5%® 00 5,5iF 00 5.52% 00 5.514% (0
¥T 63 0.0 $.348-02 2.51F-02 3,98B-02 5,30%-02 6.,70%-02 B8,15F-02 9.5€6F~-02 1.12E-01 1.29BE-01 1.bL57-01
¥T 64 1.6%E 00 1 $18 00 1.5%F 00 1,B1F 00 1,617 DD 1.81F A0 1.RI1F 00 1.61F 00 1.61F Q0 1.64% 00 1,60% 00
NI 6% .0 £,238-97 5,23F=07 S,34E-07 £,50%-07 5.70E-07 5.93%-07 6,18E-07 S,4LE-07 6.707-07 6,97F-07
cu 62 C.0C 0.0 .0 0.0 0.7 0.0 0.0 0.0 2.7 0.0 0.0
T 63 c.C 1.LE9F=-08 E,93F-05 1.34E-00 2,38E-C4 3,75®-04  35,82P-04  7,43%-04  9,79T-04 3, 25%-03 1.56F-03
CU 64 9.0 .16F=-10 L.6%F-10 1,38¥-09 4,9LF-09 3,16F-09 4,76F-09 6,80E-09 9.34E-09 1.2LE-08 1.6%F-0R8
cr &5 0.0 3.73F—0u 7.47F~08  1,13%7-03 3,52F-03 1.93¥-03 2.35F7-03 2.79E-03 3.25P-03 3,72P-03 U4,22F-01
Co 66 0.0 9,86F=-12  1,98¥%-%1  3.04%-17 4.23%-91 5.55F-17 T7,04F-11 8,71F-11 1,06E~1C  1.26m-1C 1.49E-1D
Zw £3 0.0 0,0 0.0 0.0 0.0 Q.0 n.0 9.0 0.0 0.0 n.9o
¥ b4 0.0 2.00P-09 1,47FP-08 %,70B-08 4, 38F-07 2.77F-07 4.9LE-07 A.12E-07 1.26F-0f 1.RB6E-0F 2.6LF-0F
¥ 65 0.0 7.19%-14  1,08F=12 5,34F-12 1.65E-11 U4,03F-1%1 B,L2f-1% 9.58P-10 2,76¥~10 4,537-10 7,09F-1]
Z¥ 66 .0 1,06F=-07 4,25%=07 9Q.70F-07 1.76F~CG6 2.83F~06 UL, 217-0¢& 5,908E-06 R,06%-06 1,06%E~05 1,386%=-058
N 87 0.0 0.0 3.0 0.0 0.0 0.0 0.0 0.0 G.0 0.0 0.C
ZN &8 0.0 0.0 0.0 0.0 0.0 0.0 C.0 n.0o 0.0 0.0 D.0
Z¥ §9m 0.0 0.0 0.0 0.0 0.0 0.0 G.N 0.9 0.0 J.C 0.0
¥ 69 0.0 J.0 0.0 0.0 0.0 0,0 0.0 0.0 0.0 0.9 n.2
¥ 50 0.0 2.0 0.0 0.0 0.0 3.0 0.0 0,0 0.0 0,0 0.0
Zx 71 0.0 0.9 0.6 6.0 0.0 0.0 0,0 0.0 0.0 0.0 0.0
ZN 71 0.9 0,0 6.0 0.0 0.0 B.0 0.0 0.0 0.0 0.0 o.n
G: 69 0.0 0.0 0.0 0.0 C.C 0.0 0.0 0.0 0.0 0,0 0.0
G:r 7C 0.0 0.0 .0 0.0 0.0 0.0 0.0 c.0 0.0 0.0 .0
cr 73 0.0 0,0 0,0 0.0 0.0 0.0 0.0 0,90 0.0 0.0 0.¢
G¥ 10 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,20 0.0 0.0 0.0
ST 88 0.0 2.26F=08 L.51F-08 65,81F-04 9,38%-08 {,16F-03 1,02"=-03 1,68¥-03 1.957-03 2.25F-03 2.55F-03

¢0t
POWER=

B A9
? 90
R 91
Y 90
¥ S¢
Y 9
¥ 21
ZF 90
P 91
P 82
P 93
ZF% Su
ZR 95
Z% 9%
WB 92
HB 93m
B 93
HE b
¥B G2
HB 96
¥B 97
HC 92
MO 93
MO 931
MO Ob
NG 925
MO 96
RO 97
MmO S8
0o 99
MQ100
MC13
TC 99M
TC 9¢
TC101
UG
CD113M
CD113
CD115H
cBits
Ch119H
cb11%
CD1Z1
IN113
TR
TR119
TR12 1M
IN121
SH114
SK115
SN116
SN117X

REFERENCE PWE FQOILIBRIUM FUPL CYCLIE -- 3.3 /0 ENFICHED U

27 03
Tr 02
28 02

- - - . .

0r 02
58 01

3® 01

LU OD OO aDO TP WAaODOODODO
-

0F=-01

4 % & 8 @& § B 3 2 & & 8 © s & A

DNk QOO QDVDDOIIOOT &

9E-01
3E-01
8F 00

D E a0 OITIDDIHDODDIIISWN

30.00KMW, BURNUP=

110, b
8.80r~-06
9.8‘E‘10
1167?-08
0,0
2.20E~-05
2.558-10
2,53r-05
1.42E 03
3.06E (2
§,62% 02
3.868-02
L.60% 02
7.57E~03
7,258 01
3. SBE"O"
3.11%=06
1.032 01
1.75}3-fi3
2.€E7E-03
2.,722-08
2-29‘8-11
9,57%=-01
4,u5m=-05
3,36%-09
5l327¢"01
9. 19E-01

B, 46R-01

1,368 00
2,83E=-05
S.L0E=01
2.99E-08
2.21F-06
7.398-08
2,878-08
2.25P=-04
0.0

1.45E=-09
0.¢

2,268-11
O.Q

2, 62E-10
2.85E=15
c.0

fl|723-1&
S.1up=-13
2.528-15
0.0

2.19E=-01
1. 13E-01%
4,68F 00
9078}3‘03

TABLE A-3 (CONTINUED)

33000, MWD, FLUX= 2,92F 13R/CM**2-5EC

220. D
1. 08E-05
3.331-09
1.67E=-08
8.0
2. 20E-05
2.56F=-10
3.22E-05
1,828 03
3.06F 02
b,63F 02
7.72E~-02
4,608 02
9.92E-03
7.25% 019
3, 30E=-07
1.2L4%=08
1.03% C1
3QQ9F"O3
4,68%=-03
4,685-08
2- 29E-11
9.57E-01
8.90E=05
3.36E~-09
5.328-01
9- 183“'01
9, 77p-01
5. “61“"‘01
1.36% 00
2,83%~03
5.40F=01
2,99e-08
1.50F-03
2,87E~08
L, 47 =04
0.0
1.518=09
0.0
2,27~ 11
0.0
2,62E=-104
2. 85?"15
8.0
4,72E-1L
5. iuf"’ 13
0,0
2, 19F=01
1. 13801
4,678 00
9,82¥F-08

NUCLTDE CONCENTRATYIONS, GEBAM ATOMS

BRSTS = MNT CF HERVY ®ETAYL CHAPGED

330. D
1. 15805
60 808-09

« 70F=-08
0.0

2, 24E-05
3.48B~-0535
1,428 03
3.06F 02
L.63® 02
1. 17E-01
L.50F 02
1.0BE=-02
T.285F 0%
3.98E‘D7
2.78%=-08
1.03F G1
5.27E-03
5,L98-03
5.55%E-08
2,338=-11
8,57F-01
1,34E=-04
3.43r-09
5,32E-01
C.19E-01
9.877-01
B.LEF-0Y
1.36% 00
2.898=05
5.39F=01
3.058~-08
2.25?"‘06
2- 272‘-03
2.927-08
6, 72R=00
0‘0
1.51?‘09
0.0
2.31E-11
0.0
2,68F-74
2.918=15
0.0
4,82E-14
5.247-13
2.58E-15
0.0

20 19E"O“
1. 132-01
h.oe6® 40
1.00E~03

sug., D
1. 19%=05
1. 1BE=0R
0,0
2.31E-05
2.69E-10
3.60B~05
1. 627 03
3.06% Q2
$.63E 02
1. 57%-C1
4,60% €2
1. 13P-02
T.25E 1
4,10F-07
u‘ 93?"08
1.03% 01
7.098=-013
S5, B6E-03
€. 15E-0B
2, 40F- 11
$.57E=C1
1.81F-08
3.53r~-09
£.32¥-01
9- 21‘2"01
9, 97E~-01
5. 46E-01
1« 35% €0
2 QBE‘OS
5.397-01
3. 142-08
2.32E-06
3. 05E-03
3.018-08
9. OEE-OL\‘
€.
0.0
2.388-11
0.0
2, 78E=-14
3,00R~15
0.0
i

«96F-1L
£.39E~13
2.66E-15
0,0
2, 19E-01
1. 138=-01
4. 668 0D
1.03E~-03

S50. D
1.23¥-05
1. 73E-08
1.82%=-08
0.0
2.39E-05%
24792-10
3,.74F=-05
1,42% 03
3.05% 02
§.64% 02
1.998-01
4.60E 02
1. 188-02
7.25% 01
fl‘l 25}:.‘“07
7.72F-08
1.02F O
B, %8F-03
6.128~03
6.65%-08
2,497-11
g,c7E~01
2.30E=00
3,66%-09
5.328-01
9,2UFE-01%
1.01% 00
5.u6F=01
1.35% 00
3,08%-05
5.,39%-01%
3.25F-08
2.40E-06
3: 85 E"o3
3.128-08
1, 14R=03
0.0

- 513‘09
0.0

2. u-fllE" 11
0.0

20 863‘1“
3. 118=15
0.0

S. 157-14
5.58E-13
2.75E-15
0,0

2. 19F-01
1.13E-017
8.65E 00
1. 07E=03

£60, D
1.29E-G5
2. 4€E=-08
1.898-08
c.0
2. 49E-05
3. BBE-08
1. 427 03
3.05F 02
L. BUE 02
2, 428-01
4,602 02
1.22E-02
7,28F 61
u‘i u2E‘0‘f
1. 11E-07
1.02% 01
1, 09E-02
€. 37F-03
7.20=2-08
20 59?‘ 11
9.57F-C1
2,80®r=-04
3.81E-09
£,328-01
9, 26E~01
1. 02E 00
8, U6F~0 1
1. 35F €0
3, 21E=05
5, 397-01
3. 38E~08
2. 50E-06
4.67E~03
3.2uE-08
1. 38E=-03
0.0
1. 518=09
0.0
2. 577~-11
0.0
2.97r-11
3, 23e-15
.0
5. 35F-14
5.80%-13
2.867-1%
0.0
2. 19B=01
1.13=-01
4.6%% 00
1. 11r-03

TO REACTOR

770, D
‘t3u‘E-05
3, 35E~-08
1.978-08
0.0
2. 6CE-D5
3. 02?‘ 10
L, 04%~08
1. 42F 03
3.058 02
4,64F 02
2.87TR=-91
4,60F 02
1' 273“02
7.25% 0%
L,EQE~07
T.528-07
1.02F Ot
1. 30P-02
6.632-03
7.BO0E~-08
21 70E' 11
¢, 57R=-01
3.33F-04
3.97%-09
5.328-01
9.297-01
1. 03F 00
5u u6F“g1
1. 35% 00
3. 348=-05
5.38F-01
3.52E-08
2.60R-06
5- 52?"03
3- 382"08
t.64R=03
0.0
1,51E~06
0.0
2., GBE-11
¢.C
3.108-1L
3. 37?'15
0.0
5.58E- 14
6., OUR-13
2.98E-15
G'O
2, 19E-01
1. 13F-01
L,A84F 00
t.15E-03

880, D
1.“0?‘05
fl. qu'OB
2.068-08
0.0
2.71P-05
3.159‘10
H.ZGF-Gs
1.82% 03
3.04%® 02
4,64E D2
3. 31&}3*01
4,€0% 02
“a 33E-02
T.25FE Ot
4,.308=-07
2.00E~-07
1.02% ©1%
1.512-02
£.81%-03
B.UTE-D3B
2, B2F~ 11
9.57E-01
3.85E-00
4, 13p-0%
5.32%-01

.32E-01
1. 04F 00C
B BEF=01
1. 35% 00
3. 48E=-05
5.38%-01
3.67F-08
2.717=(6
69 38E-G3
3. 852F-08
1,90E=03
8.0
1. S0E- 06
8.0
2,80F-11
0.9
3.238-114
3.51E=15
0.0
5.810=-14
6. 29E"13
3. 11E"15
0.9
2,19F=-01
1. 138-01%
4.63% 00
1.207-03

990, D
1, 467-05
5| 69E-08
2. 1uw-08
2.0
2.82%-05
30 28E- ?0
4,377=05
1. 628 03
3.0LF 02
L,65F 02
3.83E-01
L,50% 02
1. 388-02
7,287 01
5.00®=-07
2,EB5E-07
1.028 01
1.739-C2
T.2%B~03
9. 20%~08
2:938-M11
9. 878-01
4, u5E-04
L, 31=2-09
5.328-01
9. 34R”-01
1.05E &0
S.45E=01
1. 35F 00
3.62%=-05
R.388-01
3. 82R-08
2- 82F" 06
7. 28R-013
3.67F=08
2,177=-03

2- 1QE-01
1. 13-
8,637 00
1.252-03

1100, D
1. 52?‘05
7.16E=08
2.239-08
e.0
2.93E-05
3,L2E8-10
L,85F7=058
1. 02% 03
3.08® 02
L, 63E Q2
B,347-01
L. 507 (2
1. QHF-UZ
7.25% 91
5,207=-07
3,16m=07
1.02% 01
1.9%¢-02
THE0°-03
9.96E~08
3,05F=-11
9.56F~-01
5,048~-00
4,48%=-0%9
£.327-01
9.37E-01
1.0677 00
5, 66F=01
1. 35% 00
3,778~-05
5.372-01%
3.988-08
Ze q3E"06
8,187-03
3.817-08
2, 453F=03
6.0
1. SOF-OQ
0.0
3. 04Lm-114
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3.508=-18
3,81F=15
G.0
€.308-14
6.80E-13
3. 37E- 15
0.0
2v 19F’01
1. 139-01
8,62% 00

£ol
POWER=

SNt117
SN118
SN119M
SN119
gN120
SK121M
sSHi29
Spi22
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TOTALS

FLOX

WODODI OO DMOIOIOOD SOOI OO . O
a & &4 83 B & 5 % e @& & & @& B a2 & a2 A 4 g 4 & 2 & s @ & s =B g s s
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30.00M9, BURNUP=

110, D
2.L7E 0O
7.73E 00
1. 037-05
2.70F 00
1.008 01
$,398-0%
1.3LE=-05
1.477 00
1. UBE~-0E
1.538-07
1.82F 0¢
3.358-09
1.95%-07
8.89?‘0”
4,08F=-05
1, 18E-13
1. 353-07
3.80F-05
¢.61E~13
1.528-09
E‘QQBE-QS
3.90=2-07
1.098-06
L,87E-09

<
-

WODOODDOO0DODO OO
s 4+ & & & B & % » & a a » 8
DDA DODOO DA DD

8% 03

2.587 13

Tagie £-3 (CONTINUED)

PEFERENCE PWR EQUILIBRIDM FUEL CYCLE -- 3.3 O/0 EWRICHFD N

33000, MWD, FLUX= 2,92F I3N/CM**2-S3EC

220. D
2.47F G0
7.70% 00
1.802-05
2.73F 00
.07 071
1, 28E=-05
1.35E-05
1.47E U0
1.48%-08
2' 37?‘07
T.82F 00
3.36E-09
1.95%-07
T 78?’03
8.0L¥E-05
2.27%-13
3.23F8-07
7.37F-05
1. 87F=-12
3,20F~-09
3.63F=07
1. 11E-0F
4,71r~0F
2.55F=~08

WO DO DA DDO
* a & [ I - 8 e & * & » a -

OO OQODOCOUOOO

TOCTLIDE CONCEXNTPRTIONS,
BASTIS =

330. D
2,47 00
7.74% 00
2.38E-05
2.738 00
1,048 01
1.938-05
1,378-05
1.678 GO
1.518-08
2.851-37
1.827 00
3.,437-09
1.99E-07
2.58E-03
1.29R-04
3.&7E' ?3
S, 18%-07
1.08¥-00
2,79%-12
B.,997-09
2. 018-07
1.89E-06
1,10R=-05
6.B0E-08
0.0

WOODDIO2DOCO
“ o & & 8
DO DO OTIIDIOO

8% 03

2,538 13

MT OF HFRYY MRETHL CHARSED
uz0, D 550. D 660. D
2,477 00 2.47F 00 2,LEER D0
7.75%F 00 7.75% 00 7.7fE 00
2.,B4F=-05 3,22P-05% 3.55F%-05
2,737 00 2.73F DO 2.72F 0O
1.04E 019 1.007 O1 1.02F Q7
Z.59P-0% 3,29%-0% L,Q0E-0B
. 44F-05 1.u45F=-05 1.5%2F-05
1., 498 00 1.87E 00 1.487% 0D
1.567-08 1.82FP-08 1,68E=08
3,167-07 3,39%-07 3.5BF7=-07
1.82F 00 1.82% 00 t.82F 00
3.53F-09 3.66%-09 3,817-09
2.08F~-07 2,93%-07 2,217=07
3,59F-03 &,53F=-03 5.49%-03
1,61P=-04 2,038-08 2,45F-04
B, 78E-13 6.23E-13 7,.BUE-13
T.298=07 9.34E-07 %, 16F-06
1. 81FP=0U  %1,742-08 2,086E-0L
3. 75E-492 4&,7%®-12 5,92F=-12
£.,8%E-0C 8,76F7-09 1,09F7-085
1.69F=-08 2.75%~-06 U,.09E=-06
2.86%=-08 3,U2E-D6 4,178-056
t1.98E~-05 3. 12F-05 4.50F-05
1.808-07 2.48FE-D7 4,04F-07
C.0 0.0 0,0
0.0 0.G 0.0
0.0 D.0 0.0
5.0 0.0 n.c
G.0 0.0 0.0
0.0 0.0 g.0
0.0 0.0 G,0
C.0 0.0 0.0
C.0 0.0 0.0
c.0 0.0 0.0
0.0 0.0 0.0
0.0 0.0 0.0
0.0 0.0 0.0
0.0C 0.0 0.0
3,687 03 3.08®% 03 3,088 03
2.7 13 2.8%% %3 2,93F 13

GRAM RTONS

™0 RFACTOP

770. D
2, 487 02
7.76F 00
3- SHE'OS
2,728 00
1. 047 01

2.317=-07
6. 47E-03
2. 897=-00
9.€2F-13
1, UOE=-06
2. 39F~-014
Te WE-12
1. 327-08
5.739-06
L.,91F-06
6, T4F=05
6. 16E=-07
0.0

0.0

0.0

830. D
2.U8F 00C
T.7TR 00
4, 13E-05
2,727 00
1.0u8 04
S5 52E8=05
1, 47E 00
1.83E-08

.93E-37
1.82F 0C
4, 13=-N9
2.407-07
7, u87-03
3.337-01
1.6 E-12
1. 6UF-06
2.74E-01
8.45B-12
1. 56F-08
="o 58?-66
5. 66F=-08
8.02E-05
8.96E-07

OO0 0
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3. 187 13

590. D
2. 58% 90
T.777 D0
b,367-05
2.73® 00
1.08% O
6.33E=-08%
1. T72%-05
t.47F 00
. 90F-08
L,i52-07
1,822 0C
4.31%-09
2.50E-07
8,527=-03
3.79E-04
1. 37E-12
1.90e-06
3.008-04
9.88E-12
1. 837-08
9.95R=-08
b, U1E~06
1.018-QU
1.26R=~C8

WD DODOODODDD>DO DO
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3,317 13

1100, D
2.458% QO
7.78F GO
4,607-0%
2.71F 00
1.0u4F 01
T, 1TE-0F
1.798-05
1.4L77 00
1.98F=-08
L,277-07
1.82% CC
5,087-09
2.63F=07
9,58%-03
4,25%-04
1.60F-12
2.17E=-05
3.37F-C2
1., 167-11
2. 11E-908
t.26E-0F%
7.17F-06
1. 25704
1.71%-06

DO

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x
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PB208
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PR21D
PE211
pBZiz
EBZ14
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BY210
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POZIL
BO215
PG216
Po218
RT217
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PN220
BEN222
PR221
FR223
RRE223
TR224
FR225
PR226
RE228
BC225
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TH228
TH229
TH230
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TH232
TH233
TH234
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Pa232
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« & & 2 B 40w

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30,008W, BOURNUP=

110, D
3.74E=-05
3.57E=20
3.80P-17
1.388-22
t,17%-20
1.97E=-16
1,198-12
5.53E=-19
5,94p~-17
2.708-19
2.178-14
3,77E=-2¢
8.89%-17
3: 23E‘ZO
1.618-20
2.,078=15
1.318-19
2.77R=2¢
1.0UR-19
10 9’4‘3“"25
1.098-25
1.918-28
4.€97=-27
2.24F-25

+ 52E‘20
bL.298-21
1. 49E-24
8,98%-22
3. 18R=17
7.74E=- 18
1.38E-20
5.,51F-21
1.23F7=18
1.79F=-13
Sc 95E‘17
T.18%=12
T.4EF~20
4,028-17
2.03%-13
T.T98~24
2.79E=18
30 fl2'§7"11
L,u8w-12
8. 8“3"07
1.56E-09
1. 50E=-08
2, 807~14
5.68P-08
7.U2E-08
g.01R~11
1. 13E-09

RFFERENCE EWP BQUILIBPION FUTL CYCLE

33000, 9D, FLUX=

220, D
1.728=08
2.83E-18
1.5&E"16
6,508-22
3.67E~18
3.295-15%
9,72F-12
2, 14 E=-18
8, 79E~14
1.83F-1%
F.5347=18
2.53E=10
1.287-1¢
B.37E-15
6.31E-1¢
1.05%~19
1,33F~18

« SEE=24
4,42E-25
9, 198-28
1.78%=-26
1.78E-24
34 QSE-'IB
1#63}2"20
7. 1ER-24
3.96F%-21
1.29%=-18
2: 933‘1‘7
5,44%-20
2.928-20
9. 7UE=18
7.20F=13
2.B85F=-1¢
4.508-12
5.71E-19
1.08BE-12
5.,95¥%=-23
1.86E=15
1.39E-10
1. 6L F~06
2.40F-09
5.73%-08
9. 14¥~14

5.91e-08

2. 07F-07
2.52E-10
4,31E=-09

BUCLIPE CONCENTRATYONS, GRRR 17T0ONS

BASTS = MNT OF HP2VY MR™AL CHARGED

330. »
5.18%-04
2,007-19
3.65E-16
1.63E=-21
2.558=-18
1. €1E-14
3.398-11
fiq B?E“"‘g
1,27E=15
€.808=18
2.088=13
3.06E-19
. E9T~15
81 Z?E-‘!g
4,058B~-19
1.98p-14
f.788-18
2.288=-19
£, 95L%=-18
5.90¥-28
1.058=-24
2. 318-27
3.818-26
5.652-28
8,187-19
3.49F=-20
1:80:&"23
1.286%-20
3.06%-16
5;29‘5"‘17
1.628=-19
8.007=~-20
3.098-15
1.728-12
7. 13E-18
3. 628~12
t.84%-18
L.85%=16
2.53E-15
3,287-10
3.85%-11
2.27%=08
3. 16E-09
1.23%-07
2.008-13
5.918=-08
3.86E-07
ug‘?gE"O
9105E"09

bup, v
1« 378-D3
2.01R-18
7. 06E=16
3. 28R=-21
9.75%~18
4,847~
g, ug=~-11
1.337-17
2.90F=-18
1. 528=-17
£, G2P=-13
5.17E-19
9. 72%=15
1:892" 18
9003E“19
3.83R~1L
3. 15%=18
3. 802" 19
1.093-23
2.02%=24
4, 59E=27
€.43E~26
1.26%=23
1. 588=18
5.888=20
3; 5‘,‘5“'23
2.807-20
5,90F-16
1.0€6E= 15
3.22%8=19
1.6EE=19
6- SQE" 15
3.317-12
1. 425-15
1. 623"‘11
4,188-18
9.65u=16
B.0BE~-12
b, 378-22
1. 1981k
£,33E-10
6.,85%-11
2,79E=-0§8
3.85E~-09
2, 09E-07

2 519‘13
5. 89E-08
€.,03%=-07
7.T2E=10
1,51E-08

2,92% 13V/CH**2-5FC

550, D
3. 24F-01
3,6%E~-18
1.228-15
5."7‘3-21
Za TOE=-17
V. 13‘E"13
1. 77810
2.36%-17
5,85E-15
2.7%2-17
€.97E-13
7.67E~19
2. 10FE-14

+ 56718
1.56E-118
E.E68R-14
5.60E~13
2.647-43
¥,28E-17
2- O1E“23
3.518-24
8. 16E~-27
9. 54 R=26
2.3Z8~-23
2.7 =18
B.73%-20
6.368-23
5,158-20
1.02R-15
1. 87F=16
£E.72%8-19
2.89%-19
5- -’5?"‘12
2,52%-15
2. 41E=-11
7.84F-18
1.72E~15
1.078-11
8, 18%-22
2,16E-14
1.10%=09
t.09E-10
3,20E-06
b, 87R-09
3, 12%-07
£.083E-13
5.888-08
8., 49R-07
t.132-09
2.23%-08

860, D
6. 87F=03
6.03%-18
1, 98E~1E
6. 12%-17
2,23%7=-13
3,30E=10
3.928-17
3.05E-15
u,56%-17
1., 137-12
?eOSF“g
L.oLom-1y
5.927=-18
2,729 18
1.08E-13
2.318-18
."c 69”"19
7, 86E-17
3, 28%7=23
5. 68%-28
1. 36E~-26
1. 30%-25
3.798-213
4, uBr-18
1. 19F-19
1. 06822
8. L2720
1. 66E=15
2, 15F=15§
gs 515-19
4,57E~-19
2. 07F-14
9,31F~12
o 1EF~15
3. 292"11
1. 308=-17
2.85E-15
1.69¥%-11
T. 369-21
3. 48E~14
1. 78E-09
1. 64810
3,52F-06
5.038~09
&,31E=-07
7.7%E=13
5.878=08
1. 12BE-08
1. 548=-09
3.03F=-08

™0 FEACTOP

770, D
1. 32F¥-02
9,07F-18
3.05F-1%
1- 52?‘ 20
1.21E-156
3.96E-13
5.72F-10
6. 22E-17
1. 38E"’ ‘Hl
61 863-’ 17
1.74P=12
1. 35E-18
7. 20F=- 14
9, 02E~-18
1.668-13
T UBE- 37
9,627~ 19
1. 338-18
4,947-23
B, 74p-24
2. 15F-26
5,708-23
6. B3E-18
1, 5uF- 10
1.687-22
1. 27F= 19
2.55F-15
2,77r-16
1. 51F- 18
6,718-19
3.12F=18
T, 03P=-11
6.63F~ 15
L, 2eP-11
1.98E-17
4,538-15
2. U7F-11
2.07E-21
5. 18E~ 14
2, 7T4E~-09
2.007-10
3, 758-0¢6
5.52E-09
5.62E=07
1. 06E=-12
5. B3E-08
1. 39E-06
2.018-09
3.91F=-08

80, T
2. 31E-02
t.28%-17
4,51F-15
2.33E~-20
2.158-1¢
6, 46F-13
gq 362— 10
9.52%=17
1.98E=10
8.70F=17
2.57F=-12
1.87%F-18
1.21%8-13
1. 29F-17
5,77E~1§
2,45%-13
2.26%=%7
1.238-1R
2.0LP=~16
6, 98F-23
1.29E-23
3,28%=26¢
2,078~ 25
8.06P=-23
10 D‘E‘ 17
1.90%=10
2.56E=-22
1. 798~ 19
3. 77TE-15
3.427-15
2.31r-18
9.31E~19
4, 81E- 18
2.12E-11
1.01%=-1¢
5.238-1%
2,80%-17
5.92%=18
3,438~ 11
2.37E-21%
T 27E-18
4,08F-09
3, U2~ 10
3.B9T-06
5.92E=09
T.03E-07
1.389-12
S5.83r-08
1. €8E=-0€
2. 518=09
L,85F=-08

Taste A4, Isotopic ConceNTRATIONS (G-ATOM/METRIC TON OF U) OfF BeTiIniDES AND THEIR DAUGHTERS £S A FuUNCTION OF
irrapiaTion Tive (Davs)
-= 3.3 0O/0 FNRICHED U

220, D
3.77TE=-02
1.737=17
6, 43%-15
3.485E~-20
3.568-16
9,918-13
1, 46809
t.L1%~ 16
2. ‘TOE‘ 1{3
1.318-18
3.66B=-12
1.99F- 18
1@ 95‘:- 13
1. 778~137
-ra —',QE-' 18
3.689E-13
3. 35%=17
1.47E-18
2.858-15
9, 42R”-23
1.84E=23
L.Bgr=26
2, 48w=25
1. 09%=-22
1. 6L%5=17
2.278-19
3: 80?‘ 22
2n 523" 19
5,388-1%
fi' GQE" ]5
3. 42%=-18
1.24%-18
5. 95E- 14
3.028-11
1.5CR- 14
6, 26¥%- 11
3. 89%~ 17
1.03%=-14
4,56%8-11
4.06E-21
9, 75%-14
5. 768~ (8
4.837-10
3. 96E=0E
6.28E-00
B.528-07
Te TUR=~ 12
5.82E=-CR
1. 957=-058
3. 058~09
5.817-08

1100. D
£.78F=-02
2.25E-17
B,89%-15
4,967-20
E.BUEF-16
1.457=-12
2,21F=09
2.038-158
3.558-14
1,70%~-15
5.07r-12
2,32r-18
3.087-13
2, 32F=17
1. 01E~-17
4.83r-13
L.B2R-17
1, 71E-18
U,07P~ 16
1.22F=-22
2.55F-23
T.028-26
Zn 895‘""2:
1.412-22
1.992-17
2q 61"?-19
5. 47822
3, 18%-1¢
7: ufiE"S
L.77F=-16
t,927~-18
1.59F- 18
7,73E-14
4,13F-11
2, 168- 18
7.29%=11%
E.12R=-17
1.488~ 18
5.B6%~11
5,35p-21
1.262~13
T.87F=-09
6.7€F-10
3.9‘73'06
6. 0T7F-09
1.018-06
Ze 157=12
S.80B~-08
2.22E-086
3.81E~-09
6.79%~08

501
Tapie A-U (CONTINLED)
FEFEPENCE PU® FQUILIBRTIUN FOTL CY¥CLE -~ 3.3 020 PURICHED ©

POYEP= 30.00MW, BURWUP= 33000,%4D, FLUX= 2.92% 13N /CH**2=GTC
¥UCITDF CONCENTPATTONS, ~TRA% ATOES
w93TS = M7 OF HFAVY MSTLL CH®7GED TO ®FACTOR

CE2PGF 110. D 220. D 330. D beg. D 5S4, D GED. D 770. D B30. D 990, D 1100, T

PA234 0.0 8.30F-13 13.33F-12 2.0%®-12 3.038-12 8,27E-%2 5. 7gT-12 7.50P-12 9.49F-12 1.178-11 1.U0F-11
1232 0,0 2,508-08 5.53E-08 G.7T4F-08 1.58F-07 2,42E-07 ~.58F-07 5,007-(7 T7,02F-07 9,38®B-0D7 1.,228-0%
U233 0.0 £.36E-06 1.12F-05 1,09¥-05 1, 76F-05 1.95%-0% 3. 07F-05 2.14F-05 2,15F-N5 2, 12®-05 2,06¥-05
U234 1.73% 00 1.05B 00 9.84F-01 L17P-01 B,53%-01 7,91%F-01 7,31E-01 6.7uF-01 £,29FE-04% S,€£8%-01 5,19F7-07
y23s 1,809 02 1.24%® 02 1.09F 02 9.61F 61 £.82% 01 7.35F 01 6,3BE 01 S5.50F 071 L, 71T 01 5,018 09 3,407 04
U236 .0 3,372 00 £.29% 00 &,88% 00 3.%11% 07 1.318 D1 1.48F 01 1,627 01 1.75F 01 1.85F O T1,93F D1
9237 0.0 5,042-03 1,27E-02 1.72E-02 2,15E-02 2.572-02 2.99F-N2 3.38¥-02 3.77E-02 4,13¥-02 U, 47P=02
¥238 4.06® 03 4,057 H3 G4,048F 03 4,088 03 L,03F O3 5,02% 53 L.O1F 03 4,00F 03 3.98% 03 3,97% 03 3,967 03
U239 0.0 1,78%=-03 1.,777-03 1.81E-03 1.8582-03 1.92%-03 1,997-33 2,077-03 2.%15F-03 2.24E-C3 Z.32F-03
uzan 0.0 1.22F-24 2,06%-31 1,58F-29 3.48F8-28 3,87%-27 2.p07-26 1.51F-25 5,897-2%5 2,36F-20 7.51E-2k
NP23¢E 0.0 §.118-10 1.23¥-09 2,407-09 3,94F-09 5.84P-D9 8.129-A9 1,07F-08 1, 37E-0R 1,69F-08 2,04F-0R
NP237 5.0 5.37TE-0G2 1.60F-01 3.072-01 &,BB8F-01 6,99%-01 g.132E-01 1.18F A0 1,8458F 90 1,72% 00 1,997 00
¥P238 0,0 1.7298-04 3.85F-04 7.55%-04 1,2LE-03 1,BUR-03 2. 55F-03 3,38¥-03 4, 30E-03 5,32P-03 6,L17-02
Np23¢ 0.0 2.56F-01 2.35F-01 2,60F-01 2.67%-01 2.76%-01 2, 8867-0% 2,98¥-01 3.09F-01 3.212-07% 3,337-01
Np2L0N 0,0 1.05E-36 1.77F-33 1,36E-31 3.00E-30 3.34%-29 5 L2E-28 1. 30F-27 5,60F-27 2,0u4F-26 65.LBF-26
HP249 0.0 6.33F-06 6&.33F-06 6.57E-06 6,96F=-06 7.LB6F-06 8, 067-06 &,72F-06 9,US5F-0f 1,02F-05 1,107=-0%
PU236 0.0 7.89F-09 4,55F-08 1.25F-07 2,607-07 L,63F=07 7.44F=-07 1.31F-08 1,57F-0§ 2,137-08 2,797-06
pyU238 0.0 1,86F-03 1.07F=02 2.998-02 $.,27E-02 %,12%-01 s.81E-01 2.71F-01 3.94%-0%1 5,19E-0% K,76E-01
_pU230 _ GLO £.73% 00 1.15F 0% 3.29% I1 1,73 01 1.89% OF 5,807 0% 2,07F G1  2,12% 01 2,158 01 - 2,17F OF
pg2il 0.0 3,69%=-01 t.,23% 00 2.3u4F 00 3,53% 00 4,.7%% 00 5.852F 00 6,828 00 7,69F 00 8,u42F 20 9.02F 00
PU2LA 0.0 J.61P~02 1.65F-0t UL,LBP-01 6,686%-0% 1,397 OO 1.98F 50  2.59F o0 3,207 N0 3,77F 00 L.297 0O
PL2L2 0.0 6.=7P-04 B.42F-03 3,55F-02 9,47®-02 1,97%-01 3.50F-01 5.56F-01 B,15F=-0% 1.%2% 03 1,0€F 0O
DU2L3 0.0 1,92F-07 2.45F=-06 1,06F-05 2,91F8-05 €,28%-05 3. 1BP-04  1,92F-06  2,0LP-0% &, 208-0¢ 5,71F-CL
U240 0.0 §,28E-28 1,0€F~-20 B, 14F=-19 1.79¥-17 2.00F-16 q, 84%-15 7,76¥F-15 3.35P-14 1,228-13 3,B7P-13
U245 0.0 9.03%-30 1,52F-26 1,19®-28 2,792-23 3,13F-22 2,35%-21 1.32F-20 5.92FE-20 2.25E-19 T U2P-19
Akt 0.0 9.30F-05 1, 1LE-02 U4.51E-03 1.312E=-02 Z,16E=02 1, B4F-02 5,37E-02 6,93E-02 B,71F-02 9.007=01
AM2u2% 0,0 8.31F-07 1.76F-0% 9.,267-05 2,78E-0Q4 §,0U7-0L 1, 0aF-03 1,70P-03 2,41P-93 3,16T-03 3,89F-03
AN20u2 0.0 2.172-07 2.66F-06 1.07E-05 2,75%=-05 5,507-00 9.35F-05 1.52FE-04 1,99F-0u  2,81%-04 3,2LF-0F
AM2U3 0.0 4,058-05 3.,737-0u4 2,39E-03 §,71%-03 2,32E-02 5, 07F-02 9,64FE-02 1.,65F-01 2,£IF-01 3I.88E-07
AM208 0.0 L,75%=10 1.23°7-08 B8.0uF-08 3,0%°-C7 B8,32F-07 1.89%-06 3,7LF-05 B6.698-06 1,10F-05 1, 70E-0%
AK2US 0.0 5,65%=-26 1,06F-24 7.93¥-23 i,728-27 1.89E-20 1.38F-19 7F.28F-19 3,12F-18 1.13%-17 3.55F-17
cHau? £.0 3,93%-06 9,237-05 5,37E-08 1,76FE-N3 4,22°-01 8,29F-03 1, 42F-02 2, 19F-02 3.927-02 u,17°-02
CH203 0N 3.07F-09 1.23P-07 1,25E-06 5.49P-D6 1.657-05 3.929-08 7, 877-05 1,39F-08 2, 26®-03  3,327-CU
cHMuu 0.0 3.45F-07 1.80F-05 4.77F-04 B,86T-04 3,05F-03 3. 28T-03 1.01P=02 3.89F-02 7.Q1E-02 1,2067W-0%
cHM2L5 0.0 2. EUP~CC 2.66F-07 3,83F-06 2,50%-05 1,06%-00 3, 38E-04 8,9%5F-04 2,05E-03 u,2%1E-03 7,69K-03
cH266 .0 2,158-11 &.40FP=-09 ©,77E-08 8.78¥=-07 4.817-06 1.937-05 6.21E-05 1.70R-0& u,127-0f 9,01P~001
£H2087 0.0 2.46°-1% 9,97E-12 3,338-10 G,05E-09 2.398-08 4,38F-07 5.28F-07 1.69F-0f L,68%-05 1. 16@=0F
c*®2L8 0,0 1.26F-146 1.08E=-13 5.328-%2 B.B2E-1% 7,90%-30 4.70F-09 2.22F-08 B8,40%8-08 2,72%-07 7,787-07
CM2U9 0.0 1,067=-27 8.73E-19 G.57E-17 7.81F-16 7.25%-15 4,58T-%4 2,217-13 B.71F-13 2, 947-12 e TRe-42
CM250 n,0 0.0 -,12¥-23 5,69®-21 1,337-19 1,58%-18 1, 23E-17 2, 167-1" 3.38P-16 3.31E-195 U4,4GF-15
BK2u9 0.0 1.6%7-10 2.56%-36 1.92%-1% 0, 18E-13 4, 58712 3.200=91 1.76F-10  7,55F-10 2,73E-0% 2,€1E-70
BK250 0.0 9,23F=-23 1,U7E-19 1.128-17 2.51E-16 2.877-15 5. 10E=-i4 1.19F-33 5,34F-13 2,01%-i2 6,60F-12
CP2L90 ¢.0 2,20E=-21 §.85F-18 1.067-15 2,92E-14 3,82%-13 3. 13P=-12 1,8%5%-11 A,58E-1%1 3,312-10 1,107-08
C¥250 0.0 k,09%-21 1.291E-17 3.278-15 3, UYBE-1k L, ,567-13 3,75F=-12  2,237=11 1.0%%-10 L,09P”-10 t1.37F-99
CT251 0.0 3.E0%=22 1.93F-1R 2,85%~186 O, TiE-15  1,48%2-92  1,39F-12 9, 13P-12 G, B4F=-%1 1,C8F=-10 6,90%-10
CF252 0.0 3.E1P-23 1.658-1¢ 3,72E-17  1,73F-15 3.Uu2%B~10  3,98E-13 3.12F-12 1.88T 11 9,11F=1%1 3,73F-10
CF253 5.0 6.0 9.6uF-23 2,79E-20 $.50FE-18 3, buP-37 L ULOFT-76 3,80F-15 2.47%~3&  1,29%-13 5.63E-13
CF25L 0.0 0,0 G.D 8.86T-2L §,29F-22 1,71F=20 2,55F-312 2,53F-18 1.857-17 1.07F-%F B,.11F-36
TE253 0.0 9.0 3.72F=23 1.408B-20 9.C%E-19 2,28¥-17 3,09F7-16 5.837-15 1.93%-1L  1,047-33 U, E9%-33
POTATS  4.20F 03 U4.99E 03 &.17%® 03 L, 16F 03 L.ILE (3 g.13° 63 &, 11® 03 4,107 03 b,09F 03 4.07F 03 5,067 03
FLOAL 2.58% 13 2.58F 13 2,63F 13 2.71F 13 2.81% 13 2.93F %3 3.05¢ 93 3, 18F 13 3,31¥ 13 3,u5F 13

g0l
POHER=

72

-y

72

73

73

L 7
74

75

" 754

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75
76

T8

76
= 76
774
A
17
77

78

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BONK

TeBLE A5

» 8 @ e #* ® a M & & & o

DODIOODOTITOIIDDITODOADDDIOODDODDNOADDOODDODIDTIDIOADIDIOIDODN

4 & ® & ¥ @ 4 @ B * & w T

.

& & @3 @& & ® ¥ & & ®w S 4 @« @ Q4 A =

DO QOOTIINOTITITITCUOT IO AOOSOORITOEIOIDADINDDDODODDOD

30,0CHW, BURNUP=

110. D
2.05%-03
1.06E~-07
3.208~-08
3,19p-06
5,68F~08
1.66E~05
4,.18E-09
50u3E'GS
23 ‘IOE"OQ
8a053‘10
B.B0B-08
T.15R=04
1;79'5."09
3.648-00
6:2“3“09
2. 118-07
8.17E-05
2:91R=06
216&3“05
3. BIE=-12
1.18%-03
2.419=-04
0.0
2.,L297-06
2,9EP-03
6. UTE~07
2,81%-07
R.02E-03
7.06¥=07
3.178-08
1.3298-02
3.278-0¢
BOROE’OS
t.638~-04
1.07¥%-08
1:102'06
3. 46F=-08
2.0868~-02
3»72E“11
1, %18=05
4,STE=02
6, QUE~-09
2,2TE=-06
6,02r=05
3.%1E=07
6.%1E~06
8.B5E=-05
6,838=05
7.51F=02
3.81E=-08
1. 81F=-07

Tive (oavs)

RFFERENCE PWR EQUILIBPIUM PUEL CYCLE -~ 3,3 070 ®NTICHED U

33000, ¥¥D, PLUX= 2,92F 13IN/CH**%2-SEC

220. b
n,258-03
1.408-07
4,23F-Q2
B.07E~-06
4,.940E=-08
3.37E~05%
RQSGE_OQ
1.16E-00
2.078-0%
T 9EE=10
B, 5GE-08
2.308-08
1.808~0¢
7. 36E"DL=
t.25%=08
8, 48R=07
E,23E-09
2.93E=08
2,B62E~0%
9! BBE- 12
2, 818-03
2.642-086
0.0
2.523‘36
£E.018-03
6.23F-07
2. 70F=07
1.58R-02
1. 41F-06
3:0“3‘08
2,78 E=02
3. 15E-09
8, 38%-08
8,30r~04
1:053”08
1.09%8-0¢
3.378~06
4,068=-02
7, 188-11
7. 45705
8.96E-02
1. 16808
L,39%-0f€
2.298=-04
3.538-07
6.28%-06
8.,018-05
1.83F7-01
3.57E=-06
13323'07

NUCLIDE CONCENTRATTONS, GPAM RTOMS

BASTS = MT OF HFAVY METAL CHARGED

330, D
£.567-03
1.67E=-07
5. 08E=-08
1.428=-05
5. 17E-08
5.38E-05
L,847R7-09
1.828-00
2,068-09
7892E'10
B, L5E-08
3,U5F-04
1.828-09
1.118-03
1091E‘08
1.938-06
8.311-09
2,96E-06
2.68%-0%
9,582~12
3.64%-03
2.46E=0¢
OQO
2,55%-06
90 '!BF'03
6.06%-07
2, 638~07
2,348-02
2,128-08
2,958-08
4,058-02
3.088-09
8.53%-08
1.29%~-03
1.098-08
3.32¥-08
€£.03r=-02
1. 0€R-10
1. 658-04
1.32%~01
1. 75E=-08
£,598~-06
5.07E-04
3. 288-07
5.828-06
7.387-058
5.70r-05
2.05e~-01
3uflGE'06
!-25?'07

uy0, D
8.95%8-02
1. 90807
5, 7TE~08
2. 13?"05
5.37E-C8
7.37E=0%
%.15E=09
2. 53E-D4
2.05E-09
7.89F=-10
8. u2r-08
L, 59E-0n
1.837-09
1.50E-C3
2, 61E-08
3. 47R-08
8.38F=-0%9
29985‘06
2n66E‘05
1.01E=-11
L, B8E=-03
2. 49%=-05
0.6
2.38E-06
1023E”02
5,92%=-07
2,57E=-07
3,08E-02
2,838-08
24873“08
5,338-02
2,99r-09
B,77R=-08
1. 67%=-03
1. 05%-08
1.09E-08
3.27E8=06
7097E‘02
1.412=10
2,927-08
1. 73E=-01
2.378-08B
8,93F-06
8,97p-04
3.00E-07
E.L3¥=-08
£. 85805
5.29%~-05
2,61%8-01
2,26%-0¢
1+208=07

550. D
1.18-02
2. 12807
£,02%-08
2,54P-05
5.557=-08
9.048-05
5, 39%-09
3¢28E°Du
2. 05%-06
7.86FE=10
8.,u40T-08
8.72E=00
1. 858=09
1¢B88E~03
3,38%-08
5.8507-08
8,45%=0¢
3,018-06
2, 69T-05
1.02%-11
£.13F~03
2a 523“’06

5& BOE‘”D‘,
2,51v=-07
3,80E~02
3.54F%-06
2,80F-08
€.58%-02
2.928-09
8,07FE-09
2,02F-03
1. 06E-08
1.10E8-06
3.23%-0%
9188?“02
1.77R=1)
4,.56F=-08
2. 13E-01
3. 04E~-09
1.1&?&05
1.40E=-03
2,78%=-07
5.09E-06
6, 388-05
4,932-05
3.12%=-01
3.138-06
1. 15E=-07

€60, D
1, 397=-02
2.318~-07
T.01r=-08
3.828-0%
50723‘08
1.16F=04
5. 82F=09
4,07E=-0b
2.0“E-O9
TaBUEF-10
&, 38R-08
6. B5F=-04
1, 86E=-0Y
2.27E~-03
4.212-08
B, 06%-06
B.52E~-09
3303E'06
2, 7T1F-05
1. 03F7-11
fii36w‘03
2,54%=05
0.0
2.63E-06
1. 89%-02
3, 69F-C7
2.87R=07
L,52F-02
fl426E°06
2.7uE-08
7.81F-02
Z.B*E-OQ
9,01F-08
2. 36E"03
1, 07E-08
1. 11E-06
3320?‘06
1. 18%-01
2.15%-10
5.595'Cfl
2.53F=-01
3, 7SE=-08
1. 41E-05
2.63r-03
2. 57p-07
b, 78r-06
5,98E=-90%
4, £0F=05
3.57E-01
3,9027-08
1.11E‘07

™0 RFACTOR

770. D
1. 65802
2.508-07
7. 58E-08
4,78%-05
5, BEE=-08
1, 38E-0QL
5.BUE-CS
4. 83E- 0L
2,0LE-39
78310
§. 3ER-08
T.97E=08
1. BBE=-(%
2.67E-03
5, 10F- 08
1, 128058
8,59~ 09
3105?”06
2( 73?"05
1. 0LE-11
8. B6CE-03
2.57E-D6
3.9
2. 66E-C6
2,228-02
5.598=-07
2. 42F=-07
5, 22E-02
4, 97E-086
2. 69E-08
9.01F-02
2,828-09
3, 78E-08
2,687=03
1. 09E~-08
1.138=-08
3. 17E=-06
1. 368-01
2,5%E~-17
9;92?“0&
2.918=-01
4.51E-08B
1. 70F~- 05
2.7%E-03
2. 39E-07
4, 88E-08
5.58E=05
4, 292-05%
3.98E-01
2., 91E-06
1,07E=07

BBO., D
1.919-02
2,68R-07
8. 1f1F-08
5.82F~05
6.03F-08
1.60E-0L
65.05E-09
5. Tir-04
2., 0UE=30
jaSEE—1Q
&.35E-08
2, 08F-04
1. 29F=-079
3. 0AP-~03
6, GB%=08
1, L9%-08
8.REF=0%
3.07E=0F
2. 7HE=05%
1.058=-11
3,83%-03
2. 59F-06
2.0
2, 68F=-06
2.56F%=-02
5.50F=-07
2. 38807
5.90E-02
5. 68E=06
2,5638-08
1. 028=C1
2.77E-09
1.02F=-07
2.98F=~03
1. 117=-08
1. 158-0¢
3,158-06
1, 5EE-01
2,95F- 10
1. 19E=-03
3,28P=-01
5.33»=-08
2,018-05
3,488¥-03
2. 21E=-07
L,23%7=05
5. 1BE~05
8, 00F-05
#,338~01
2.81%=-0%
1. 03E=07

Isotopic ConceENTRATIONS (G-ATOM/METRIC ToN OF 1) oF Fission PrODUCTS AS A FUNCTION OF {RRADIATION

990, T
2.17»=-02
2, 8um~07
8., 62708
5. 928-05
f. 18E-08
1.83%-04
6.258=09
6. E2E=-04
2.03=2-09
7.818-10
8, 3uR-08
1.028=03
10?03“09
3, 46®E~-03
7. 08r~-08
1. 92E-05
§.73%-09
3, 10p-058
2. T7E-D5
1,078~ 11
1, 1T1E-03
2. 62705
2.0
2,717~ 04
2.918-02
T, u1E=07
2,3%5E=-07
6. SBF'—DZ
8, 39R~08
2, 58¥-08
1.138-01
2.738-09
10 QEF"D“?
3,268~03
1. 12E=-08
1. 178=06
3, 12E8-06
1, 72E=-01
3, 36E-10
1 E1E~-03
3. 65801
6. 19B=08
2.33E=-05
§,708~02
2.O&F’07
3197E'Q6
#,83%=-0%
4,eur=0G1
2,72F-08
9, 918-08

11608, D
2.UuF-02
3.00%-07
8,118-08
8008E‘05
6, 327=-D8
2.07r-0L
£.44%-09
7.53E~00
2.03R-C%
7080?‘10
8.348%-08
1. 137~03
1uqu'G§
3.87%-03
A, $&F~08
2,428-05
8.79E-D9
3, 12%=0¢
2. 797058
1.08r-11
1, 23F=-02
2.6“?“06
0.0
2.73F-06
3:26E_02
5.,348-07
2-31E“07
T.2UFE-02
7, 09E=08

2 SUF=0E
13252-G1
2.69?'09
1010?‘07
3.527-03
1. 18%=08
1. 18E=-0¢6
3, 10E=-086
1.889-01
3,782-40C
1.887=-03
§,01E=01
7.09%-08
2.6TE=08
5.868-03
1.88?‘07
3. 74r-0¢
4,50R=08
3.47F-0%
2,912-01
2.637-0€6
9,587=08

L0L
FOWER=

90M

9%

¢
91
gz
92
92
92
G2
@3
83
92
93
93

Q3K

93
QL
9L
94

30.00M%,

s ® 4 4 B = &

B ® 8 & & & & & & & & 2 @ 3 s @ 4 & a

DOO0ODDCOLIODDIOOITDDDIDD IO ODODODIOID IO ODIITOODIIGODODOOOODIIDIODTOD

a & 4 B § & B » e A 4 B 8 » B g s 8 g B A s s e A

DO O0ODDIOODDODIOOCDTOTZIODDDOTTIDTIIIISTTIODIGDTITIOITIAOGOINODDN

110, D
i.uBF-O1
2.807-07
3.073-06
4.03R=-04
4, T1F-02
1- 3“3"01
2.16E-0¢6
2.829-01
5.78F-11%
5.87E=(%
1. 188-05
2.718-06
2,327=-04
3,98E-01
2.%19E-12
4.5%8-10
. 147=-06
7.35F-04
7.798-05
BIQTE-O1
b4, 09w-07
1.BOF-05
5.67F=05
3LUBE-03
3.21E=01
3.377-0%
1. 78E-05
7.99F~-01
1.458-19
20113'0&
2.938-03
7.2UF-07
2.10F-0%
4, 1aE-03
2. 13704
b,537=01
3.67E~-01
1. 22F-07
5.898-07
1.08%-03
1.608~03
8.50%-01
2.16E-08
7.223'07
6.21%=-05
L,7%8-03
9.13B-01
6036E-08
3.278-10
5.32%-0%
T 61207
9-09?-06

SURNUPE=

33000. MWD,

220. 1
2082?‘07
§.20¥-07
3.79¥-06
3.16F‘0u
9,02F-02
2.60E-01
2.00%-06
5.457-01
T.53F7=11
1.2CE=-05
4.B02-05
2.59¥-06
2,15%8=04
5.71E-D"
9.20E-12
3.85E-09
1-05?‘06
E.8487=-04
7.25E-08
9,6%E~-01
3.788-07
1.6fi?-05
8.03F=05
4,037=-01
83,87E-01
3.14F-06
1.66%-05
1.54%7 00
B.O0YE~T0
4,08F=-0L
1,17 E=-0Q2
&,T18E=-07
7.558=-06
3.908-~03
1.98%=04
5.U09%7-31
1.08F 00
1. 16707
5.55F‘07
1.02%-03
1.51E-03
1.66% 00
2.3TE~08B
5.88%~-07
5.917-05
4,527-03
1.79F 20
2.50F-07
2.59?'09
5.20%=09
1.55F=07
B. TLE~06

NOCLIDY COHCRETPRTIONS, GPAM ATONMS

RASTS = ®T OF HYAVY METRL CHARGED

330. D
L, 17E- 01
7.76E-07
3.59E-086
3.56%-08
1.308-01
3.8%E-01
1.888-08
7.98E-01
9.36F-11
1.828=-05
1.707-084
2.36%-08
2.037=-00
9.,77E-01
2.18%-11
1.35F-08
9.94%-07
6. LET=-008
§.,84F=-05
1. 408 0O
3.54F-07
1.572-05
7.558-05
3.97F-01
T.88R 00
2.988-0¢
1.563'05
2.23% DO
€.82E-10
5.93E-Ofi
2.60?‘@2
61“0?‘0?
7.1%8~-06
3-703‘03
1. 88E-08
5,538=-01
1.78% 00
1.112-07
5.318=-07
9,79%-00
1.408-03
2,847 00
2.318-08
£.838-07
5,7CE-05
B,36%-03
2.64%E 00
5.53F-07
B.€1r=-0Y
5.16E~-09
1.51E-07
8.498-06

TABLE A-5 (CONTINUED)
PEFFRENCE TWR FQUILIBRTUN FOEL CYCLE == 3.3 0/0 ENRTIERD U

tug, D
5.512-01
7-382’07
3.,41%2-05
3.38E-00
T.67F=01
4.96%-01
1. 78E-06
1.838 00
1.13E-10
2.L6F=-05
1.98BE-00
2.237-0%
1.928-04
1.277 0D
3,99%-11
3.318-08
9,u2%-¢7
6. 137=-04
£§.50E-05
1. €28 00
3,34%-07
1. L3E-05
1-‘52—05
3.80E-01
2.05¥% 00
2.81%=06
1.4G8E=-05
2,88F €0
9,758~-10
7. 08204
L.54%-02
6.117=07
8.89F~-0%
3.52¥~03
1.792-08
5.260=-01%
2,508 00
1.078=-07
5.11F=-07
9. 418=-08
1. 39%-03
3.18BE (O
2.26E’08
6-&3?—07
5.537-05
U.237-03
3. 46E 0D
9.67E-07
2,01E~-08
S.167=-09
1. 6BF=-07
8,29F7=-06

FLUX= 2,.92F 13N/Ck**2-SEC

SED. D
5,838-01
7.05?’07
3.25E-06
3.,23%-01
2.02%=01
6. 088=-01
1,697-05
1.25% @0
1.33?‘10
3.93%-05
3.138-00
2,11E-06
1.83Rr-04
1. 54F 0
£, 50F-11
5.71?’08
8,958-07
5.85E-04
6.20%-05
2.22% 60
3.168-07
T.418-05
6.80%-05
3.827-01
2.597 no
2.6B7=05
1. 82%=05
2,498 €0
1.28%-09
9-33?°0fi
%,978-02
5.857-07
6.52%-06
3.37?'03
1.717-048
5.15P=-01
3.19% 00
1.03%¥-07
.93F-07
9.09%-04
1.30F-03
3.81F 00
2.237=08
6425207
5.3387-05
4,1t7-03
4,257 00
1. h9%-06
3.883—08
5.19%-09
1, 45F-07
8,12F7=06

560. D
8. 13E-01
6,758-07
3, 128-06
3. W0F-04
2.35F-01
7. 158=01
T« 61P-06
1.47F 00
1. 55E-10
3.84F=05
4,56F=08
2. 01%~-0¢
1. 74F-00
1.87F CO
9,538=-11
1.20%-07
B8.53%-07
5.59E-0U
5.92F8-05
2. 607 DO
3.00E-07
Y. 34E=-CS
£,L8F-CS
3.4657-01
2117 20
2.56%-08
1,35FP-05
4,07 00
1.607=09
11093‘03
9.867-02
5.62Fr-07
6-25?*06
2,237-03
T BLE~DL
5. 95F-01
3.86F 00
1. CO0E~C7
a,778~g7
g.79F~00
1.30E-03
L,&69F 00
2.208+308
6,097-07
5.2L2-05%
1, 012=-02
5.02F 00
2. 10E-G6
6-62?‘08
5.23F-09
1. 028=-07
7.967=-06

TO PFACTOR

770. D
9, L3E-01
6.077-07
3.00F=-06
2.07P-01
2. 604F-01
B.10¥-21
fi.53F-96
1.68F &0
1 77E-130
bh.59%-05
6.30F-04
1. ¢3F=-06
1. €6E~-00
2.06E 00
$.23P-10
109?E'07
R, 1UE-07
5.35e-04
5.67E-058
2.87F 00
2.85F-07
1,28F~-(05
6. 48T-05
3.29P-0%
3.69F 00
2.U57-0%
1, 307-0%
2,62F QOO0
1.,937-09
1-2“2'03
1032?‘01
5.80F-07
6. 00E-05
3, 10F-03
1.58E-04
4, 15P- 01
4.%0F 00

176E‘08
4.627-07
B. 527~ 70
1.25F-03
5.298 00

.?SF*DS
5.957-07
5.12P-05
3, 91F~03
5.7BF 00
2,B2E~086
. D48~-07
5,282-03
1.00F-07
7. 82F-05%

BBO. D
1.C7F 00
5.21?‘07
2.887~06
2. 857-0L
2,927-01
9, 20B-01%
1, iSF~06
1.87% 00
2.01F~10
5.38F-0F
8.367-~01
1.819F7~0¢
. 39%-04
2.30F 00
1.987-10
3, 10707
T TEE~07
5.12E-04%
5.43F-05
3.327 0¢C
2171F‘07
?.227‘05
5.93F=25
3.138-0%
4,087 00
2.35F-0F
1.248-05
5. 147 00
2.277=09
1.38E-03
1. 697-01
5.20F-07
5.717P=-0¢
2|99E‘03
1.527-08
L,567P-01
S.12F 00
3,51E-08
4. 48F-07
8.26F-00
1.227-03
5.95% Q¢
2,1r?=-08
5.81%-07
5.00E-05
3.82F-03
6.51% 00
3,52%-08
1.33E-07
5.358-09
1.38E-0"
1-59?-06

950, n
1. 207 00
5.97E=-07
2.767=06
2,7ue-0u
3. 167-01
1. 022 Q0
1. 3IB8F=05
z2. 067 00
2426710
6. 21E-05
1.07%-03
1. T3E-05
1. 52F-04
2.5%3% 0O
2. &5F-10
L.6TE-07
7, 41R=-07
e 91F-04
5.212-05
3,65F £O
2.57%-07
T, 17R=-05
3, 83®=-05
2.998-04
i, 53% 00
2.28E-06
1.19%-05
5.63F7 Q0
2.63%-049
1.52%=-03
2. 11E-01
5.018=-07
5. 558~ 045
2.877=-33
1. L6%=-0U
4, 397-01
5.72F 00
9, 27R=-08
4, 3Rw-07
8.037-0UL
1. 18%-03
6.59F 00
2.15F-08
5.68%=-07
L, 39%~-05
3.742-03
T.22% 00
u,52F-06
2. 16E=07
5.U427-09
1.388-07
T.ETR-0F

1100. D
1. 33F 00C
£, 74F=-07
2.,587-08
2.64%-00
J.42E-01
1.177 0D
1.32E’06
2.247 00
2.53E-10
7.0€6E-0F
1.35E-013
1.84F-0€
T.U45F =010
2.752 0D
3.45E-10
€.59F=-07
T.087=-0"
u,7iE-QL
5.007-0%
3.97F 00
2.U5E-07
1., 127-05
5. 38%-0%
2.86F-01
U, 967 0C
?2.1¢7=0¢
1. 9LF7~-0%
6,107 00
3,007-09
1,657-03
2,58F-01
u,837~0"
R.36F~98
2.777-93
T.U1F~08
G,22F-0¢
f.297 D0
9,057-0¢
Le237~07
T.80F~-04
1. 152-03
7.227 DO
2.137-08
5.567=07
L,79F-D%
3.66F-032
7.99F 00
5.50F=0%
2,92F=07
£, L87-09
1.35%-07
T UEFP-0E

801
POWER=

®o 99
2 S9y
T¢C 99
B 39
NR100
HO10C
TC100
RO100
NB101
%0101
TC101
RU101
80102
TC1028
mC102
RE102
me103
TC103
2103
PH103%
FH103
MO108
TC1086
RU104
RE10UN
RH10L
ED10%
¥0105
TC105

* & &« & o @ =

C
0
0
o
0
0
0
0
0
0

. * @« & o 8 F & & & 8 @ e ® B a3 a

QOO OISO ITIOOTODC OO DDIADAOOODDIOORIDIGOIOS DA DD
-
SOOI OOCC OV DOOPAOODANDDDAIITIORODDAOIDIISITO DD

* & ® 8 4 % a & w & = s 8 8 & &

30.00¥W, BURNUP=

HAPGE

116. D
1.U28-00
9.20E-01
g.10®-08
4,83%-06
8,B5E=-05
5.268-01
6. 11E=01
1.212-01
1,B%E=-01
11912“05
4,202-01
3. 61R-06
7075E“0u
T.R1P~07
7,97E~03
7.568=06
5.638~-04
B8.7BE~01
7,70E-06
1.34E-05
5,328-05
B.56E-01
1. 96E-05
3.298-02
2.56%~-03
8.60E-01
4,237=-07
2.588-05
g, 37E=-01
2.42¥-08
L:n 59E_03
8, 92E~06
1. 01E=0L
9,728=-05
7051E-D}
E.50F=05%
1. 38E-05
2.48E8-07
6: 383-01
t,77E=-058
3.8RE~06
2. 183-01
2.188-08
2,586B=-01
%.288-06
5.85E-05
3.2%p-01
8.238-08
1.833‘67
1,06E=02
1.35E-06
2.738-07

TaglE &-5 (CONTINUED)
REFEPENCE PP EQUTLIBBIUN FUOEL CYCLE =-- 3.3 070 ERPICEED 3

33000, ¥¥D, PLUX= 2.92F 13W/CH**2-IEC

220. D
1.36F=0U
1.81F 00
8.86E=08
L,69F7=06
8.59%-05
€.812-01
7.97E-08
3.30E-01%
7,858-01%
1.86E~05
1.82E 00
SiQuE-OS
6.00F-03
7.68E-07
7, B80E-03
7.378=-06
5,53F-04
1.76F 00
7.62F=0€
1.52E=08
6, 098~06
1.71F 0¢
1.94E~-C5
3.268-02
Z,5U4E~-03
1.75% 06
1. 72E-08
2.58E=05
1.88% 00
t.Q2F-08
1. 918=02
£.96E«06
1.02E°0H
9, T7E=05
1.51F 00
£.718=-05
1.37E-05
2.58E=-07
1.31E 00
5.05E-06
H;U7E‘GG
2, 67E-01
2.67E=(04
6. SZE-01
L,87%8-06
£.78E-05
7021?‘01
2. 20®=057
4,B9E-07
6- 1“E-02
10693*06
3.80%F-07

WUCLTIDE CONCENTRATTONZ, GRAM ATOMS

BRSTS = MT OF RFAVY MRTAL CHARGED

33¢. b
1.33F=-04
2.68% 00
8, T0F-08
4,60R=-06
8,82%-05%
7.198-01
g,45F~-Du
3.77F=01
1.56E 00
1.82E=05
2,.7T1E GO
€,37E-06
1.908-02
7.608-07
7.76E~03
7;303‘06
5. L7P-04
2,63 0C
7.57E~08
14513‘05
§,72E~-06
2.58F 00
1.938~-05
3,25E-02
2.53E~03
2.62F 00
3,BO9%-06
2.598-05
2.8uF 00
7,552-08
8,36%-02
70 01E'05
1.03E~08
3,8BE-05
2.28% 00
6.888-05
1. L3R-05
2.861E-07
2,992 00
5.298=-06
L. 27205
2,888-01
2.88E~-04
1.12E 00
%,372-06
7.47E=-05
1.16% 00
31683‘0”
8919E-07
1-622’01
1.36E-06
3.95E~07

ueo, o
1.29E‘0u
3.54% 00
8, 59E~-08
4,53%-06
8028E-05
7.24E-01
g,512=-04
3.89F-M
2.39% GO
3,59F QB8
6,94r=0%
4, 128=-02
7. 54E=07
T.T0E=03
T 2Uw=-08
E.438-04
3.50F 40
7. 85E~08
1.51F-05
T.26F%=05
3,447 00
1. 93E-C5
3. 24802
2.528-03
3.45% 00
£.,91P2=-0¢
21 60F-05
3. 8% 06
1.0LE=-C7
7.89E-02
707206
1-OHE*0H
gaguF‘OS
3.05% 00
7.0U4r=(%
T, LBR-0F
2.8EE-07
2.73E €0
50 SOE‘OE
B, 40F8=08
3,03E-01
3.03E-04
1.58% 00
SOSOE-OE
8,06E=-05
1. 65F 00
5.218-07
1. 16E~06
3. 18E-1
2,20%-06
8,428-07

550, D
1.27%=-08
4,38% 00
B.50F-08
4,378=-056
8-17E‘05
7, 19%-01
&,468-008
3- 893-01
3,22% 00
1.77E=-05%
4,058 09
7.39%-06
7.388-02
7. 49807
T.E5F-03
7.20%-04
5.20R=-04
B, 367 00
7, 53%-08
1.51E=-05
7. 5E-06
4L,31% QQ
1.93%-05
3, 28E-02
2.52%=03
L,38®% 60
1.087-05
2161E“05
4,78% 00
1.34E-07
1.26E-01
7. 12R=06
1.QUE-GQ
1- GOE"O“
3,82% 00
7. 18E~-05
1, U78=-035
2,72E-07
3,48F 00
5.70E=086
4,B0E=-06
3. 16 E=01
3.15%-04
1.93% 0
£,.20%-06
B8.61E-05
2,.17¢ 00
£.78E-07
1.512-06
5. 20%=01
2,42%-086
u,B858-07

660. D
1. 24F=-08
5.218 OO
L,BiF=-06
8, 06E-05
7.12E-C1
8.37%-08
3, 86F-01
4.03F 00
1| ‘?53-05
5.318 00
7.80E-06
T UER=G7
7.51F~03
T.AEE-08
5.37F-04
5.2198 00
7,528-06
1. 5CE-05
8, 21E-06
5. 17% 00
1,838-05
3,24B-02
2.528-03
5. 20F 00
1. 55F=-05
2, 837-05
5.76F 00
1. 66E-07F
1. 850-01
7, 18E~06
1«053"03
1: 0 1E-Ou
1,608 0D
7, 329-05
1. 507=05
2.,77E=07
8,25% 00
5, B9F-06
4,758=086
3,278~04%
2.29E 00
5, 57E~-06
9, 13E-05
2.72F 00
8.37E-07
1.B6E-06
7.80E~01
2. 62R-06
5.2¢8-07

™0 PFRCTOP

70, b
1.228-04
6. 03E 0O
8,378-08
uo37F‘06
7,97F=-05
7. 0UF=-01
8.28F~01
3.82F-01
4,82F 00
1. 73F=05
6, 167 00
8. 19F-05
1, P3E-01
7, 827=07
7.58E=-013
7, 13E~-06
5.38%-08
€, 08F OO
7.51E~08
1.50R-0F
8, BUE=-06
6. 04F 00
1.938-85
3, 2u4B-02
2,828-03
6.C4% 00
2; 10“'05
2. 68F=05
&, 74F 00
2.01E=07
2.57E-01
7. 23E-06
1. 06E-04
1. 02F-04
5.37F 00
7, 85F-05
1. SZE-DS
2. B2F=07
5.0u® 00
£. 07E-06
4,90F~06
3. 39E-01
3.38F=-04
2.82F 00
6- 922-06
9.61?‘05
3.37F 00
9,97E=-07
2.22e-06
1.0%F 00O
2. 818-06
5| 6“F"07

8ed, D
1.2C0E-04
6.43E 00
8, 32%-08
4,33P-06
7. 89E-05
6.97TF-01
8. 19F-00L
3. 78E=-01
5,%9F 00
1. 71E-05
7,008 0D
B.S8E-06
2, U3R-01
7339?‘07
T.S5R-03
7:102“&6
5.33F-08
6,91F% GC
7;51?‘06
1. 50F=08
9, 050-086
6,927 00
1. 93F-05
3. 24F~02
2.538-03
6.86% 00
2. 73E-05
2.56E-05
7.73F 00
2.38F-07
3,43%-01
7.2%E-086
1.078=-08
1. C3E-OL
6,157 GO
_F.. 592-05
1. 35808
2.87TE=-07
5.857 OO
F. 24706
5.0“3“06
3,49E-01
3.39?—0&
2.91E 00
7.26E-06
3,92% DO
t.16F8-06
2.57F-06
1.46% 0GC
2.99%=06
6900E”07

990. D
T.63F Q0
B, 277=08
4, 29F=-06
7-81?'65
6. 30%-01
8. 11204
30 7&“5‘@1
6,387 06
1, 70E-05
7. 84F 00
2,96E=-06
3. 20E=01
T.378-07
7.52E8-03
7.08E~06
5.312-04
7,758 00
7.21%=08
t. 50808
9, ULr=-06
T.T%E G0
T.93E~05
3.2%E-02
2.538-13
.67 0D
3, 88%-085
2 ETR=05
B, 73% €0
2.788-07
b, b4r=-0%
7. 34%~06
1.08%=04
1, fiR-0U
6, 928 00
7. 718=05
1. 588=05
2,92%=07
£E.E8% QO
6551?“05
3.60E-01
3. E0E=-04
3I,17E G0
fiISSE-QG
T,05%=04
4,57% @G0
1. 31E-06
2.928-06
t.88% 00
3, 16F=08
6,308=07

1100, D
1.17E-08
2,428 00
802“?‘08
bh,257=-06¢
7.7UFE=0F
6.83¥-01
2.03r-Cu
3.707-01
7.07% ¢
1. 68E=-0%
B.66% OO
§,32E=0¢
t, 14F=-01
7.38E-07
7.507-03
7.067-06
5., 30E-04
B.58E 0
7: ‘31?'06
t.508-05
9,810=086
. 677 00
1.238-05
3.25%-02
2.548-03
2. BEF DO
4,237-05
24) ‘SBF"‘OS
9,728 08
3,198-07
5. 60%-01
T.L0E=06
1.09E=-04
1.05%=04
T.69F 00
7.83%=05
1,80E=05
2,878=-07
7.53E 00
6-57E’06
5.39F_06
3.89E=-01
3.6%E~-0L
3,407 00
7.887=-06
11108-0u
5.248% 00
1. UEE~DE
3.25F-06
2.38F 00
3.32P~06
£,67R=07

601
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110, D
5. uSE-OQ
1.54E-06
3.338-03
1.L0R-01
8.10E-07
1.00E-01
2,00E~05
2.66%~07
5. LuBP-02
2,55%=-08
1.86E-05
8.218-08
65.548=-02
8,29E-10
2,298-06
1.04E-07
3.56E-02
9,928=-17
1.33B-12
1.36%=-07
4.63E-10
2.24%8-014
1.857=-37
1.778-02
U, F9e=16
9,18%-09
8.13%8-03
3.2ZE-05
8.32R=-09
B,923-04
106:-1’::-06
1.378-06
7.89E-08
6.84E-04
3.938-11%
L,708~-03
6.338-05
6.59?‘06
2,83E-03
6.91E-08
S5.92E-09
1.,4179-05
1.33P-06
1.59%=-03
6.068-09
S-VSE-OB
2.008-09
5.79E=03
7,097=-17
2.70E-15
5,4UF=-11
te 56E"08

229. D
6.80E-0L
1.92E-06
u01?E’03
3.328-01
1.11E-08
2. 39E‘01
2. 49E-05
L, 40%€-07
1.53%-01
5.18E8-06
2. 73E-05
9,07E~08
1.818-01%
B, 30°-09
3.57E=-06
2.25EF=07
1. 0BF-~-01
5.26F-1¢
1. 36211
2.178-07
1. 4%F=-09
3.,52E-04
2.98E~-07
5.38%-02
9.09%-15
1.39E-08
2| 36?‘02
1.77E-00
2.53r-08
S5.32E-03
1.72%-06
1.518-06
T, 09E~-07
9.53F-Ct
1.87E-10
1. 31‘E-02
5.95%=-0°8
9,.06T-06
T.42F-03
7.48T-08
6. U?E-Og
1.53E-05
6' 66‘5"06
1.82E-93
5,7TuR=08
6, 84F=-08
2,37E-09
T.4%7-02
1. 067-09
3.19E=-14
1,25E-09
1.827-08

TasLE &-5 (CONTINUED)

PPFEREINCE PWR TQUYLIERPICM FUPL CYCLFE -- 3.3 0/ TRRICHED U
30.00M%, BUFNUP= 33000.M¥D, FLUX= 2,92F 1IN /CHEA2-5RC

NUCLIDFT CONCEWTRATIONS,

BASTS

230. D
7.90E~-04
2.23p-06
U.82F-03
5.62E~01
1.358-06
3.97E-01
2.94F-05
6.27E-07
2. 993-0?
£.49F-06
3.40%-95
1. 14E=-07
3.36E-01
1.208-08
U,61E-06
2.902-07
2.09%=-01%
1.“‘6E"15
5,582-11
2.81E-07
2.788-09
4,78E-04
3,94F-07
1.02F-01
SUHAE-1%
1.767-08
4,497-02
B, 7Lp-0L
t,B8F~038
1,5L¥-02
1.82%-0¢%
2.357-05%
1-3“?‘{}7
io‘tflF-Og
5,52F-10
2.L1E-02
7.258-05
1. 1 1‘9'05
1,30E8-02
T.97E-08
5.83E-09
‘5063?-{15
1.778-0%
1.927-03
2.20E-07
2.68%=09
2,3€E-02
5, 13E-09
1.40F-13
3.18E-09
2,038-08

= MT OF

4ug,., D
8.B8E=-0U
2.U9¥-06
5, 35F-03
8.2%2-01
Y. 57E=-086
5.B3E=-01
8.21E-07
4,93F7-01
T.62E-06
3,99F-05
1.34E-07
5.23¥-01
2, 47F-08
5.50E-06
3.46E-07
3.38P-01
3.10E=-15
1.55%-10
2.377=07
4.578-09
5.83F-04
4,BQE-D]Y
1. 578=01
1. 9-7?.-13
2. 09“'08
7.0BE-02
9.37E-08
7.7BE-0B
3. 28E-02
1.93F~-06
2.7LE-06
1.55E-07
f. 26F-03
1.217=09¢
3.72%7~-02
§.39E-05
1,287-05
2.05E-02
8. 3%E-08
7.19E-09
1. 71E-05
3.638-05
1.97E-03
5.78E~-07
8. 51E-08
2.857%-09
32, 387-02
1. 573-08
4,10®B-193
3,15E-08
2,22E-08

HFAVY METAL

550. D
9,72%-034
2.74E=-05
5.837-03
1. 1%% 0D
1.768-06

Te358-01

3.808-05
1.02%-0%
7.372-01
B.HUT-0F
4,538-05
‘:.527_"07
7.36E-01
4,328-08
6.307=08
3,97R-07
'4- 782"01
5.63F-15
3.47E=-10
3,87B-07
€,79%~-09
5.82E=-00
5.62%=-07
2.198%-01%
5.UBE-13
2.38%-05
1.01%=-01
1,57%2-03
1.9128-07
5.908-02
2.05P-048
3, 09%-06
1, 75%=-07
1. 53F-03
2.268-09
5,227-02
9,42%-05
1, 44%-05
2.86%-02
8.7TF-0K
7.528-09
71 79‘.""05
6. 41E-05
2.00%-03
1.23F7=-06
9,217=-03
3.20E=-09
L, UTR-02
3.76%-08
9,51%=13
o, 067~-08
2.39%-08

GPAM ATCHS
CHARGED

660. D
1. 06F-03
2.977-06
6.25F-03
1. 43% 00
1. 93R-06
8.98E-01
L, 24E-05
1.217-06
1. 03E 00
9,89E-06
5.02F-05
1.707=-07
9,78E-01
6, 84=-08B

7- 0&?'06

4.43F-07
6.517-01
9,29%F=-15
§.78E=10
4,337-07
9,462-09

7- 80?‘0;4

6, L27-07
2,827-01%
1.28%7=12
2,658-08
1. 35E-01
2.38F-03
1.51%=-07
9,558-02
2,177=06
3.,018-06
1. G4E-07
1. 70E-03
3.817=-09
F.918-02
1. 04E-04
1. S8E-05
3, 77E=02
9, 14E-09
7.8438-09
1.87F-05
1., 03E-00
2,007=03
2.298-06
9,377-08
3. 43F-09
5.63E-02
7.71E-08
1. 91F-12
2.178-07
2.5%¢-08

T0 PFACTOR

770. D
1. 138-013
3.187-06
6.647-03
1. 738 00
2.10E=-06
1. 0EF 00
u,68F-05
1.812-06
1.3BF 00
1. 08P=-05
5.59E-05
1. 86F-07
1.247 00
1. 01E-07
7.75%-06
4. 88E-07
8,20E-01
1.03E-12
1.20E-09
4,777=07
1.26E-08
£, 77F-0%
7.228-07
3.U9F-07
2. 65F-12
2.91F-C8
1 * 72?'0‘3
3.34%-03
1.94E-0"7
1.L37=-01
2.307-06
3.72F-06
2. 11E-37
1. B5F-03
5.95F-09
8,77E-02
1.137-04
1. 72P-08
uo VBE-O2
9, LeF=-08
8.13F-08
1. 94E-05
1.55F-00
2. 00E-03
3., B9F-06%
. 05%8-07
3,647-09
6.8Lr-02
1. 42%=07
3,47F-12
b, 55%-07
2,70%-08

g80. D
1.202-03
2.397-06
£.997-03
2.08% 00
2.25F-06
1.22F 00
5. {4n-05
1.60FE=-0¢€
.77F 00
1.13F-05
5.9LF-05
2. 021:'"07
1.53% 00
1. 49E-07
Bo ’-‘2?-06
5.30F=07
1. 018 00
2.,08¥-10
1.98F-09
S. 19F-07
1.63F-038
9. 7'4‘3-03
B.027-07
4,158-01
5.02P-12
3.16E-08
2,13%-01
4,47F-03
2.41E-07
2. 04F-01
2,B3%-0¢8
L,01E=-0%
2,28F-07
2.00E-03
8.827-09
1. 082-01
1., 21F-08
1.85E-05%
5. 877-02
9.827-08
B.41E-00
2,01F-065
2,22F-04
1.992-03
6.1uF-05
T 11E-07
3,85E-09
B.10E-C2Z
2. 42F-07
5.85P-12
8.71==-07
2., B4m-08

990G. D
1,27E-03
3,.597-06
7.2%E-03
2. 43% 00
2, 417=-06
1. 38% 00
5. 80E-05
1., 788-06
2.22% 00
1.227=-05
£.378-05
2. 17E-27
7.83F 00
1.90E-37
9,05%-06
5.70%-07
1.22% 00
2.92E-14
3.10E-09
5.59%-07
2.0u%-08
7, 078-03
£.838=-07
u,827=-01
&, 888-12
3.369-08
2,579-01
5.,738-03
2.918=-07
2.78E-01
2. 577-0%
L, 297-05
2- L‘J’UPE"O',I
< ALER=N3
. 25F-08
. 30%-01
. 308-04
t, 878=-05
. O?F'O—"
. 69F-109
. 07E-05
. O"E"Du
. 978E-03
. 21%-06
. 17E-07
. 058~ 09
. 02%W=-02
. 88E-07
. 30%-12
1.558-06
2.98=-08

2
1
3
1
4
-
1
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2
3
3
9
1
4
9
3

1100. D
1.347E=-03
3.77E-05%
7.60R-Q3
2.80F 00
2.56F-0¢
1.53F 00
6.06F-05
1.978-08
2.71e 00
1.29%=-0°¢
€,778-0%
2.322-07
2.16F 0O
2, LAF=-07
9-65?‘06
6.08%-07
1. 48% 00
3.97P-14
G.pU7=-00
5.96%-07
2.51E-08
1.377-03
9.6UF-0%Y
5,.07P-01
1.487=-11%
3.61F7=-08
3.0u4F-01
7.138-03
3.8uP-0"
3.667-01
2.70F~06
b,557-06
2.60%-07
2.277-03
$.72F-C8
1,537-01
.37=-0u
2.09E-07%
8.327-02
1,047-07
8.,95E2-09
2‘ 135‘-05
b, 13p-10
1.95%-03
1.,327-05
1.22F-07
4,237-09
1.08?-01
R, 93F=-07
TLH1E-11
2.60F7-06
3. 11E-08

oLt
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DODODODIDOD DT ODTA GBS OO IO O

30,00¥W, BURNUP=

110. D
1.94%=-09
2.99E=-07
6§.41E=-0C
6.277=05
5.27E=0¢6
1.588-03
9.22E-05
L,86E-0R
1. 95E=-03
1.89E-07
2,.178-10
2.L1E-01b
2. 26B-08
5.%118-10
2,8BE=06
2,38E=-06
8,25%=-07
3.53E-08
2,628-03
1.CG1E-C&
8.70%=11
1.71%¥=09
2.02?‘63
2,95%=08
1.06%»=07
3.83r=-07
2.298-0%
L,E9P-08
2.165-03
2.29E-08
5,128-10
8.802-09
2,308-03
8,90E~-08
7.88E-08
2.19E=-10
£, R1E=-10
4.208-05
2.558-03
3.373—09
2.763-03
1. 2LE= 10
1. 19F-0¢
1.06E=05
1.63E-08
5,568-10
1-33E‘07
2.04E-03
9.858-04
6., 36E=-10
1. 578-09
2,408-09

TreLE A-5 (coNTINUED)

REFPRENCE PWR EQUILTRPIUM FUFL CYCLF -- 3.3 0/0 ENRICH®D U

33000. ¥WD, FLUX= 2,92F 13N/CH**2-3%C

220. 1
2.26F=09
3. 49807
8,92E=-05
734205
6.183-66
3.20E-03
2. 10E=Gu
557&5’08
4,32¥%-03
3.84F~07
b, 41E=-10
©.91F-0u
2.60%=08
1. 13E-02
3.041T=06
207QE‘06
4,%0B=-07
1. TLE=G7
L. U46E-03
1. 16 R=0§
1. 90 E~13
1.978-09
4, 48F-03
3.378-08
?1252-07
L,49F-07
2.62F~09
5, 07E=0¢
4,78%~03
2.59¥%-08
8,92F-10
9.94F=-08
5.01E~-013
1. 00E=07
8.87=~-08
2.18F~10
2.91E~09
33723-65
5.5E5E=03
3.80E-09
5.96E~03
2.70E~-1C
2-59E'06
6038&*05
1.86E=-08
6.25E-10
1.50¥%~07
3&S3E’03
3.0BE-03
4.B2E-09
1.418-08
2.T£R-09

NUCLTID® CONCENTPATIONS, GRAM ATOMS

BASYS = H#T OF HEAVY

330, D
2.538-09
3.,90E~07
1.05%-04
8,258-05
6.54E~-06
L,7¢m-03
3.UE6T~-00
€.37E-08
7.038-03
5.75E’07
£.50%-10
2.253-03
2-893* 8
1.8388-09
3.78E=06
3. 0LE-06
B.ULE-COT
,28E-07
7.20E-03
1.29E-C%
1. 18R=-13
2.19E~-09%
7028E-03
3.727~-08
1.388=-07
4.66E-07
2.898-09
1.308-33
7066E“03
2.8LF=08
7. FBE~10
1.09E-08
8. 05803
?aDQE-Oj
8,697-08
2.22F- 10
7.00E-09
5.15E~05
B.BE€F-03
g, 138-09
3,51F-03
4,30%E=-10
b,215=06
1.53P=-08
2.04E-08
6., B5¥9-10
106ug‘07
b, E8P-03
5.967-03
1.5UF=08
5122?'98
3,08F=-09

bao, b
2.76E-09
4,26F-07
1. 18%=04
9.05%=05
7.61E=06
6.0118-03
L, 97R-0U
6|93E“08
1. 008-02
7-58‘5"0“T
8.71%=10
4.00m=-03
3.?33'08
2, 762~09
L, 115=-05
3,31E-06
5691F-07
B.G9E=-07
1.03E~02
1.408=-0€

27E-13
2, 3BE-0¢C
1.08E~-02
b,02¥-08
T.49E-07
5, 362-07
3, 13%=-(3
1.658~05
1.09%-02
3,06%-08
8¢!BF“10
t. 178=-08
1. 14E-02
1.178=-07
1.0LR=07
2,298~ 10
1. 338-08
5,52F-05
1. 20F%=02
y,04%m=09
1. I4E=02
€. 33k~ 10
€. 08806
2,%0F-08
2.207=08
7.39¥-10
1.778-07
5. 50E-03
9., 438-03
3,53%~-08
1o 3LE-07
3.30%-09

55G. D
2.97E=09
4,58E-07
1.29%-04
9. 80%=05
8,24%=-0¢6
7.13E’03
6.62% =00
7.43%-08
1.328-1n2
9.388~07
1.07F7-09
£.23%=03
3, 36%=08
3478E-09
H.H1E-05

» SLE-0%
6.337-07
1.33E-06
1.36%-02
t,50E-08
1.602%-13
2,.55%-09
1.378-02
&,308-08
1.598-07
5.738-07
3.34%-03
1.97R=0%
1. 83E=02
3.26F-08
B.68%-10
1, 258~08
1.48F=02
1.25%=-07
1. 11R=-07
2.368=10
2.,20%-08
5.882-05%
1|62E'02
4,72%-09
1, 75%=02
8.56?‘16
8,21E=-086
&,B81%-04
2.35%E-08
7898~ 10
1.90%-07
6., 18E=03
1,33%-02
€.73E=-08
2;833‘67
30533“09

MBTLL CHARGED

660, D
3, 17E-09
b4,8ar-0"
1. 40F-04
1.05E8-08
8. 8L4E=-06
8.,087-03
B, 41E=-04
70912*38
1.67F=02
1. 10E-06
1. 288=09
8.918-03
3.57E~-08
L,9€E~-09
L.69E-08
3.77F=-08
F.748=-07
2.00F=08
1. 718=02
1. B5E-0€
1,578-13
2071E-09
1, T3r-02
L. 56E-(8
1. 69P-07
€. 07E=-07
3.547=-09
2, 25E-05
1. 80E-02
3, uu=-08
9. 178~ 10
1, 32E=08
1.877-02
1. 32E-07
1. 172-07
2. 45P-19
3.378~08
6.18E"05
2.01%=-02
k. 97E=0Q
2.188-02
1. 118-0¢
1. 0EE~05
7.328-04
2.49%-08
8.378=-10
2.01E-07
6. 75F-03
1.768~-02
1. 13E-07
5.287=-07
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BUFNOP=

TrsE A5 {CONTINULED)

REFERENCE PHP PQUILIBRIOM PUFL CYCLE -« 3.3 0/0 ENPICEED U

33000. HED, FTIO0X= 2.92F 13W/CH**2-SEC

220, D
8,36%-03
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FUCLTDE CONCEWTPATTIONS, GPAM ATOMS
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1,35%-02 1.99pP-02 2,%1%-02 3, 15E-02
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FIFERERCE PWR EQUILIBRIOM FUYL CYCLE -~ 3.3 O/0 ENRICHED U

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KOCLTDE CONCPNTPATTONS, GPIM ATOMS

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330. b
2.14F 00
2.19E—05
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2,978-0%
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3.318-0t
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770. D
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2.208-05
3. 32F-04
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4.058-086
1,182 01
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2,.998-06
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9,608-07
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BUPNOP=

RPTTIRENCE PR EQUILIBRTUX FUFL CYCLE

33000. ¥¥D, FLUX=

220. D
1.26%-08
1.71E-07
8.01E-05
T.05F-0L

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4,65%=05
3.73%-03
1.56E-09
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5.078-01
7.257-03
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1.227-03
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2.927-086
1,238-01
3.07E-07
£.19E=-05
3.,838-05
1.39%-06

TapiE A-5 (CONTINUED)

-- 3.3 0/0 EWPTCHRED O

2,927 13W/CH#K2-SEC

NUCIYDF CONCENTPATIONS,

BASTS

330. D
1,25%-08
1.68R=07
7.87E-08
£.937-0C0
2.58E 00
7.66E-0%
9.617-03
1.54E-09
7.718-08
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9,90F-05
1.LCF-02
1.368%2-01%
2.10F 00
4.L9R=07
1.60F 06
6.832-05
9,298-01
1. LBE-05
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1,6LE 00
5.,45%-05
9,38%-05
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3.30E-08
3.65¥-0%
4,978=-02
6,017-0"7
7.55F-02
1.53E-06
4,57%-06
7.608-01
©.528-03
£.39E-C3
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3.467-0%
1,77F-01
71,912-03
3.95E-C2
3.238-01
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6.,31F-01
8.,99E-06
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1.408=-01
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1. 247-08
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1. 397-048
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7.56E-08
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2.7LE 00
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1.87% 00
7.997=-0F
1.54F% 00
1. UE%-05
1, 767-03
2.15% 00
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90 231:"05
1.84F7 00
3.25F-06
3.628-05
b,98E-02
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1, 20%=-01
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1. 0% 00
1.10F-02
5.33%-02
2, 54E-01
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1. 79F-02
3,507-03
8, 138-02
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3. 48E-05
£,97%=-01
4, 35%=06
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1.71P-01
2.%17=04
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6.LUE=-07
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1.828-04
1, 597=-0E

550. D
1. 235‘0”
1.687-07
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5.”57*0u
4,207 00
1, 838-01
3.05%8-02
1.5L18-09
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1.128-06
9,58%-05
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T, 34R-01
3,333 00
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2.07F 00
8.82R-05
2.28% €0
1. 43%=-05
1.717-03
2,647 00
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2.31F 00
3.23%-05%
3,58%-03
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1. 667=-01
1.637=-06
b, 5% F=05
1.277 00
1. 19F-02
7.01%=-03
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3.60E8-06
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3.81E-06
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9.,59m-08
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1.98%-01
2.927-04
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3, 42%=-01
7.79E-07
2.62%-04
2,867-04
1.67%-06

GPAM ATOKS
= MT N7 SEAVY M®=TAL CHARGED

660, D
1. 22%-08
1.62E-07
7.588-05
6.587=01
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1, 79E-04
4. 6CE-02
1. 54E~09
7.337=-08
1. 31E-08
9,u5E-05
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1.328-01
3.836% 00
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2.23% 00
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3.06E €0
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1, 69F~03
3.19% 00
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9. 0up-08
2.80% 00
3, 21%-08
3.56F-05
4,931-02
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2,227-01
3.237-08
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T0 FPFACTOR

770. D
1.22F-08
1,€07-07
T.518-05
6, 81F-04
5.R7% 00
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1. 32702
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9. 818-05
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1.677-03
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3.837-058
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7.80B-03
6.697-01
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9, 72E-013
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1.745F 00
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1.55F-09
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1.3182-02
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7. 487 00
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4,56%-06
2.27% 0D
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5.127-08
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9,04F-02
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5.06% 00
3.,93F-07
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2,587 13

Temie A-5 {CoNTINUED)
PE?EBENCE‘PWR PQUILIBRTUM FUTL CYCLE == 3.3 D070 ENRICHED T

33000. MWD, FLUX= 2,92F 13K /CH%*2-SEC

22¢,
1. 758=03
8.083'02
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L,268-07
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£, 258-09
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2,55%-06
1.237=-07
5.,92F 01

2,58F 13

NOCLIDE CONCENTRETIONS, GRAM ATONS

BASTS = MT OF REAVY METAL CHAPGED

330. ©
2.37E~-D3
1,888« 01
2,08E=-06
4.76F=-07
5. 18r=02
2.26E-032
2,68E~-04
2«873‘06
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9.258-0%
3,258-0%
4.35F-03
3,95E-02
1.95%8-08
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1. 027=-08
8&59?’0&
6'18E—05
6.E1E-05
€. 00®-09
1.E1E=05
2.608-04
8.11E=-G9
5.835E-09
0.0
1!73?‘0“
1.29%=09
€.58F=-08
1.07E8=-04
1.62F-07
2.92E-G5
1.758-10

b, 517-09

EI 1&3—05
1. 25F=-07
2.388-08
£.£E6%-08
5,87%-0¢
4,10%8-07
B.ggr 01

2,538 13

Lup, o
3,02¥-03
2.21&‘01
5.03F=06
. 1BE=07
7.39?'02
#, 2BE-02
6.60B-04
3025?‘06
Y. 24E-0UL
3.70E=05
50823’03
E.63B-02
Z.24E~-08
Bv 09?’@5
1. 25708
9.56%-07
2. 01:‘:"02
1. 96E=-07
1.247=0%
2&97E“03
1,22¥-08
t, 36F-03
1, 208-048
1. 83F-04
7. 15F=09
1.9%2¢=-08
3:91E'0u
. T58~(9
7.038~09
0.0
1.53E-09
7. 96F=08
1. 93F=-00
1. 95"1‘"’07
2. 27805
2, 86%-10
8, 19E~0%
L,398-Q5
1.52E=07
€, U3¥-08
1. 10F=0%
9.883-07
T.18% 02

2,718 13

550,
3, 71E=03
3.10E=01
9.82%=-06
SQSTE'07
9 ? -’BE—O?_
7.05%m-02
1.33P-063
3.618-06
1,22%-02
1.63%-04
fl.OQE*OS
7. 698-03
1. 02801
2+51P-08
4,587-05
1. 38701
1, 087-06
2.825-52
2,23%-07
1.827-05
£,137-03
1, 39%-08
1!95E'03
1.85F%=04
2,8%7-04
B.20E~09
2.2018-05
5.33E°03
1. 12E~08
8! 10‘5’”09
0.0
4.019=04
1. 75 E=09
9. 2uE-08
3, 08E=04
2,24R-07
8, 48%-05
4, 39710
1.378=-08
TaB81E=08%
1.77E~-07
1, BUE-B37
1.598-037
1.E8%=-05
2.022=-086
1.88% @2

2,818 13

6€0, D
4.L17=03
L.088-01
T« REE-D5
chu?‘07
1. 237-01
1. 06P-01
2. 38E-03
3. BUE~-DE
1.60%-02
2. N9R-04
b,87v-05
1.01R=-02
1, 49F-01
20 75E-08
5.03F7-0¢
1. 49E-00
$.207=08
3.74E-02
2, 472=07
1.608-05
5, 3%%-G3
1. 55R=(8
2.627=013
2. 6LE-G
k.B2E-0U
9. 178=-09
2, 4e8-05
6. 632"0“
1, 26208
2, 10E=-05
0.0
5. 35E-0L
1.858~-09
‘uOQE'O?
4, 85p-00
2, 52807
!a 27 E"Ou
ELLEE-10
2, 12E=-08
1. 31g=-010
20003’07
2.86%8-07
2. B0R-07
3.04F-05
3.732~06
1.78% 02

2,938 13

TO PEACTOR

770. b
5.13E-03
2.56?'05
t. 50F=01
1.49F-01
3.80r-03
H.ZSF-OG
2.08F=-02
2. 60704
L, 82P-05
1, 31902
2., 10E-01
2.99R-08
5. USR=05
11603‘0“
1.328-0¢€
b, JEE-D2
2, 70E-07
1.788~05
6. TUE-0]
1. 718=-08
3.35E-013
3. 55R=-04
7. 3€F-04
1. 01F-08
2; 112‘05
B, B3F~0L
1. 397-08
1.00F=-08
0.0
6. 77E-04
20 1uF‘09
1. 15807
69 ’OE-Ou
2.78F~07
1&798‘0&
9. 158~ 19
3.13E~08
2, 08E-C8
2,228-07
5. 258=07
3. 578-07
4,752-05
6| HBE-OG
2,078 02

3,057 13

880, D
50 852"03
6.23E=01
3-67E‘05
6.62F=07
1. 79E=-01
1. 983"'61
5.,728=03
4, 56R-06
2,588=02
3. 248%8=-00
S5« 16F=05
1.678=02
2,89E=-01
J.218-G8
8. BER-05
1. T2R-08
1.22F~0¢€
5,83%-02
2,92p=-07
1.96E=08
8-16?“03
1. 85E~-G8
L,Y6E=-03
b, 50®-0L
1i05fi'03
1. 10E-08
2, 958-05
1. 01003
1. 51E=08
1.09E=-0R
§.¢
8, 26E-04
20333_09
11265‘07
8, 00r-01
3.038=-007
2, 4z28=-04
1. 26F=00
4,41P-08
300fi3‘0u
2.438=-07
2. 038=-07
S 22E=07
7. 22F-05
1' 083-(‘5
2,378 02

3.18% 13

990. D
6. 578-03
T.35E=-01
5.028=05
6. GLF-07
2:09E-01
2.53%-01
8. tap-3
L, 8E%=-0F
3. 16%=02
3.9812-04
Z. 48705
2. 10E-C2
3.89?'&?
3. 42908
B, 25R-05
1.35E°Gfl

« 53806
T, HR-02
3,138-07
2. 18705
9. 63E=-023
1.998=-08
5, 022-03
5. TBE-0L
1. HuE°O3
1, 187=08
3. 17%=05
t.20m=-023
1. 637-08
1. 18808
0.0
9-832‘0“
2.50E=09
1e 36R=07
1. 01R=03
3.267=07
3. 16%=04
1.678-GS
5. 898-08
4, BOF--OU
2. EUT=07
t.4RE-06
Te 2TE~(7
1, 078=05u
1. 74B=45
2.67% 92

3.31% 13

1100, D
qong-O3
B.UEE=-O1
6.58E-05
7-2“?'07
2.40%-01
3.13r-01
1.117-32
5-1“3-06
3.758-02
b, 62R=00
5.78P~06
2.609-02
5e12B=-01%
3. 6z2F-08
6.61E~05
1.897=-00
1- 62?‘06
§,51r-02
3.33r-07
2.327=-0%
1. 118-02
5,958~03
7. 08F-04
1.89E=(G3
1.26F=-08
3,3BE-0F%
1., 4802~-03
1.7&2—08
1, 26E~-08
0.0
1.15F=03
2.66%=-09
1. 467=07
1.25F~03
3, LBR-G7
3,995-03
2. ¥7P-09
T.B8T=08
6. 0%9F=0u4
2.83E-07
2.327-06
1.0“?-06
1.567=-00
2,718=0%
2,96% G2

3.85% 13

Gil
TagLE A6, Stvmary TABLE oF isotopic ActiviTies (Ci/METRIC TON OF U) oF CLADDING AND STRUCTURAL MATERIALS AS A

NLCLIDES WHOSE CONTRIBUTION TO THE SPECIFIC ACTIVITY OF THE FUEL S LESS THAN 0,001 Ci/meTrIC TON OF U AT A

ELNCTION OF POSTIRRADIATION TiveE (DAYS)

POSTIRRADIATION TIME OF 150 DAYS ARE EXCLUDED.

PEFEPTNCY PW¥R EQUILTBRIUM FUEL CYCLE -- FUEL LRCAY TTRES
POWER= 30,00MW, BURNOP= 33000.M¥D, FLUX= 2.92F 13 /CHA¥2-SEC
NUCLIDE RADIOACTIVITY, CURIES
BASTS = MT OF HEAYY MFTAL CHARGEL TO REACTOR
CHAPGE DISCHARGE 30, D 9¢, D 160. D 365. D
car 45 0.0 3.17F-02 2.79E-02 2.17F-02 1.62E-02 §,838-03
sc 86 0.0 5.26F 00 3,338 00 2.03E 00 1,14% 00 2,09%-01
CR 5% 2.0 2.95F 04 1.39E 04 3,127 03 S.45F 02 3,29% 00
My 5o 0,0 2,698 02 2,32F 02 2.02F 02 1.72F 02 1,087 02
PR 55 0.0 2.00F 03 1,95 03 1.87F 03 1.78% 03 1,53F 03
2 59 0.0 2,28E 02 1.U3E 02 5,69% 01 1.94% 0% 8,247-01
co 58 0.0 9,327 03 6.96F 03 3.89% 03 1,972 03 2,68E G2
co 60 0.0 6.04% 03 6.37F 03 6.23% 03 6.08% 03 5,64F 03
NT 59 0.0 3,852 00 3.8EF 00 3.B5F 0C 3.85F 00 3.8%% 00
¥T 63 0.0¢ 5.652 02 S5.65F 02 5.6u4F 02 5,.63E 02 5.61E 02
SrR 89 0.0 1,812 01 2.56F 01 1,15F 01 4,52% 00 2.94%-01
¥ 9% 0.0 1,01 02 7.108 ©1 3.50% 01 1.,53F 01 1.37F 00
zr 93 0,0 1.038=-01 1.03F=-01 1.03F-01 1.03®-071 1.03E-0%
ZR 95 0.9 2,898 04 2,10E 04 1.1%%F 0d 5,25E 03 S5.90F 02
HB 93 0.0 8.32F-03 8.79%~03 9,72E-03 1,08E-02 1,39E-02
¥8 95 0.0 2,80F 04 2.62F 04 1,79% 04 9,742 03 1,23F O3
20 23 0.0 2.008=02 2.00E-02 2.002-02 2,008-02 2,0CF-02
TC 99 0.0 1. 40E~02 1.40¥-02 1.407-02 1.407-02 1,40F-02
syit7m 0.0 1.21F 04 2.74% 03 1.40F 02 4,397 00 1.72F-0L
SN119M 0.0 2,81F 01 2.21F 01 1.87F 01 1,5urF €1 8,7LF 00
sSN129M 0.0 3.37P-01%1 3,237%-01 3.37E-0% 3,36F-01 3.3U4F-01
S¥123 0.0 B,47F=01 3,78%-01 2. 71E-01 1,BLE-01 5,90E=-02
sp12it 0.0 L.73F 00 3.35% 00 1.87F 00 Y.LSE-01 6.98E~-02
Set25 0.0 4,47E 01 4,38F 0% 4.20% 01 4.00E 0% 3,L6F 01
TFr125K 0.0 1.62F 01 1.65F 01 1.66% 01 1.62% 03 1.43% 01
gupToT 0.0 1,96% 05 B, 03F 04 4,52F 0L 2,627 Qu 1,00F 0%
TOTRELS 0.0 1.52F 05 8.03% Ou u4.52F 0L 2,62F 04 1.00% 04

3653. D
6.87%-09
3.35%=-13
0.0
5.87®%-02
1.3%F% 02
8.39%7-23
3.53F=-12
1.727% 03
3.85% 00
5. 24% 02
2.737-20
1. 03-5'—01
3.51F-13
5.318-02
T, u6T-13
2.00%=-02
1.40E=-02
t.0
9- 62E'0u
3.08%-01
-’l 1UE- 10
2,2u%=-18
3,437 00
1. 827 00
2,807 03

2.L0F 03

oLl
TeeLe A7, Sumary TARLE oF IsoTopic AcTiviTies (Ci/MeTric Ton oF U) oF ACTINIDES AND THEIR DAUGHTERS AS A FUNCTION

RUCLIDES WHOSE CONTRIBUTION TO TME SPECIFIC ACTIVITY OF THE FUEL IS LESS THAN 0,001 Ci/MeTRic Ton oF U AT A

oF PoSTIRRADIATION TIME (DAYS)

POSTIRRADIATION TIME OF 150 DAYS ARE EXCLUDED,

REFERENCE PWR EQUILTIBRIUM FUEL CYCLE --

POWPR=

PB212
Br212
PO212
PO2Y6
RY¥220
RAZ22Y4
TH228
TH231
TH23tk
P1233
Pr234HM
5232
0234
0235
U236
8237
0238
NP237
NP239
PU23€
Py23R
p1u239
PU240
PU241
PU242
AMZ241
AM2L2H
AM242
AM243
cHM242
cHM2a13
cHzZiag
cyzas
CHr2ué
BK249
SUBTOY

TOTALS

30.00n%,

CHERGE

e & & 4 =

a ® g = 4 & »

3% 00

ha NODOOAOOOODUCDOOTIIPOWOO I aTOTOIDIOOID

038 00

BURKRUDP=

33000. MWD, PLUX= 2,92F 13N/CH*%2+35EC

FUEL CECRY TINES

NOCLIDE RADIQACTIVITY, CUPIRS

BASTS =

DISCHARGE
1,50%=-013
1.50E-03
1.50%~03
1,508-03
1.508~-03
1. 498~-03
7.93E-01
3. 18E=01
3. 28F-01
3421E"01
£.07E~03
71 51F-01
1;713‘02
2.BBE-D1
8.65% 05
3.18E-01
3,338-01
1.85% 07
3.50E"01
2,72F 03
1,18E.02
4,778 02
t.05E 05
1. 388 0O
8,59F 01
9.16F 00
€.34F 08
1.81% 01
3.34F Ou
3.71E 00
2.,54F 03
30“1E"’01
6. 84F=-02
3:58E‘03
1. 96% 07

3.91% 07

MT OF BEAVY

3. D
1.618-03
1.61E~-03
1. 03E"'03
1,618-03
1.61E-03
1.638-03
1. 71&‘02
3.14%8-01%
3, 31801
3, 1P~ 01
6, 36%=-03
7. 52¥=01
1.718=-02
2.88BE~-01
3.978 0Ot
31 1BE"01
3. 80”=-01
2, 708 €3
3.448=01
2.77E 03
3,238 @2
4,778 2
1.08% 05
1. 388 QO
9.97F 01
9.16F 00
9. 16E 00
1. 82E 01
2.96F Ob
3,70 00
2,48 .03
3.01E-01
6., 84E=02
3,36E-03
1.B3E 05

1.B3F 05

S0. D
1, 908E~03
10 903’03
1. 21E-03
1- 90E"03
1. 90F~03
1: 9013’03
1. 928-03
1. 71E=-02
3.14F=01
3.38BF-01%
3| 1“3‘01
6. 8B8E~-03
1, 71F~02
2.88E-01
8,E63F 01
3,1U4F=-01
3. 40F-01
1.82% Q1
3.31E-01
2,80F 03
3.238 82
4.77E 02
1. 04E Q5
1,388 00
1.278 02
9. 138 00
9, ¥5E 00
1.82% 61
2,297 04
3.69E 00
2,427 03
3. 81E=-01
6. 8UF~-02
2! 9“E‘03
1.33F 0S5

1,33F 05

160. D
2. 29‘&“03
2,298=-03
1. 6E~-03
2,298=-03
2¢ 29E“"G3
2,298-03
2- 2"3-03
1. 7T1E=-Q2
3,1uB-0C1
JLU0F=-01
3. 14E-01
TLUBE-03
7‘ SSE'G“
1. 71E-Q2
208 SE-G?
2. 54F €0
3, t4E=-01
3.40E~-0%
1.82%8 01
3. 16E=-01
2,82% 03
3,238 02
4.77E 02
1.03F 05
1. 388 (0
1. 598 02
9,148 00
9. 147 00
1,82E 01
1.78F 04
3.68E 00
2,40 03
3. 41E~01
£.84%-02
2,32E-03
1,268 05

1.26F 05

METAL CHIZGED TO RFICTOR

365, D
3. EOE-03
3.808-03
2, 17E-03
3,40¥~-03
3.80P-03
31 L‘QE-03
3.38¥=03
1. 71E~02
3. 1UE-01
3, 808~-01
3, 14E-01
S, 0TE-03
T S59F-01
1. 71E-02
2.8BF-01
2.41F 00
3. A‘uE'OT
3. 408-01
1.82F 01
2t 75E"01
2.86E 03
3,237 02
u, 77 02
1,008 @5
1. 3BE GO
2,507 Q2
9,12% 00
9.12F 00
1,828 01
7.12F 03
3.63F 00
2,357 03
3.41E-01
€. 88E=02
1. 60F-03
1. 18E 05

1. 14 05

3653. 1D
1. 60F-02
1.60E-02
1. 02%=02
1. 60%=-02
1.608-02
1. 60F-02
1, 71e=02
3. 1LE=-C%
3.4837=-01
3. 148=-01
1, T4E-02
8. 308~-01
1. T1E-02
2: 88}"‘0‘
1.57% 00
3n 1uE—O1
3, 43F=01
1.82% Q1
3.68®9=02
2.70F 03
3.23% 02
2,79% {2
£.53% 04
1. 388 00
1.41%7 03
8, 7% {0
B.75% §0
1. 82 01
7. 182 00
2. 99F% 00
1.67% 03
3. 817-01
6.83%=-02
7.20% 0

7. 20" 0

L1
Tapie A-8,  Stvmary Tasle oF Isovoric THERMAL Power (W/METRIC Tom OF U) OF ACTINIDES AND Tre1R DAUGHTERS AS A FUNCTION

NUCLIDES WHOSE CONTRIBUTION 7O THE SPECIFIC POWER OF THE FLEL iS LESS THAN 0,001 WveTRIC Ton OF U AT A POSTIRRADIATION

TivME OF 150 DAYS ARE EXCLUDED,

REFERENCE PWR EOUILIBRIUM FUFL CYCLE -- FUTL TECAY TTEES
POWER= 30.00%¥, BURNUP= 33000.MWD, FLUX= 2.92F 138 /CH**2~-SEC
NUCLIDE THERMAL POWER, WRATTS

B1SYS = HT OF HPLYY METRL CHARGED TO PEACTOR

CEAPGE DISTHARGE 30. D 90. D 160. D 365, D

Pa23Ly 0. C 1.65¥-0% 1,628-03 1, 62E-03 1.628-03 1,628-03
9238 4.71E-02 2.16¥~-02 2.16E=-02 2.177-02 2.17E-02 2.19E-902
0236 0.0 7.81F-03 7,81E-03 7,.81E-03 7.81E-03 7,812-03
0237 0.0 S.74F D2 2.64% 01 5,737~02 1.68E-03 1.609-03
U238 8.15F-03 7.95B-03 7.9%E-03 7,95E-C3 7.95E=03 7.958-03
¥p237 0.0 9.178=-03 9,98¥F-03 9.998-03 9,99E-03 9,99%~-03
w2239 0.0 2,51 OU 3,65E 00 2,U46F-02 2,B6E-02 2,46E-02
PU236 0.C 1.22F-02 1.20E-02 1.15F=02 1.108-02 9,58%"-03
PU238 0.0 9.02F 01 9.17% 0% 9,27F 01 9.35% 03 9.472 O
PU239 0.0 9.89F 00 1,00% 0% 1,00F D1 1.00% 0% 1.00E O
PU2U0 0.0 1. 489F 01 1.49F §1 1.89F 0% 1,498 (1 1,497 01
pu2u7 0.0 4,36F 00 4. 34F 0D 4,31 00 4.27% 00 4, 186F 00
pU242 0.0 4.07E-02 4,07E-02 4,07F~-02 4,07E-02 4,07F-02
an2e1 0.0 2.878 00 3.33F 00 #,28EF 0C 5.30F 00 8.33F 00
Am242K 0,0 2,617=03 2. 618-03 2,60F-03 2.608-03 2.60E-03
am2u2 0.0 8,467 01 1,22E~02 1.22¥-02 1.22E-02 1.22F-02
A®2433 0.0 6.62F-01 6, 63E~01 6,.63%=01 6.63E~01 6,563F~01
cH242 0.0 1.23F 03 1.00F 03 B,45%F 02 6,278 02 2.62F 02
cH243 0.0 1.36F=01 1,36F-01 1,36F=01 1.35F-01 1.33E-01
c¥2u4 0.0 3.55F 01 8.52F 0% B.47F 01 B.H1E 01 8,23F 01
cw285 0.0 1.078~02 1,07E=-02 t.078-02 1.,07E-02 1,07E-02
cw286 0.0 2,20%=03 2,24F-03 2.287-03 2.24%-03 2,2UF-03
SUBTO™ 5.52F-02 2.72F 04 1,33% 03 1.08E 03 8,407 02 4, 78F ©2
POTALS 5,.728-02 T.46E O4% 1,33F 03 1,06F 03 B.40F 02 a.787% 02

oF PosTirRraADIATION TIvE (DAYS)

3652, D
1. 62E-013
2. 39E‘02
7.82%-03
1.04%7-03
T.95E-03
1.018-02
2 115"‘1-02
1.078-03
8.,9u® 03
1.00% 01
1. 49% 01
2. 71 00
4,07F-02
g, 71E 01
2. ugE-03
1, 17E-02
6.63F-01
2.65%-01
1. 10%-01
5.837% 01
1. 07E‘02
2.20%8-03
2,267 02

2,247 €2

8Ll
TapLe A-S, Suwiary TapLe ofF Isotoric AcTiviTies (Ci/meTRIC ToN oF U) oF Fission PRODUCTS AS A FUNCTION OF

NUCLIDES WHOSE CONTRIBUTION TO THE SPECIFIC ACTIVITY OF THE fuEL 1S LEsS THan 0,001 CismeTric Ton oF U AT

PosTirraDIATION TiMe {Davs)

A POSTIRRADIATION TIME OF 150 DAYS ARE EXCLUDED.

PFFEPENCT® PWR FQUILTIBRTIUY FUEI CYCLE ==~ FUFL TECAY TIHES
POWEF= 30,.00MW, BURNUP= 33000.MwD, FLUX= 2.92F 13N/CU**2-SEC
KUCLIDE RADIOACTIVITY, CUPIES
BASTS = NMT QF HEAVY METAL CHRERGED ™0 REACTOR
CHARGE DISCHAFRGE . p %0, D 160. D 385. ©
B 3 0.0 T.09F 02 T.08E 02 6,99F 02 6,91F 02 6. 70®” 02
SE 79 0,0 3,98%-C1 3,98F-01 3,98F=-01 3,98E~-01 3,98%-01
kK2 85 0,0 1,13 {8 1,13 08 1, 11F 04 1,10 04 1, 06F 04
RB B 0.0 4.93F 02 1,628 02 1,767 01 1,318 00 6.57E-00
Sk 89 0.0 7.18E 05 60,81F 45 2,16F 05 B.S51% (4 5,538 03
SR 0 0.0 7.76E 04 7,75E O4 7,72E D4 7,68% O4 7,59R 04
Yy 90 0.0 B.07% O4 7,758 08 7,.72F O 7,68% Q4 7,58F 04
Y 9% 0.0 9.38BF 05 €,63E 05 3.27% 05 1.43F 05 1.28F {8
Z®» 93 0.0 1.89F 00 1,89F 00 t,89F 00 1,89% 00 1.89F 00
¥B 934 0,0 1. 45F-01 1,528-01 1,66F=-01 1,83F=~C1 2.3tE=-D1
Zk 95 0.0 1.378 06 9,97F 05 5.26F D5 2,49% (5 2,80F 0Ok
¥B 954 0,0 2.B80® 08 2,112 O 1,.12F O4 5,29F (03 5.94F 02
¥B-95 0.0 1387 06 1.28% 06 8.72¢° 05 B,73F 05 5,957 04
TC 99 0.0 T.U37 01 1.83% 01 1.U43F 01 1.83% 01 1.83F 01
RU103 0.0 t.22E 06 7,.21F 05 2,52% 0S5 7,417 04 2,0SE 03
PH103® 0,0 1.22% 06 7,228 05 2,52 0S5 T7,.41E 04 2,05E 03
RU106 0.0 5.457 05 5,1EE 05 4.59F 05 4,03E 05 2,73 0S5
RH10€ 0.0 7.80% 05 5.1FE 05 4,598 05 4,03® 05 2,73E 05
2n1¢7 0.0 1.10E~-01 1.10E-01 1, 10F=-01 1,108=-01 1, 10F=-01
AG110n 0.0 3,68% 03 3,3%F 03 2.88% 03 2.37%8 03 1.35% Q3
AG110 0.0 1.597 0% 4,41 02 3.74% 02 3,098 C2 {,76F% 02
AGt1Y 0,0 3.96E 04 2.48F 03 9.70F 00 1,50%~-02 B.B9®~11
CD113% 0,0 1. 058 01 1,058 0% 1,088 01 1.03F 01 9.99% 00
IR1144 0,0 1.55E €0 1.02F 00 4,85E-01 1,69E~-01 9.Bu®»-03
IR 0,0 2,217 00 9,87P~01 4, 30F-01 1.63R-01 9,U49E-03
cp115m 0,0 5.51 €2 3,40% 02 1,29F 02 4,18 0t 1,53F OO
ERY17® 0.0 5.96E 01 1,358 01 6.92F-01 2,168~-02 8,US5E-~-07
sSEi19M 0.0 1.68% 01 1.518 01 1.28F 0%t 1.05E 01 5,.96F 00
S¥123 0.0 8.88F (03 7.528 03 5.398 03 3.66% 03 t.17F 03
TP123% 0,0 6.108-01 5, 118-01 3.58F~-01 2.36F~-01 7.02B-02
sg128 0,0 4,068 €2 2,878 02 t.487 02 6.39% 41 5,99% 00
sW12%5 0.0 1. 35E 06 1, H8BF 03 1,777 01 1.02E-01 2,77E-08
58125 0.0 8.70® 03 B8,6u4F 03 B, 29E 03 7.89E 03 6.83% 013
TE125M 0.9 3,118 03 3,20" 03 3.25E CG3 3,198 03 2.,83% 013
sS¥i126 0,90 5., 66F~01 S, 46E~01 5.06P~-01 5,06E-01 S5.46E-01
SB126% 0.0 2,25% 01 S.U6F-01 5. L46%-0% 5, 06FE-C1 5,406E-01
Te1278 0.0 1.54® C4 1,32E O4 9,.C0F 03 5,77F 03 t.57F 013
TE127 0.0 7.20F 04 1,338 O8 B,%0F 03 5,70® 03 1.55F 03
TEt29% 0.0 5.73F 04 3.13E ¢t 9,208 03 2,21 03 3,38% 01
TF129 0.0 3,378 05 2.00% 04 5,907 03 1,828 03 2,177 Ot
1129 ©.0 3,718~02 3,73B-02 3, T4F-02 3,74E-02 3, TUE-02
13t 0.0 B.61E 05 6,71 0L 3,83F 02 9,23E-01 1,99FE-08
X?1314 0.0 6.39E 03 2,56F 03 1.03% 02 1.78% 00 1.07E-05
X®133 0.0 t.61F 06 3,B3F OB 1,837 0% 1,44¥-023 2,80%-15

3653. D
L. 03 02
3. 98R-01
5. 96F 03
0.0
5. 157~ 16
6. 07% Ot
6.,07% 04
1.897-13
1. 89F 00
B8, 40F-01
1.67E=11
3.54F-13
3.61E- 11
1. 43F 01
2,098=-22
2,08E=-22
5.50% 02
5.,50F 02
1, 10F=-01
1. 66F=-01
2. 16E-02
0.0
6. U0F 00
1.58%-22
1. 533"‘22
1. 4B¥E-213
0.0
6.56E-04
1. 42705
1' 92?' 16
0.0
6.78% 02
2.81% 02
5.86%8-01
5. 35?-01
5| H1E-01
1. 30E-06
1. 292-06
0-0
.0
3. 7&E-02
0,0
0.0
0.0

6l1
PEFEPENCE PHR EQUILIBRIUX FTUFL CYCLE -~ FUEL

POATR=

C5134
£8135
€S136
£sS137
B21374
BA1LD
LA180
CE141
PRIL3
CE1UY
PPita
¥b187
PEILT
PM1L8H
PHI14E
sm151
Eg152
GD153
EU154
EU155
BEU156
TB160
SUBTOT

)

O OO0 CVROCRLOO0O0O0OOIoSO E

" % ¢ & 8 & & B & 8 8 8« e & =

SO OO OO C DD ODD DO
- - a - - - . .

<

SURNDP=

TasLe A-9 (ConTINUED)

330060, MWD, PLUY= 2.92%F

¥UCIIDE PATDIORCTIVITY, CURIES

BASTS =

! DISCHARGE

2,48F 95
2.86E~01
5.08E 04
1. 08F 08
1,01% €5
1, U5E 06
1.50F 06
1.39F 0%
1,208 06
1.112 06
1.12E 06
5. 887 05
1. 02E €5
3.88F 04
1.99F 05
1.25E 03
1.25% 01
3.55% 01
£.99F% 03
7.48% 03
2.26E 05
1.28% 03
2, 10% 07

1.38EF 08

30. D
2., 40" 05
2.86F-01
1.23E 0Ot
1. C8E 05
1. 01F 0%
2.E86% 05
3.30F G5
7. 38R 05
2.94F 05
1. 038 06
1. C3F 06
9. 04 Qu
1. C6E 05
2.37F 04
6. 06F 03
1.25F 03
1.25E 0%
3,28 O
6.97E {3
T.2%E 03
5.66E OO
9,618 02
1. (B8 07

1. 088 07

90. D
2.27E 05
5.0%E 02
1. 078 05
1.00E 05
1. 117 04
1.282 Ot
2, 04F 05
1. 412 Ot
8.92F 05
8.93% 05
2,137 03
1.02F €S
8.80F €3

7.09F 02

1.25F 03
14287 01
2,75% 01
6.92F% 03
6.81F 013
3.547 03
5. 407 02
5. 19F 06

§. 19F 06

160. D
2.12F G5
2,86%-01
1. 20" 0%
1.072 0%
9,98E Cu
2.5%F 02
2.89% 02
4,56F 0Ou
4,098 02
T.52% 05
7.52E 05
2,708 O
9.73E 04
2,77F 03
2.237 02
1.25% Q3
1.22F C1
2.25E M
6.86% 03
6.33F 03
1.39% 02
2.78E 02
L,19% 06

L.,19F 05

LFCRY TTMES

T30 /CHR¥2-3EC

MT OF HERVY METAL CHAPGED TO TRFACTAR

365. b
1, 76% 05
2,86E-01
2.168-04
1. 08% 05
9,857 J4
3. 797=03
L,36E-03
5.678 02
1.297=02
L.56F 05
4,56F 05
-"c 39!‘.‘-05
8.39E 04
9,407 01
7.55E GO
1. 207 03
1. 1E7 01
1.25% 01
6,698 023
5. 11F 03
1. 0‘72"02
3. 848 01
2,22% 06

2,22% 06

3653, 1
8.38% 03
2.86E-01%
0.0

&.56F 0OU
8.00E 04

2,57F-22
2.07E=-23
1. 168 03
7.08% 00
1,.02%~03
L, 53% 03
1. 63F 02
0.0

7.21E-13
3. 18E 05

3.8 05

0cl
Tapte A-10, Therval Power (W/METRIC Ton oF ) oF Fission Probuct ELements As A Function oF Postirrapiation Tive (pavs)

PEFTRRENC® PH® FQUILIBRT UM FUEL CYCLE -- FUERL TFPCAY TIMES

POWEP= 30.00M¥, BURNUP= 33000.M¥D, PLUX= 2,92F 13N/CH**2-5EC
ELEMENT THFFMAL FOWER, WATTS
BASTS = MT OF EFAVY METAL CHRRGED TO REACTOR
CH2RGE DISCHARGE 10. D 30. D 60. D 90. D 120, D 160. D 270. D 36%. D 1096. D 3653. D
H 0.0 2,52F=02 2.52¥-02 2,517-02 2.50F=02 2,59F-02 2,47E-02 2,46P-02 2,628-02 2,38¥-02 2,13F-02 1.43%-02
ZN 0.0 2.70E-02 7.55P-04 5,89%-07 1.29F-11 2.Rt¥-15 §,12F-21 3,74E-27 3,03E-U48 5,27®-59 0.0 0.0
GA 0.0 1,91 01 1.75F-02 1.37F-05 2.997-10 6,.52%-15 1,82E-19 B8,67F-26 7T,04E-43 1,22¥-57 0.0 G.0
GE 0.0 3,81 01 3.57F-0F 5,837-19 3,B5E-38 2,54w-57 0.0 0.0 0,0 0.0 .0 0.0
AS 0.0 4,487 02 5.09F-02 9.35%-06 2.35%-11 £,88%-17 1, uBF-22 5,038-30 1.47P-50 0.0 0.0 €.0
SE 0.0 5.36F 03 2.53F-08 1.51E-0t 1,51E-04 1.51F-0% 1,51F=-084 1.5%18-0C4 1,518-02 1,517-04 1,51%-08 1,51E-00
BF 0.0 4,438 04 3.52F-01 2,84E-05 2,06¥-11 1,49F-17 1,08p-23 7.02F-32 0.0 0.0 9.0 0.0
KR 0.0 5.19F 04 1.86F 01 1,83E 01 1.82F 01 1.81F 01 1,80% 01 1.798 01 1.75% 01 1.72E 01 1.32F 01 9,68% 00
BB 0.0 1.16F 05 1.61F 00 7.67E-01 2,52E-01 8§,29¥-02 2.73¥-02 6,198-03 1, 058-04 3.12BE-06 1,282-08 1.2BE-08
sP 0.0 S.62F 0L 2.36F 03 1.83F 03 1,26% 03 8,79% 02 6.237 02 4,07F 02 1, 71E G2 1.19E 02 9,843 01 7.95% 01
¥ G, 0 1.06F 05 3.65F 03 2.98%F 03 2,23% 63 1,70% 03 1,33® 03 9.97®m 02 5.98F 02 4,95% 02 4.24% 02 3.37% 02
ZR 0.0 2,577 08 E,86E 03 5,228 03 3,79F €3 2.75% 03 2,00F 03 1,307 €3 4, 0uE 02 1, U7E 02 €.05BE-02 2.24F-08
B 0.0 1.08% 05 €.62% 03 £,20F 03 5,24F 03 8,21% 03 3,28%F 03 2,2%F 03 7,70% 02 2.87E 02 1.21E-01 1, 498-04
¥C C.0 5,857 04 S.18F 02 3.61E 00 2.10B-03 1,22R=06 7,13E~10 3,.456F-10 #,77E=-26 2,72E-36 0.0 0.0
TC G.0 7.63% 084 1,03EF 62 7.288-01 1,01®-02 9,69%-03 9,698-03 9,697-03 O9,69F-03 9,€69¥-03 9,.69E~03 9.698-03
PU 0.0 1.66% 05 3,807 03 2.81® ¢3 1.23F 63 8,587 02 5,17F% 02 2,68F 02 5.50F 0%t 2,29% 01 4,077 00 3.268-02
PH 0,0 5,817 04 6,1%1F 03 5,75® 93 5,31F 03 &8,95F 03 4.53® 03 u,27F 03 3, 4uF 03 2,87% 03 7,22F 02 5.78E 00
ED 0.0 1,30% 03 8.00F-03 S$.16%-06 €, 16E-06 §.,16E-06 9.162=06 9,16E-06 9.16E~-CE 9, 16%=06 9,16¥~-06 9,168-046
AG 0.0 2,347 03 1.08F D2 6£.68% D1 5,6%FE 01 5,137 01 4,.73F 01 8,248 01 3.13¢F 01 2,82% 01 3.26F 00 2.9€%=03
€D 0.0 2,088 02 2.85F7 00 1.28F 00 T.80F-01 L.B86F-01 3,05%-01 1,66F-01 3.93®-02 1,86E-02 1.202-02 B,U862-03
H 6.0 1.20F 03 7.54E-0% 7.26F-03 3.80F~-03 2,50F-03 1,85E-03 Q. t9F-04 2,07¥-C¢ 5,53%-05 2,20F-09 B,92E-25
5K 0.0 4,17E Ok 7.10E 01 3.61F 0% 2.36FE €1 1.92% 01 1,627 0t 1,30F 0% 7,04% D0 4,168 00 7,35P-02 5,91E-04
SE 0.0 1,04 05 1.20F 02 8,13% Ot 3,728 01 3.,%56% 01 3,83F 0t 3,298 01 2,99% 01 L78% D1 1,667 01 2,76F 0D
TE 0.0 9.08F G4 5.85F 02 1,78E® 02 1,028 02 €,.46% 0%t 4,30® D1 2.74% 0%t 1.23F 01 8.36w 00 2,95E 0O 4,838-01
T 0.0 1.60F 05 3,81E 03 2.69® 02 1.78F 01 1,3t% 00 1.01e-0%1 3,29E~03 2,89F-0% 2,867-05 2,48%-05 2. 486E=-05
XE 0.0 7.26F 04 R,.46F 02 6.4%9E 01 2,23%F 00 2,.228-01 3,60%-02 3,45F-03 5,50%-06 2,08%-08 L,67"-27 C,0
cs c.C 1.118 05 3,25F 03 2.88% 03 2,68F 03 2,58F 03 2.%51% 03 2,82F7 03 2.2tF 03 2,032 03 1,112 03 2,297 Q2
BR 0.0 5,912 0&# 3,22E 83 $.35% 03 5,.83% 02 4,31F 02 &,01% 02 3,937 02 3,89F 02 3,878 02 3,70F 22 3,%4F 02
1 0.0 9,27% o4 1.71F 08 S.B2F 03 %.15% 03 2,26% 02 &,84% 01 5,098 0C 1,328E-02 7,70%-05 4,95F-22 0,0
CE 0.0 3.20F O£ 3,15E 03 2,29F 02 1.55% 03 1.13¥ 63 8,90F 02 7,058 02 &, 9% 02 3.74F 92 6,278 01 1.23E-01
Pr 0,0 4.04F 04 1,027 04 8,6L® 03 7.58F 03 6.95% D3I 6.u43F 03 5,837 03 4,86F 03 3.53% 03 5,9LE 02 1,17F 00
¥D 0.0 5.35F 03 1.02F 03 2.94F 02 4,517 0% 6,93% DO 1.06% D0 €&,76F-02 8.,98E-05 2,40B-07 3,59%-27 0.0
oM 0.0 §.75E 03 9,04F 02 3,978 02 2,43F 02 1,68E 02 1,22F 02 8,63F 01 5.22% 01 4,58 01 2,558 01 &.00F 00
M 0.0 1.36F 03 3.36% 01 2.21% 00 2,18F 00 2.18F 00 2,18% 00 2,18% 00 2,172 00 2.17% 00 2,13® 80 2,02F OC
®y 0,0 2,52E 03 1.48F 03 6.27% 02 2.04F 02 9,79% 0t 7.12% D1 6.32FE 01 6£.,05% 61 5,958 01 5,267 01 3,75E 01
GD C.0 1.53% 01 5.08F-02 &,70R-02 4,31¥=-02 3,96F-02 3,63F-02 3,28F-02 2,36F-02 1,80¥-02 2,22F-03 1. L6F-06
B 0.0 1.73% 01 1.03% 01 8,228 00 6.12F 00 4,59% 00 3. USE 00 2.30F 00 9,13®-0%1 3,26%-01 2,89F-04 6.13E-15
DY 0.0 1,44% 00 1,23F~-03 2.08F-05 4,59F-C8 1,008-10 2,19E=-13 €,23¥-17 1,10E-26 04,.19E-35 0.0 g.0
1O 0.0 5. U6E-01 1.04F-02 1.67F~06 7,78F-06 7,B4E-058 7, L48%-DF T, ULE-0E T, BUF-06 7, U4E-06 7T.43F-05 7,40F-06
TOTALS 0.0 1.528 06 7.52F Ou 4,78F D8 3,36® C& 2,71E O4  2,30T O4  1.92F 64 1,32F 08 1.05% ¢¢  3,50F 03 1.0UE 03

L2l
44

~

TaBLe A-11, TweLve-ENERGY-GroLP PHoton SPECTRWM OF THE Fission PRODUCTS AS A AWNCTION OF PosTIRRADIATION T1vE (DavS)
REFERENCE PHE FQUILIBRTUM FOURL CYCIF -- FUYRYL DECAY TTKFS
POFAER= 20.00 ®w¥, BURNUD= 33000, 19D, PrLO¥= 2,927 13 %*%2-S¥C
THTLYE GROUP PEOTCY RFLERASE RATPS, PHOTONS/SFC
BRSTS = MT OF HFAVY MBTAT CHASGFD T PRAITAHAW
EMTFREN TIMP® EFTEP DTSCHARGE
(MTY) INTTTAL 10. D 30. D §0. D 98, D 120. D 160. D 270, D 355, D 1096. D  36%3. D
3.002-01 9.12FE 17 ©S,USFE 16 2,998 16 1,31F 16 4.05F 16 9.20F 15 8.00F 15 S5.97F 15 4.81P 15 41,12¢ 15 1.76€E 14
6.30E-01 1.72E 18 2,89E 47 1,7LE 17 1,2%E 17 1.02E 17 8.27F 16 E.40F 1§ 3I.T3IF 16 2.B0® 16 41.29T 16 4.01® 15
1.50% 00 6.40F 17 1,19F 16 4,97F 5 2,.60F 15 91,96% 15 1.7%% 15 1.54F 15 4,257 45 1,08% 15 4, 29F 14 1.35F %t
1.55E 00 3.90F ¥7 3,738 16 1,28P 1€ 2.99F 15 4Y,.05E 15 £,.38F 14 5, %87 18 &,22F 14 3,.6LT 16 1, 3LF 4 1,039 13
1.99% 00 6,54F 16 1.60F 45 7.93F 14 L, L8P & 3, 60% 16 2,99F 18 2,.66F 14 2.05F 14  1,63F 14 2.94% 33 1,207 $1
2.38% 00 T.%4FE 16 1.18F 15 &,28F 14 Y,00F 8 4,53® 13 3,152 13 2,687 12 2,14F 13 1.79F $3 4, 43T 12 3.03% 10
2,75% 00 2,93F 16 2.66F 12 2.57F 12 2.842F 12 2,29% 12 2.78F 12 2.01F 12 1.53F 12 .36 12 3,527 i1 2.737 DO
3,252 00 5,197 16 8,L2E 10 B8.C9F 10 7T.64F 10 7,227 10 £,82F 10 6,33F 10 5.14F 10 L4.30F 10 1.08F 10 B.ESE D7
3,708 00 3,07F 15 0.0 9.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
8,228 00 9,40F 15 0.0 0.0 0.0 0.0 0.0 6.0 0.0 6.0 0.0 9.0
8,708 00 U,32F 15 0,0 0.0 9.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
5.258 00 1.69F 15 0.0 0.0 9.0 0.0 0.0 0.0 0.0 0.0 5.0 n.0
TOTAL 3,90% 38 3,55% 17 2.75F 17 1,49F 17 1,16% 17 9. 46% 16 7.43F 16 5.52F 16 3,457 16 1.0U6F 16 1,33% 15
MEV/SEC 3,297 18 2.50F 17 1.44% 17 G,4%F 16 7,22% 16 5,847 16 G.58F 16 2.78F 16 2.1928 16 O.10F 15 2,74F 135
THELVE GROUP BWFRGY RELEASE RATFES, MFY/HATT-SFC
BASTS = MT OF RFAVY METRY CHARGFD 70 RPACTOP
EMBEAY TIME EFTFR DISCHERNGE s b
{MEY} THITTRL 0. D 30. D 60, D 90, D 120. D 160. D 270, D 385, D i04e. 1 3653, D
3.00E-01 9.12% 09 S5,.85F 08 2,197 08 1,21F 08 1,06F 0S8 O,20F 07 B8.00F 07 5.97% 07 Uu.84F 07 1.12F 07 1.7€F OF
6,308-01 3,61F 10 5.22F 09 3,66% 09 2,72F €9 2,15% 0° 1,74P 09 3.34F D9 T.B83F H8 5.89F 0R” 2,707 08 B.U41F 07
C _.1.%0F 00 2,357 0 4,38F OB 1.82F 08 9.52F €7 T.17R 07 6.28F 07 5.68% 07 4.59F 07 3.94F 07 1.57F 07 L.IBT 0
3,558 00 2.0%F 10 1.,93F 09 6.%9% 08 1,54F 08 5,818 07 3,30F 07 2,5KF 7 2,18F 07 1.88F 07 £.Q1F 06 5, 44F O
1.998 00 4,3G6FE 69 1.06% 08B 5,288 07 2,S5F 07 2.26% 07 1.%8F 07 1.777 07 1,367 07 1.08® Q7 1.G5F 06 8.20% 03
2.38% 00 5.66E 09 9.39F 07 3,37FE 07 8,63F D6 3,60F 06 2.50% 06 2,12F 05 1.70F D6 1.42F 06 3.52F 05 2.76% 03
2.75F 00 2.74F 09 2.4LF 05 2,35F 05 2,22F 05 2,%0F 05 1,98%F 05 1.88® 05 1.49F 05 1.25% 05 3,13% oL 2.50F 102
3,257 00 35,63F 09 9,12F 03 B.76F 03 B8.28F 03 7T,82FE 03 7T.39F 03 A.86" 03 5.57F 03 4.65% 03 1.47F 03 9,.37F 86
3.70F 00 3.79F 68 0,0 0.0 0.0 0.0 0.0 0. 0.0 0.0 0,0 0.0
B,22% 00 $.32F 69 0,0 8.0 0.0 8.0 0.0 0.0 5.0 0.0 0.0 9.0
8,70% 90 6.77F 08 0.0 9.0 0.0 0.0 0.0 0.0 5.0 6.0 0.0 0.0
$,257 90 1.90F 08 5.0 0.0 0.0 0.0 0.0 0.9 9.0 He0 0.0 C.0
TOTAL 1.10F 1% 8,33F G9 u,89% 09 3.1U% 09 2,81% 09 1,957 09 1,53% 0¢ 9.26¥ 08 7.07% 08 3,067 08 O,92F 07
’ ' e ot e A e B A TEeT CRAV RS A g L, Tt
GRMMA WATTS 5.2BF 05 4.01Z 04 2,312 04 1,518 04 1.76E 04 9.36F 03 7.34F 03 L,4SF 03 3,407 03 1.87% 03 4,80F 02
ROUCLIDFE

FH106
CELY
PE144

WUOCLIDE

Z%® 95
¥B 935
RH106
CeS13L
BA137Y

KOCLIDE

PHi06
€513
PRILGE
RU154

RUCLIDE

RE106
aG110M
€s134
PRI4G

ROCLTDE

FHEI1CE
eRiLL

Taele A-12, Suary ofF THE MosT ImporTanT ConTRIBUTORS TO EACH PHoTon Enerey Group oF THE FIssIon PropucT

Grve Ray SPECTRUM

NUCLIDES THAT CONTRIBUTE MORE THAN 57 OF THE SPECIFIC ENERGY RELEASE RATE IN A GROUP AT A POSTIRRADIATION
TIME OF 150 DAYS ARE INCLUDED,

INITIAL
4,18% 07
4,11r 07
3,128 07

INTTTAL
1.23% 09
1.312 C%
1.97E 08
4,597 08
8,248 07

TNTTTRL
5.227 07
1.04% 07
1.328 {7
6.758 06

INITTAL
1.06% 07
L,218 (6
1.81% 07
7T.7%8 06

INITIAL
4,178 06
2.28% 07

DRINCIPRL PHCTON SCURCES IW GROUP

MEAY E¥EPGY = 0,300nMFY
10, D 3.9 60, D
3.02E 07 2,9%% 67 2.75E 07
4,0t® 07 3.82% 07 3,55 07
3.02Fr 07 2.8B% 07 2,67F 07
PRINCIPAL DHUTON SCURCES IN
MELN ENFRGY = 0.630MEV
0., D 0. D £0. D
1.108 09 8,91E 0B 6€,L7R 08
1.29% 09 1,21F 09 1.03E 08
1. 427 08 1,37F 08 1.30r 08
4,55 08 B,87F 08 U4,3ur 08
8.23F 07 8,227 07 8.21F 07
PPINCIPAL PHCTCN SCURCFS IWN
HELN ENEPGY = 1.100MEY
10. D 3¢. D 60. D
3.778 07 3.63F 07 3.43E 07
1.03FE 07 1,01F (7 S.20F 06
1.28% 07 1,22E 07 1,13 07
6.74% 06 6,73F 06 6.708 06
PRINCTIPRL PHCTICY SCURCES IN
RE2N EWERGY = 1.ES50MEVY
0. » 30, D 60. D
7.6 06 T.,38FE 06 6,97 06
4,098 06 3,88E 06 3,57% 06
1,807 97 1.37E 07 1,34% 07
7.55F 06 7T,19% 06 €.58% 0F
PRINCTPATL PHOTCW SOUPCES IN
MELN FNERGY = 1,990%¥%Y
1. © 30. D €0, D
3.02r 06 2.90F 06 2,7uE 08
2.218 87 2,10F 07 1.386r 07

1, MEV/WATT=SEC

TIME AFTER DISCHARGE

9%, b 120. D 160. D
2,60% 07 2,46% 07 2,287 (7
3.30% 07 3,07®% 07 2,78% 07
2.489% 07 2,.31F7 07  2,09® 47

GROUY 2, MREV/RATT~SEC

TIXE ATFTEP DISCHARGE

20, D 120, D 160, D
5.70% 08 3,41% 08 2,237 08
B.25E 08 6,43F 68 t4.48% 08
1.228 08 1.16% 08 1.07F 08
4,22 08 u4,.11F 08 3,96F 08
8,198 07 8.,17® 07 8,13% 07

GPOUP 3, MEV/HATT-SRC

TINE AFTEP DISCHRERGY

9¢. D 126. 10 160. D
3.2u® 07 3.06% 07 2.84% 07
9.,53F 06 9.,27E 06 8.93% 05
1,087 07 9.75F 06 B.85E 06
6.68F D& 6,.65F 06 F,.627 06

GROUP &, MPV/WATT=-STC

TITRE A¥TFP DTSCHARGE

S0, D 120, D 16C. D
€.598 06 6,22% 68 S,777 06
3.29% 06 3,03F 06 2.71E 06
1.30% 07 1,268 07 1,22F 07
6.21E 06 S5.77% 06 5.23% 06

GROUT 5, MEV/NATT-SEC

TINF RATTER DTISCHAPGE

0. D 120. D 1€0. D
2.59% 6 2.U5% 068 2,272 06
1.82% 07 1,69% Q7 1,53 07

270, D
1. 858 07
2.138 07
1.608 07

27C. D
6.89F 07
1.51F 08
8., 712 07
3,587 (8
8, 107 07

270. D
2.31% 07
8,077 06
6. 76E 096
6.54% 086

270. D
U,.59F U6
2. 018 06
1. 19F 07
5,008 06

270. D
1. B5F 08
1. 177 07

365. ©
1.55F 07
1. 897 07
1.27E 07

365, D
2.50r 07
5.63F 07
7.28% 07
3.28F 08
B.OSE 07

365. D
1.33F 07
?.39F 06
5.36% 06
B, UBE DF

365. D
3.92F 08
1. 55F 06
1017 07
.17 08

365. ©
1. 5U4EF €6
9,298 06

1098, T
3.89% 06
2.83F 08
2. 137 05

10956, D
1.03% a4
2.36F 04
1. B3E 07
1,667 08
7.68% 07

1096. Db
4,85% 06
3. 758 0%
9, 01" 05
5.93% 06

1096. D
9,857 03
2,097 05
5., 128 06
5.33% (08

1096, D
3,838% 0%
1. 5617 06

3653, D
3,117 Cu
5.,38% 023
B,20F 03

3653, D
1. 497-08
3. 42F-08
1.87F QS
1. 56% 07
6.5uF 07

3853, D
3.88F Q0
3.52F 0%
t.77% 03
t,38F 08

36%3.
7.8S9F 03
1. 808 02
4,807 OF
1.057 03

3653, D
3,117 02
3.07¢ 03

£l
NUCLTDE
TNTTTAL

FR106 3.69F 06

NUCLIDE
THNITIAL

RE106 3.36F 05

NUCLIDE
TRITTAL

BH106 1,267 0L

2.67E 06

PRTIVCTPAL PEOTCY SOURCES T¥
MEAN PRFEGY = 2.3B8CHEV

. D 30. D 60. D
2.57F 06 2,37 06

PRINCTIDPAL PHCTCN SOURCES TR

MEAY FHEPGY = + T5OKEY
i0. D 3%, D 60. D
2,03F 05 2.34F 05 2.21F 05
PRINCTPAL PHCTON SCUPCES I¥
MFEY ENERGY = 3.250MFY
0. D 30. D 60, D
9,70F% 03 B.76E 03 B.2E7 03

Taste A-12 (CONTINUED)

GROTP &, MEV/SATT-SEC

TTHME® AFTEF DISCHARGE
90, D 120. D 160. D
2.29% 05 2,%V7F 06 2,01F Q€

Grour 7, MEV/WATT-SFC
TTEP RFTEP DISCHARGE

90. D 120. D 160. D
2.69% 05 1.97% 05 1,838 05
GPOUP B, MEY/WATT-SEC
TYIMF AFTFP DISCHARGE

30, D 120, D 160. D
7,822 03 7,3¢® N3 6,887 03

270. D
j.63F 06

2‘70. D
1. 19% 05

270. D
5.57F 33

365. D
1. 367 0OF

365. T
1.20% 03

355. D
4.,65% 03

3

1096. D
LU3E 05

1096, D

3,128 ou

1.

1096, D
7% 03

3653, 7
2.75% 03

3653. T
2.50F 02

3653, T
g9,37%7 00

¥el
BI211
BT212
BT213
P0O210
PO211
Nn212
D0213
PO21L
PO21S
TO2t6
Po218
a2
®N218
PH220
RF222
FR221
PR223
PR22Y
RA226
BC22%
ac22”
TR227
TH228
TR229
THZ3D
TH232
PE231

p232

U233

g23u

5235

9236

U238
NpP237
DU236
FUZ3s
TU239
TU280
UL
rU242
pOZLY
AR221
AB243
chza2
cM2u3
CRILy
CH245
TH286
CH247T
cHzLg
BR24%9
CF2u9
CTZ50
CTF251
CF2E2
CF253
Crza4

Tapte A-13, Sources oF NeuTrons erom (a,N) REACTIONS AND SPONTANEGUS FISSION REACTIONS AS A FUNCTION OF

INITTRL
3.158-03
1.0%1¥-01
1;79}3'08
6.31E=07
1.50E~-05
1. 05t 01
1.63E-03
1.038-04
u~85?*03
6.,L0E 00
4,.06%-05
8,99%=-04
3,632-03
L.85% 00
3.038-02
5.82:’1“01‘
2.087=03
3.33% 00
4.383-04
6.21E-12
2,05E-03
2,838 0¢
U,6%9R=0%
1.968-02
1.60E-08
3.58E8-02
1.078 01
53613‘02
.89 02
1.778 01
2. 74T 02
2,328 02
u,24% 02
8,2€6E 02
5.38F 06
4,98 05
T.53% 0B
1. 277=07
1.7%F 03
1.73’.\?“" 12
1,748 05
Z.117 04

» 73 07
1.07% 04
5,898 08
£.54F 02
1.30% 02
4,1{¥-04
1593?"01
1.B8E-12
8,187=03
11 13E-O1
’7‘193-03
1.708 00
1.458-11
2-862-03

10. D
3.228-03
1, 027-01
1.628-08
€E,08FE=07
1.53E=05
1.07E 01
1., 48E-0C3
1.0&'&’"0“
4,86%-03
6.L9F 0O
4,508~-05
8,128=-04
3,72E~03
4,818 0¢C
3,05E=05
5,26R-0L
2,13E-03
3.38% g0
1.BLE-05
3.92E~-04
5. 35F-12
2,109=03
2,528 00
Bs—;OE'GS
1.988-02
1.62F-08
3,%98-02
1.08E 01
8.89F (2
1.778 061
2.74% 02
2328 @2
4,308 02
8, 24F 02
5.UBE D6
5,C5E 05
7.53% 05
1.278-07
1.79% 03
1.908=-12
1.88F 05
E. 128 Cu
9,38% 07
1,07 04
5.89% 08
5,5LE 02
1.30% G2
4. 112~-C4
1.93E-01
1.BuE=-12
B-BHE‘G3
1, H4E=0 1
7.18F=-04
1.6%E 00
9.84F~-12
2.58F-03

POSTIRRADIATION TIME {DAYS)

365. T
5,80F-03
2. 2BF=01
3. 45%-06
1. 458-06
2, T6E-05
2,397 O
3. 14704
1.61F=0l
8.938-03
1. 45% 01
6. 95F=-05
1.738-08
€, 70F=-03
t. 107 01
b,728-05
1. 12¢-08
3.83%-03
T.50F 00
2& SBE‘OS
§,3u%-02
1. 10E- 11
3.73F7-03
6. 418 00
5, 318-05
20 69?."02
2.483¢-08
3a GH’E-OZ
1.59F 01
S, 78E-02
8. 98F 02
1.778 01
2,748 D2
2,328 02
4,33F 02
6.51F 082
B.65% 08
5. 06% 08
7.54% 05
1. 21E-07
1. 79F 03
7.99E~12
5,078 05
5. 128 04
2,080 97
1,057 0On
5. 677 06
5.54% (2
1. 308 02
4,112-04
1,938=01
B. 39F~-13
2,208-02
1. 88E-017
7. 18F-00
1.317 00
9, 84%=- 18

REFFRENCE DP¥® FQUILTEPTUM TUERI CYCLF -- FOEL DECARY TIMES
ATLPHA-W XYEUTRON SOUBCE IN DISCHARGED FUFL, NWFRUTBONS/SEC
BRSTS = ¥7 OF HFRAVY MPRT2Y CHARGED TO TEACTOP

30. D 60. D 3¢. D 120, D 160. D 270. D
3.362~-03 3.58E-03 3,80F-03 4,02%-03 4,317-03 5,11F-03
1. 04%=-08 B,385R=-09 3,75F-09 3,33¥=09 3,2UF-09 3,39F7-09
£.85F-07 7,807-07 7,93P-07 B,%9%-07 C,U46R-07 1,20F-05
1,60F=-D% 1,70E-05 1.81F-05 1,91E-0% 2,05E-05 2,43F~05
T.13% 01 1.238 01 1.33F 01 1,447 DY t.612 01 2,.01F 01
9, 45E-04 H_BAF-04 3, 81F-0L 3,03F-08 2.95B-04 3,097-08
1.06F-04 1,118=-048 1,15FE-0L 1,19¥=-00 1{,26E=-04 1,4UE-04
5.18F=-03 5,51%=-03 5,.8%5%-03 &6, 19%¥~-03 6,€6LE-03 7,87F-03
6.87E 00 7,478 DO 8,102 00 B8,73% 00 9,7€E G0 1.23F 01
L,61%-05 2,79F%-05 4,97®-05 S5,16%F-C5 5.86E-05 6.23F-05
5.21E=-04 2,69F-0B 1,B8®-04 1,67F-G4 1,63F-04 1,.70F-04
3.88F¥-03 4,13F-03 &5,39F=-03 O4,64F-03 &,98P-03 G5, 90F=-023
5.20F 00 5,66% 00 6,137 00 6,61F 00 7,39 G0 9,27F 00
3,138-05 3,25%E~-0% 3,38E-05 3,51E~-05 3.71E-05 4,237-0°F
3,378=-00t {,74F-08 1,22F-08 1,08F-04 1,05E-08 1, 10E-08
2.227=-03 2,37E-033 2.%1P-03 2,66%-03 2.85FP-03 3,38E-03
3.57% 00 3.89® 06D #,2'1® OO0 U4,58F OO0 5,082 00 6,37F 00
1.89E-0% 1.96%®-05 2.03E-05 2.%112-05 2,22F~-0% 2,53F-05
2.5%8=-04 1.,30E-04% S,078-0% 8,06¥-05 7.8LE-DS B,22F-05
£.61%~12 7.01E-12 7T,40F~12 7,80F~12 B,32E-12 9.77E-12
2.19F=-03 2,33F-03 2,47E-03 2,60%-03 2.78F-03 3.29%-03
3.09% 0L 3.3€E 8¢ 3.86uUE 00D 3,92F 00 4.31® 00 5, EiF 0OC
L,78E=-05 4,79F-05 U4,84EBE-05 L,BSE-05 &.05E-05 5, 14T-03
2.028-02 2,088-032 2,%14w-02 2,20E-02 2,28%-02 2.507-02
1.67F=-08 1,75%~-08 1.B82E~-08 1.,89®-08 1,99E~-08 2,26P-08
3.%9F-02 3.€0F-02 3,60F-02 3,60%=-02 3.61E=02 3,63%7=-02
1,128 0% 1,178 01 1,21% 01 t.26% O1 1.,31% 01 1.86F Ot
5.628=-02 35.,63%=-02 5,6%E-02 5,66E-02 TS,68F=-N2 5, TUE-02
8.90F 02 8,%0F 02 8.%1F (02 B8,92F% 02 8,93F 02 8.96F 02
1,778 01 1,77= 0 1.77°R 01 1.77F 01 1.77E 91 Y, T7TE DY
2.74F 02 2.74® 02 . 7UE 02 2,74F% 02 2,748 £2  2,7T4E 02
2:32F 02 Z.,32® D2 2,327 02 2,.32% 02 2,32% 02 2,328 02
4,338 02 4,33% 02 b6,33F 02 4,33 02 U4.,338 02 08,337 02
8.13F D2 T7.387% 02 T,82F 02 T.88F 02 T,48F 02 5,937 02
S.46F 06 S.508 06 S,52F 06 S.55% 06 S.578® 06 5,62F 05
5.06% 05 E&,06F% 05 53,06% 05 5,06% 05 ©S.06E 05 G5,08F 05
7.53F 05 7.53® 05 7.%83F 05 TF,.E3% 03 T.53F 65 TF.S53F 05
1.27€=07  1.26¥-07  1,26F8~-07 1.25®B-07 1.25B-07 1,23F-07
1.79F 03 1.79F 03 1,79® 03 1,79% 03 1,79F 03 1,79F 03
2.20E~12 2.TEE~12 3,27¥=-12 3,78E=12 4,47®-12 €,36E-12
2,.02% 05 2,30F 0% 2,5%8% 0% 2.85% 05 3.22%® 45 4,22% 05
S.42F 04 5,.12% O& 5,12B 068 5, 12F 04  5.12F 04 5,12F 03
8.62F 07 7.89% 07 6.58F 07 5,88% 07 4.86F ¢V 3,11F Q27
1.07F Q4 1,07F O 1,07® 0¥ 1.086F% Q% 1. 06F 04 1,057 08
5.87F 06 E.86%W Q€ 5,BLF D€ 5,82% 06 B,7I9% 06 5,73IE 06
5.5uF% 02 S,5uF% 02 5,54E 02 5.54% 02 5.54% 02 5.54F Q2
1.30% 02 1,30% 02 1.3C®% 02 1.30% 02 1.30F 02 1.30F 02
t, t1E-08 &,118-08 4,118-08 4, 11E-OL &8,.11E-Q4 &, 11F-004
1,338=-0% 1,938~-0% 1,93E-01 1.93E-0%1 1.93F¥-C1 1, 93E-0%
1. 7€F-12 1.658=12 1,548=-12 1,40¥=12 1,32®8=-12 1.03F-12
£,21F=03 B.16E=-03 2,97E-03 t,%7¥-02 $.388-02 1.87E-02
1. 13F=-01 1,13E~-0% 1,12E-01 1, 12E-G% Y. 11E-GY1 1, 10E-01
7. 48F=-00 7,18®=-00 7,18E-08 7, iBE-OL 7, 18E-04 7T, 18E-QU
1.66F O 1,637 00 1,59F 00 1.56% 00 1.51F ©0  1,40F OO0
B,52F-12 1.419-12 4,37F-13 1,36%E~13 Z,87E=-12 3,97P-1%
2.03E-03 1. 447-03 1,02E=-03 7,23F-04 &£,S57P-Q8 §,30E-0L

4, 37E=-05

1096, D
1. 138=02
5.07R=01
k., 34E~-09
4,6LB-05
5.398-05
5. 30% 01
3, 96R=-C1
3. 30R=04
1. 748-02
3.22% 01
1- 33‘3-013
2. 18E-01
1. 31E=-102
2,40 01
3, 70B-05
1. t18-04
7.487-03
1. 878 01
5, B0E-05
! ¥ OSE-GH
2. DUE-13
7. 138-C3
1.43% 0%
6. 61E-C5
4, 16R-02
4, 26E=-(8
3.75=2-02
2,298 01
&, 162-02
9.,17% G2
1. 772 ¢*
2. 7LE 02
2.37Z% 62
4, 33% §2
£, 00% 2
5.638 G¢6

t. 138 06
B, 1R Q&
g,ua8% @5
1, 0608 Qu
5. 288 06
B.548 02
1. 308 02
H,11R- 0L
Y, 937=01
1. 67R-13
3.35%7-02
9, 728-02
7o 17E=QL
7. 74P=01
%, 38%~-39
1, 017-08

3653. D
2,837-02
1.07% 00
7,7%E-09
£.09F-0%
1. 35?‘0“‘
1. 12F 02
T.06T=-04
1.517-033
4,367-02
€.B2F 01
6. 547=04
3| SQF-OH
3.27E=-02
5. 167 01
K, oup-0u
2.518-08
1.87F-02
I.55F 01
2, 66F=0b
5, 107=-11
1.782-02
3.03% 391
?- 183_‘-‘-'0-&
2, 54FE=-02
1.05E=-07
b, 12%-02
3.06% D1
—’?n L‘»Z?-OZ
9,827 02
1.777 01
2.74F 02
2.32% 02
4,37% 92
7,29F ©1
£.33% 06
5.058F 45
7.56F 08
7.917-08
1.7¢% 03
A LLP~-11
Z.8B7E 096
5117 &4
2,09 G4
8.63% 03
6,022 06
5. 54F 02
1. 307 02
L,117=-04
1.937-01
5, QUF-14
3' 59}?‘@2
6.717-92
‘71 13F-Bu
1.287=061
G.0
1.927-21

74|
PU238
PU250
PU24Z2
pp2ut
cn2n2
cM2ub
cHM2ué
cM248
cn250
CP250
CF252
CF254

- P - = e e b A A S A e e i S M S M AR R MR YR W N e D Wy MR Ol R S A e MR P R M R e G S e e e e b AR e v e b e ke A e A O A M A D A R R R A R MR BB D p e e e e

INITIRL
3.73F 05
2.0tF 06
7.07F 05
2021E‘07
1.98F 08
3.uL% 08
2,0uF 06
8.11F 03
1,227=-03
3.9u% 03
2.2t 05
1.66% 02

5,478 08

6.57F OB

10. D
3.78% 05
2.0U4F 0§
T.07TE 05
2,43E-07
t.91% 08
3.L447 08
2.0u® 06
8,118 02
10223'03
3.95% 03
2.19E ©5
1,U8F 022

5.40F 08

TaBLE A-13 (coNTINUED)

PEFEPENCE P¥® EQUILIERTUOM FUEL CYCTE -~ FUFL DFCRY TTMFS

SPONTANEQUS FISSTON NEUTROW S0UPCF IN DYSCRHARGED FUEL,
CHARGED TOQ REACTOP

30. D
3,79% 05
2.04% 06
7.07E 0B
2.87E-07
1.75F 0B
3.L3F 08
2,04F 06
B.11F 03
1.22F-03
3.94%F 03
2.16F 05
1,17F 02

6,23F 08

BASTS =

60. D
3.B2F 05
2,0U% 06
F.077 05
3.53%-07
1.547 08
3., 42F 08
2,048 06
B.11® 03
1.228-03
3.,92F 03
2,12E 05
B.327 O1

5.02% 08

5.90F 08

WT OF

90. D
3,837 0%
2.00F 06
7.078 05
4,19%-07
1.35% 08
3.L1% 08
2.04% 06
8., 112 03
1,22%-03
3,918 03
2,07F 05
5.90F 03

L, 827 08

RERVY METAL

120, D
3.85F 05
2.0u4F Q€
7.07% 05
3.85?-07
Y.2%% 08
3.40F 08
2.04% D6
8.11F 03
1,22F-03
3.89F 03
2.03® 05
L,99% Ot

L,65F 08

%.377% 08

16¢. D
3.87E 05
2.0L7 06
7.07% 85
5.73E-07
1.01E 08
3. 387 08
2.04E 0¢€
8,118 03
1. 22E-03
3.87E 03
1.97% {5
2. 55% 041

4,u%% 08

. 07% 98

270. O
3.907 05
2, 04F 08
7.07F 05
8.15%-07
6.337 07
3.34F 08
2. 0LF 06
8.12F 03
1.22F-03
3.81F 03
1. 82F 05
7,517 00

NFOTRONS /SEC

365, D
3.92F 0%
2,08 08
7.07% 05
1.02E-08
4,22¥ 07
3.31F 08
2.0um 08
B.12F 03
1. 22B-03
3.758 03
1.70E 05
2.53E 00

I.79F 08

4.13F 08

1096. D
3.91F 053
2.04% 0%
7.07® 05
2. 52"~ 06
.93 06
3.07F 08
2.0u4% 08§
B. 127 03
1.22%-03
3.38% 93
1.01= €5
5.83e-04

3. 1% 08

3653, D
3, 70F 05
2.0UF 0¢
7.07F 0%
8,28F=06
L.26%" 04
2.3%F 038
2.0Lr 06
8,127 03
1. 22E~03
2,337 03
1.€18 QU
T.11P-1¢

2,40% 08

921
——

GAMER

EMEAN
(MEV)
3.008-02
Q.OOE“OZ
6,00R=-02
1.007-01
1. 508~-01%
2.00E-01
1,108 00
1,58E 00
1,998 00
2.38E 00
2,758 00
3,2%E 00
2,.T0F 30
L,222 00
L,7CE 00
5. 25F 0O

TOTRYL

MBY/STC

EMEAN
(REY)
3.00E-02
B, 00E-02
1.0CE-01
1. h02-019
2. G0E-01
3., 008-01%
5, 30F=01
1. 16 0O
1.55% 00
1. %98 00
« 3BT 00
Z.78E Q0
3.25% 00
3,70 &0
4,228 Q0
B,70% 09
5.28% 00

TOTAL

HARTS

TapLe A-14,

TNTTIAL
5.237 16
2.00F 17
2,558 47
3.90F 17
1.80% 17
1.81F 17
9.56E 16
1,60 16
8,59F 15
2.75% 08
1,377 08
6.69F 07
5,028 07
1.93% 07
1.248 07
7,84F 06
3.71% 06
2,337 06

1. 387 18

1.678 17

INTTIRL
5,23F 07
2,67F 08
5.118 08
t.30% 09
8.92% 08
9.43F 08
9.56F (8
3,36E ¢B
3.15% €8
1,428 ©1
3.06F 00
5.31F Q0
4,60F G0
2.10F 00
1.53F 0
1. 10R 090
5&81E‘01
L.08E=-01

E1GHTEEN-ENERGY-GROUP PHOTON SPECTRWM PRODUCED BY THE ACTINIDES AND THEIR DAUGHTERS AS A FUNCTION OF

POSTIRRADIATION TIME (DAYS)

RETEPENCE PWR EQUILTEPTIOM FUEL CYCLF -~ FOEL DFCAY TINES

POWER=  30.00 MW, BURNWUP= 33000, 8¥D, FLUX= 2,92F 13 Nk*2-8EC
ECTINIDE PEOTOW FELEASE RATES, PHOTONS/SFC
BaSTS = HMT OF HEAVY KEPTRL CHARGED T0 PEACTOR
TIME AFTEP DISCHARGE
10. B 3. D 6¢. D 90. D 120, D 160, 270, D
B,U4FE 15 B5,.69% 14 2,83F 13 1,37E 12 2.L4F 1t 2.09F 11 2.60F 11
£.157 15 S,.,80F 13 7.5%E 12 6,14F 12 6,08F 12 S5.98F 12 65.88F 12
1,717 16 5,86F 14 2,74F 13 3,.5%% 12 2,63 12 2,828 12 3.47F 12
5.158 13 1,22% 12 1.18F 11 €.838 16 5,287 10 5.79% 10 4,92% 10
9.€5%F 1€ 5,85% 13 1,83F 12 4,078 11 3.39F 11 3.34% 11 3,29F 11
9.80F 15 3,728 14 t.6LE 13 9.22% 1t 2,12F 11 .78 1t 1,77F 11
5.27F% 18 4,98E 13 1.78F 12 1,858 11 1.23F Y1 1.19F 11 1.19F 11
6.,55F 1 2,53F 12 7,158 11 E.9UE 11 6.76FE 11 6.55F 11 6,12F 11
2,82F t4 5,398 t1 1.38®E 11 1.38" 11 t.38E 11 1.38F 1t 1.38F 11
2.82F 08 Z,uBE 08 2,33F 08 2.24% 08 2.16F 08 2,067 08 1.86F 08
1,32 08 1,28% (08 1.23F 08 1,182 08 1.13E 08 1.08F 8 9,7&F 07
6.60% 07 6,39% 07 6.10F 07 5,.85% 07 5.63F 07 S,37F 07 u,84F 07
5.€0% 07 5.01% 07 5.0€6F 07 S5,13E 07 5,218 07 S,40F 07 S.89%F 07
1.917 §7 1,858 07 1.7€r 07 1,.69% 07 1,63 ©7 1,.55% 07 1,407 QY
1.232 07 1,%9% ¢7 1,138 07 1.098 07 1.05F 07 9,977 06 8,98% 08
7.73r 08 T,£8% 0f 7,15F 0E 6.85E 08 £.59%F 06 6,29 0F 5.%87E 06
3.66F 06 3,5uR 06 3,38 O£ 3,24® 066 3,12F 06 2.98% 06 2,.68F 04
2.308 66 2.23F ¢& 2,13F 06 2.04F 06 1.36F (06 1.,87% 06 1,69% 05
5.8uFr 16 1.,70F 15 B8,22F 13 1,35F 13 1,05® 13 1,085F 13 1,10F 13
7.20F 18 1,S5E 14 7,.83F 12 1.40% 12 1,12F 12 1.11F 12 1.12F 12
ACTTNIDE FNEPGY PFLEASE RBRRTES, MEV/RWTT=SFC
BASTS = MY OF HFAVY METIL CHARGED TC FPFACTOX
TINE RFTER DISCHARGE
10. D 30, D 60, D 90. D 120, D 160. D 270, D
L.uu® 06 5.68F 05 2,63F 04 1,37E 03 2.U4E 02 2,09® 02 2,60F 02
t.09F 07 7,73 04 1.0t® 04 B.19% 03 B.05E 03 7.982% 03 7.8RE 03
J.U28 87 1,17F 06 S.48E Q¢ T7,11E 03 B.26% 03 5.53F 03 £.93™ 03
1.72F 0% &4,08% 63 3.93F 0z 2.28% 02 2.08F 02 1,93F 02 1.84F 02
4,838 07 2,92% 0% 9,185E 03 2.038 03 1.70E 03 1.£7% 03 1,687 03
§.538 07 2.88% 06 1.0°F 065 6.158 03 1.42E 03 1,198 03 1,18F 03
5.27% §7 8,98% G5 1.78R 04 1,952 03 1.23F 03 1.19F 03 1.19F 03
1.38E 07 5.32F 04 1,50B D4 1,48F 0% 1.42F 04 1,37F 04 1.29F D8
1.03% 07  t,98% 08 S5,07F 03 5.078 03 5.07® €3 ES.07k 03 R.07F 03
1.36F 01 1.26% 01 1.21F 01 1,18 Gt 1.¥1iF Ot 1.08% 01 9.61F OO
B.798 00 B.51E 00 B.1H8R OC  7,.81% 00 T.35YR 90 Y,17% 00 6,57FE 00
54238 00 S5.07E 00 4,84 90 4,.604P2 00 4,47F 00 4,26% 0O 3,88F 00
4,58E 00 L,.60®% CQ L,68F7 GO 4,70® GO 4.78® O0C 4,95® 00 S5,.L0F OO
2,07 60 2.,00% GO Y.91F 00 1.83® 00 1,7e® 00 1,887 00 1,51F 00
1.5%F 00 %1.L6% 00 1.40F D0 1.38% 00 1.29F §0 1.237 D0 1.1%1E 0D
1.898 €0 1.05BE CC¢  1.01t® 00 9.64¢P-0% 9,28E~-0% B8.835E-01 7.%7F-01
B.738=-01 5.55%=-01 5.30F-01 S.08%-0% 4.898-0%1 4&4.667-01 4, 20F-01
L,03r~01 3,908-0t 3,73F=01 3.57%-071 3,848FT=01 3,28%7-0%1 2,95¥-01
2,407 08 S,17R 05 2,4BE 0S5 G,87F 04 3,74% Q4 3,69% 04 3,72F 04
1.15F 03 2.88% 01 1,198 00 2,25%=01 1.80r-01 1,77E-01 1.79F-01%

365, D
3.08% 11
5.827 12
4,028 12
4,u5% 30
3,268 11
1.777 11
1.1%82 11
5.89% 11
1.382 11
1.757 08
9.1%" 07
4,837 07
£,812 07
1.31% 07
8,407 08
. 30F 08
2,517 D6
1.58% 06

1. 157 13

1.13=2 12

365. D
3.05F 02
7,76 03
8.04F 03
1.u8% 02
1.63% 03
1. 18% 03
1.19% 33
Y.28% Ot
5.068 £2
%.027 00
£E.07% 80
3.58%% DO
£.88% 90
1.428 00
1,087 30
7.&6?‘01
3' 93?-03
2,76w=-01

3.77% 04

1.812-01

S

109¢€, D
6. 28F 11
5.7%F 12
8.05F 12
3,.88F 10
3,207 11
1. 747 11
1. 18% 11
5. 887 11
1. 387 11
1. 567 08
T. 537 07
3.72% 07
t. 13F 08
1, 07E 07
€,90% 06
4. 35F DFf
2.08% 06
t. 307 OF

1, 57F 13

1. 357 12

1096. D
6. 287 02
T.61F 03
1. 61 0o
1. 297 02
1.60F €3
1. 16F 03
1. 18% &3
1, 18E Of
5.06% 03
7.54% 00
5. 06 0OC
2,957 00
1.03% 01
1 167 DO
8051E-01
5, 127-01
3, 23701
2.275=01

4.4QF OO

Ze 16701

Gt
e j‘lfi'

3683, D
1.54F 12
5.6%8 12
1.94% 13
5.03% 10
3.178 119
1.682 11
1.1€8 11
5.42% 11
1.38R 11
1.178 08
6.,07F 07
2.84% 07
2.16% 08
8.21% 06
5.278 06
3.32F 06
1.57% 06
9.407% 0%

2.79F% 13

2.05F% 12

36%3, D
1.548 03
7.58% 03
3.88% Ju
1.68% 02
1,588 03
Te117 03
1,167 03
1. 127 Q4
5.06F 03
5.03% 00
£,03% 00
2,257 00
1,987 01
8.8??‘01
£.,50F=01
4L,668F=-01
2.47E=01
1.738-01

L2l
PORER=

HE U
TL207
T1208
T1.209
P32C6
o32C7
PR2GSH
PE2G9
PE21D
PB2141
PB212
PB21L
BT209
BT210
BT211
BT212
BET213
ET21E
E0210
N2
P02%2
P0213
PO294
20215
POZ5 6
PD218H
AT2537
PE299
R¥220
oN2272
P22
FR223
PAa223
Ta22¢
R&22%
P:E226
na228
AC225
7227
ac22%
TH22 Y
TH223%
TH229
TE230
TE231
TH23Z
TH233
mH234
Pa231
PA232
PL233

Pa23uy

TaBLE A-15,

30, 00KN,

1

OO DOOD DI OODORTDODIDIDIICCTODTOIDTDDGOODODOIIDDIDIODDIAIOOOD IO A
-]
x4
aQ

=

" ® # » & &4 & & 4 & B g & P s & T & 8 & & 2 s * 3 » " 3 &

OGO OO DIMOODOTIOOIDODDIOIOITCADDIIOODDIIDOITDITILODDITODOO

DISCHAPGE

0.0

1. 218-06
B.23FP-04
T.6TE-10
0.0

0.0

G, 0

3.L9E-08
BQSgE-1D
1. 271E=-0%
2.29E-03
2.008-08
0.0

B.UUE-?O
1,217-06
2.,297-03
3.L49%-08
2.00EB-08
5.77TE-10C
3.64B-09
1, 467=-03
3.u1e-08
2.008-08
1.217-06
2.292-03
2,008-08
3.498-08
1.271E~0%
2.,29R-03
2.00=2-08
3.49%-08
1.8329-08
1,2%F=06
2.298-03
3.49%-08
1.998-08
3.88p-12
3.uGE-08
1. 3GE-05
3.86%-12
1.23%=-06
2,27%-03
3.59%-019
2.06%8-05
1.71E~02
3.,17E~-11
c.0

3.147-01
2.472-95
10?62-37
3, 807-01
3. 14E=-01

BURKUP=

THE WASTE RESULTING FROM A MeTRIc Ton OF URaniwvi CRARGED TO A PWR

13000. KRD,

1. ¥
0.0
2.03F-06
5.77F-04
7.73E-%0
0

W 3 DD

0
.0
-51E‘OB
1.62F-09
2,G0EF-06
1.60F~03
2.898+08
0.0

?.52?-&9
2.007=-03
1,607-03
3.517-08
2.39F-08
9. 18F=-09
6.12F~-09
1.03F~-03
3.484E-08
2.89%-08
2,048-06
1.607=33
2.89E-08
3.51E-03
2.0UE-0%
1.50F-03
2.89E-08
3.51E-(8B
2.85F~08
200&?‘06
1.607-03
3.51F7=-08
2.,89F7-08
6.53F=12
3.51F-08
2.04F=068
5.83%-12
2.018=-0€
1.60E-03
3.59€-08
2,062-05
8.5%E~-05
J.i8E-11
0.0

1.58%-03
2.478-058
0.C

3.40F-01
1.58%-03

BRSTS

3. ¥
0.0
3.44%-06
2.91F-04
TB7E~10

5,17E-0k
3.50E-08
4,6BE-08
3-“5E-06
8. 0BF=-04
L,6EF-03
3.582-08
BuaSF'GS
8.087-0CL
L.68E-08
3,58F-08
L,82F~-08
3.45E-06
8.08E-04
3.56%=08
L.6EF=08
7. 138- 14
3.582-08
3. LEE-08
3. 13E-11
3. LDE-TE
B, NLE-JU
3,58%8-08
2.078~08
5.55%8-05
3.208- 114
0.0

1.57?‘03
20&7E-05
0.0

3.40E-01
1.57E-03

FLOX= 2.92F

= KT

10. T
¢.0
T.T70E~06
5.,09%=-0%5

0.0

1.95E-08
7.72E-06
?.ufE‘OB
u025E‘08
1. 147=-07
1.95E-08
2.32%8-08
4. QUE-DS
&, 157-08
1. 108=07
7.72F=08
1.4 1E-00
Y. 1OR-07
BOZSF‘OS
7.72E-06
1, L1E=-04
1. 10E~07
b, 25F=-08
1. 08F-07
7.72E-06
1.“1?‘0&
4,2%%8-08
1. 107-07
2.2598-11
4,2%E-03%
7.71R-06
2.21%=-1%
7.61E-086
1. 41E-04
4,2%E-08
2, 107-05
SOSBE‘OS
3,25%-11
t.0

1.87E=-C3
2.47%~-C5
0.0

3.61R-01
1. 578-83

130 /CEx*2-SEC

NUCLIDE RADIORCTIVITY,
OF HPRYY MRETAI CHARGED TO PFACTOR

30. ¥
0.0
1-57E‘DS
2,83F=05
2.18E-09
D.0
n.0
D.0
9.69%~-08
1. 138-C7
1.58%-05
7.872~05
2.567-07
.0
1. 13E-07
1.587-05%
7.877°-05%
9,697-08
2,96E-07
1. 33707
4.73R=08
5.0“?‘05
%,87F=-03
2.96F-07
1.583E-05
7.87E-05
2.%67-07
49,897-08
t,58%E-05
7. 87705
2.96E-07
9,B9F~08
2.218-07
1.58%-0%
7.37R=05
9.69%-09
2.96F-07
3.20%-11
9,83E=-0%
1.53%-0%
3.20%-11%
1.55E-05
7. 87E-05
G,B89%-08
2.26E8-05
8.56F=-05
3.397-11
n. o
E-57E'03
2.47%-05
0.0
3.”2E‘0‘
1,37®-03

CUPIFS

100, ¥
0.0
2. 37E-05
1. 45%=-05
1.61F-08

E,09%-0%

1. 11F-06
7.50F-07
7.u7-08
2.578-05
ToNTE-07
1. 11E8=06
2.387-05
4.07F-05
;111F‘06
T« 33E-07
2. 38F-05
L, 098-05
1.112-06
7. 33E-07
3.33¥9-07
2.38E-05
4, 0{E~0S
T.33F7-07
1. 11E-06
3, 897-11
7.338-07
2.388-05
3. 887-11
2,38F=-05
4,0%7-05
7. 33¥%-07
3.3488-05
8;%7?'05
3.897-11
n.&

1. 57%-03
2.58F-05
f.0

3. L5F-01
1. 577=013

CALCULATIONS ARE BASED oM ReMoviNg 99,57 oF U anD Pu aT 150 DAYS AFTER DISCHARGE,
REFERFNCE PHR EQUTILIBRIUM FUET! CYCLE -~ WASTE DECAY TTIMES

300. Y
0.0
2, i9F=05
2.1i7=-06
1. 397-07
0.0
0.0
0.0
5.30F-06
5, 01F~26
2-50?-05
. B5F= 0%
LD0FP=-06
0.0
5.01F7-06

TN

2,50F-05

5, E5F-06
6.30F-06
D0¥-96
LO01P-086
. 50F-0R
757-06
167~ 06
00F-06
50P-05
BEF-06
G0F-06
30F-36
SUF-05
352-0%
00F-06
30F-06
50F-07
2.507-08
5.85F-06
5. 30F-05
8.00F-0%
5. 35F=-11
6.30r-025
2, 50705
5.35?“11
2.078-C5
5. 85F-0C6
6.30F-C%
9,0(0F-05
8, 60F-05
5.35E-11
0.0

1. 57F-03
2,51F-05
0.0

3. 5L7-C1
1.57F-03

AR YO U YO L Jd o O
.

a 5 8 & e % 2 & &

w o
¢ e u

1000, ¥
0.0
2.597-058
2.54F7-09
1.532-06
’j.o
0.0

.0

.96F-0%
030F-G%
. BNF=-05
05%-09
30E-05
0
3

0
€
B
2
7
€
0
£, 30F-05
2.60E~05
7,057-009
6.96F-0%
6. 3DE-0F
6. 30F-05
7.79E-0R
4,517-09
5.80FP-08
f.30F-05
2. FOF-05
7,05F-009
€. 30F-05
6.S6F=-05
2.607-05
7.053_09
6,308-05
5,96F~-0°5
3.64F=07
2.60F=-05
7. 05F-00
5, 9605
£.30F-05
1. C8P=-10
6.96%-05
2, 50F=065
1. ORF= %0
2.567=-0%
T.05E-09
6.,96F-05
3.88F-04
8.737-05%
1.708%-10
Q.0

1, 87R-03
2.607-08
Oe 0

3.6%F-01
1.578-03

-
-
-
*
.

3000, ¥
0.0

2. B6E-05
1T.06R-10
$.338-05
0.0

0.¢C

0.0

6. QuTE-04
L, 73R-014
2, 867-05
2.957-10
u,78%-0u
0.0

L, 78R=-0b
2,86m-05
2.95%-10
6.047-04
b,78e-04
“.Wap_fiu
B,597=-(C3
1. 898-10
5. GiE-0L
a,78%-0u
2. BRE=-08
2,9%7-10
b, 768-01
f. 0208
2. BSE-05
2.95E*E0
4,78%=-34
6. 04E-0L
4, 01E-07
2.868-05
2. 958-10
SQOuF-Ou
. 738~ 04
2.9857-10
A, OLR=-0L
2. REE=-D5
2. 95E~- 10
2.828-0%
2. 95E-1¢
A, QUP-0OL
1. 10RE-03
Q,21F-05%
2.,95E-1%9
0,0

1. 57F=-03
2. 85T-0F
0.0
3.flRE_01
1.57%-02

Isotopic AcTiviTies (Ci), As A FuncTion oF TiME AFTER PROCESSING, OF THE ACTINIDES AND THEIR DAUGHTERS IN

10000, ¥ 100000, ¥

0.0
3.50v-05
4,31E~-10
1,22F-04
0.0
0.0
0.0
5,55F=-03
2.797-03
3. 91F-05
1.207-09
. 79F7-03
.0
2.79F-03
3.%12-0°%
1.202-09
5.557-03
2.793-03
2,797-03
1. 47F=-07
T.677-30
5.037-C3
2,797-013
3.91E-05
1.207-00
2-793—03
5,58%=03
3.91P-05
1. 207=009
2.76F7-03
£.55%7-03
S UIP-07
3.917-0%
1.207=-09
%.567-03
2-79F—G3
1.20%-49
5.55F=03
3.91F-05
1.20F-09
3. B87-05
1.20F=-0¢
5.557-03
3.59F-03
1. 17751
$.207-09
0.0
1. 57F-03
3.99F-05
.0
3.75E-01
1.577-03

0.0

2.70B-00
6,69F=~09
2,88%-073
o0.n

0.0

0.0

1.29F-01
2.2%7-02
2.70E-00
1.RER-08
2. 21F-02
0,0

2.21E-02
2.7GE*OH
1. 35T~ CH
1,297=-01
2,21E-02
2,27R=-02
8. 11E-07
1. 19E-908
f.27P= {1
2,21%=-02
2.708-04
1.85F-08
2.218=-02
1.29E-01
2,70F-00
Te BEF=-06
2.29E-02
1.29%8-01
3.79¥-08
2.70F-00
1.8€7-08
1.29F-01
2.29F=-C2
1.867=-08
1. 29E-01
2. T0F- 04
1. REF-08
2.67F-04
1.86%7-08
1.297-01
2.20F-02
3.53F-04
1.86F-08
0.0

1.57E-03
2.70F‘Ofi
0.0

3.657-01
1.577-03

8¢l
POVEY?=

PA23.
U232
0233
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w235
U236
U237
U238
7239
y2u0

NP236

NP237

HP2IR

wp23%

¥pZLUON

¥oaus
BUz236
PUZ38
POZ3%
PU2LG
241
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rp2L3
26y
PU245
LMY

R¥Z2L2Y

1mM2uz
Amzu3
aM2an
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ch2u2
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CH245
CcHu286
cm2e7
CcH2u8
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BEZUC
BE250
CF249
CFr250
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1.278-02
1.,5378=-03
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19 583“'03
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1. 628 00
2,398 00
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5,148 00
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3.78E-08
1,708 08
3,682 0O
2.80% 03
3. 818-01
£, BQE‘Cz
2.528-07
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8.38E-08.

2.02F CB

33000, ¥WD, FLUX=

1. ¥
1. 58F=056
5.04E-05
1.8LE-06
3.93E-03
8,55F~058
1. 48E-03
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1.57%=-03
0.0
6.08F-15
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2.74E=07
3. 46E-05

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€.71F £3

BASTIS

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5 TR=-08
6 81F-03
L. 812-08
4,85E~-03
8.558-05
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2. 69 01
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9.92F 40
9,02% (6
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2; 3?3' 1‘7
3.368-09
1.68F 02
3,447 Of
2,141 03
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1.65E~23
3,088 03

TapLe A-15 (conTINUED)

EEPERENCE PWR EQUILIBRTUH PUEL CYCLE -- WASTE DFCRY TTIMRS

2,927 13N/CM%R2-5EC

300. ¥
1. 57E~ 06
5.79E-06
k, upF-Qu
3.8B5F-02
8, 607-05
1. 51E=-013

3. 3HW*O?
7, 428~-03
2,52E-07
1. 82F-12
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1. G%F 02
Z.33F 00
2,338 00
1. 777 1
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6.76E=-09
1. 53E-03
2, 40E=-02
B.73E-05
1. 68F-03
7;55E-05
1.57E=03
6.0
6.068~12
0.0
3.68E-01%
8.0
1. 66F 01
£.06%=-12
0.0
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3.152-01
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3.598 01t
8., 56E=-072

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1,86F 01
7. 89F-15
0.0
7,B8RE-02
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3, 1L7=01
5.30F~-072
2.528=-07
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G.¢
B.878~-14
1.38E-0%
8.9‘7"? 18
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NOCLIDE TRDIQRCTIVITY, CUPIES
= BT OF HFLVY METAL CHRARGED TO PEACTOP
10. ¥ 30, ¥ 100. ¥
1.57E-06 1,57®=-06 1,57¥-06
B,728~-05 7.66F-05 3, 81P-0K%
1WS1E-05 4,438-05 1,07F-04
6.,327-03 1.12%-02 2,36F=02
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1.5378-03 1,57%-03 131.57F-03
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£.078-12  1,827-13 £,06E=-13
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3.892-01 3,82%-01 3, 838R-01
0.0 D.0 0.9
1.82% 61 1,81® Ot 1,80F 0%
6,07F=14 1,828-13 &,06F-13
0.0 5.0 0.0
1o 39F~-04  1.07E-06 4,31E-1L
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1.63% 02 1,68F 02 1,.50F¥ 02
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1,829 01 t.81% 01 1,807 01
7,907~17  2,.37B-16 7,89F-18
1, 19E~11 1, 18F-18 0.0
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2,965 00 1,92F 06 4, 21P-D1
1648 03 7.62¥F 02 5,272 014
3I.B1E-D1 3.0%1E-01 0 3, 397-01
£, 83802 £.818~02 &, TRP-02
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7:.917=07 7,91E-07 91F=07
G, 0 (O] 0.0
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7. 952-07 T,88%-14 0,0
G, 23B-14  9,22%-10 9,19?-1&
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2, 17705 S2¥-08 1 84=-07
Z.72R-07 0 2,E8Wm=07 2, S‘F 07
3. 27B~08  1.73B-0B 1, BRE-1&
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0.0 0.0 .0
2,297 03 1,20% 03 3.21r 02

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3000. ¥
1. 57E-06
2! 931':— 17
4,708=-03
4,39%-02
3.21E-08
2. 10E-03
f.38F-06

2.563*01
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1. 827« 11
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10000, Y 100000, ¥
1.572=-0G6 1,577=08
0.0 0.0
1.56E-02 1.29%-01
4,318-02 3,.38BE~-02
1,177-04  3,.53F-0d
3.04%=-03 3,93%-02
3.55%=-08 1,87F=0%9
1.57F=-03 1,57%=-03
a1 0.0
6.,00FP-11 5.5%0F-10
0.0 £.C
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0.0 .0
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€, 00F~-11 5.50%-10
6.0 0.0
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4,11r Q0 5,78v-01
3:173 30 3111E"DQ
1, 487=0% 7,798-05%
8.878-03 7,031P-03
2,32%-07  2,518-07
£.01%~-31 5,51E~-10
G.0 0,0
T,888-0% B8,22E-05
1,83¥-38 0.0
1.43F-1%  €,0
T.34% 00 Z2,11R-03
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1.579-02 2,78F=-08
2.52%-07 2,51E-07
T.TER-0 6. 50F-07
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£.207=-%4  1,72B-1%5
H 2 0
H.202-14 1.728E-15%
2,77P-%4 0,0
6,207<14  1,728-15
1.28F=10 0.0
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AC227
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3.65%=09
1,928-05
1.25%-11
0.0

0.0

b, 018~ 11
3.557=-134
4.05%-09
3.28F-N6
u,86F=11
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2.22E-12
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3.978-05
2. 747=10
2.78E-3C
1. 828-11
t.651F- 10
170“’5“'-05
1.€97-09
9,09E-10
5.,398-08
9,352-05%
7.23E-10
1.86E-009
1.998-08
§.67E~05
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b.zer=-14%
b,24%-08
7.82E-05
2.29P-11
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€.557-10
2.06F-114
4,23E-08
'71‘15?‘05
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1.12%-04
7.53E-07
8.867-00
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BUBNTOP=

N THE WASTE ResuiTing Fra A MeTric Ton oF Uraniuv rarseD To A PR

REFEPENCF PWR EQUIITBRIC® FURL CYCLF -- WASTE DECRY TIMES

33000, M¥D, FLUA= 2,92% 13IN/CM**2-3EC

1. ¥
0.0
6.15E-09
1. 3LE=-05
10263'11

7.957-08
2.787-05
2. 16%~-10
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3.75F~ 11
2.702-10
S U5TF-L5
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1.327=09
3. G4F~-08
6.56E-05
1. 05F=-09
1.478-09
8.26?-08
5.08F7-95
9. 51F~-10
1.« 31E-09
6.OBE-1%
1.092'08
5.49%8-0%
2, 31E-11
B8.17E~10
5.19E-186
1.21F=09
1,037=09
3,52%=-14
£.92E-08
5,237-03
1.06R~09
5.83E=-07
8.74FE~-08
7.708-13
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5.62E=07
T.53E-07
0.0

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8.13E-C%

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0.0

0,0

b,127-11
1.63E-%3
1, 15¥=-08
1.18¥=-0%
T AuF-10
0.0

1.03F-11
1, 34F~-07
1.80%~-05
2.2072-10
£.517-10
1.01B-10
4, 5TF-10
2.74%-0%
1. 74F-00
2.137-09
1.51F=-07
3. 30F=05
1.69F=-09
7.50E-09
1. 407-07
Z.067-05
1. 33F-0¢
1. 13F~-1C
1.208B-027
2.76¥-05
2.35F-11
1.327-09
8,75E~- 16
1.23F-09
1.747-09
6.027-10
1 177-07
2.83F-0%
1.08BE-CY
5.85F-07
6.74F=08
7.738-13
0.0

5.,598-07
7.53%-07
0.0

4, 60%-04
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B.OSF~-13
2,58E-08
2. 03F-C7
2,68F-10
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2.458-08%
2.89E=-1%
1. 53r-09%
6. 1LE-D
1.027-09
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2.062-09
5. 008-09
3.388-07
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3.98%-0%
e 78?.“'09
3.137~07
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2,79F-191
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1.70€=-158
1, 467=-09
3.839=50
1,177-13
2.628-07
L.628-06
1, 28%-09
5. 9%2-07
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7.857-13
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30, Y
0.9
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6.60E-07
J.567=-11%
0.0
0.0
0.0
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Y,677-92
5.277-08
1., 137=-07
7.22%-10
0.0
2.967-10
£, 1!11:“-01
1.37%-06
E. CBE-10
a.13®-00
3.8%5%-09
2,09%-09
2,67E-05
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1.35F-08
6.90%=-07
3.,227-06
i,077-0R
4, bF-09
6.33%-07
2.987=-06
9,56%=-00
3.88¥%=-00
5. 1RE=1C
5. UgE-07
2.h9F=06
5. 517=141
§,.398-09
2. 86%=15
3,39E-09
7.95F%=09
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5. 3833807
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2,997-09
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0.0
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0.0
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5.76E~08
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€.977-07
L,50F-09
1.54F7-08
2. 367-08
3. 15%=-09
1, 35F=08
3.58F-08
S.04¥-08
1.0LBE-0%
1. 6UF-06
L,01E-08
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9, 8Ur-0"
1.52F-06
3. 607-308
2.737-08
T.80E-10
g.27F-07
1. 37F-06
4.828-10
3.131-08
30 OOE"‘i;
2,52F-08
1.20F-08
2.068-12
B.08®m-07
1.337-0€
2.227-08
9, 44F=-07
f.76F~08
9, u0FE-143
0.0

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300. ¥
0.0
7.54F-08
4, 91F-08
2.27F-09
0.0
0.0
0.0
7.24F-009
8, 36F- 08
9; ?"\‘OF"O(:'
1. LEFP-08
0.0
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2. 397-07
2,317¥-07
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2, 36¥-07
81 AOF- O—’
2.00F-07
B, 147-09
1. 708-07
b,12r-15
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2,BUF~13
B, LOF-0"
1.92F-07
1.90%7-07
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1.207-12

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B 9tE~-11
2. 5NE-08
0-0
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8.00F-08
2.6172-09
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b, 288-07
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1.98%-0%
3,50%8=-09
2.397-1C
3.38°=-0¢8
2.872-08
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fi. 38 E~-1F
2.3%97-206
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5. 75F-133
B, RIR=-07
2. 317=-10
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2,62F=12
0.0
5.59F-07
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0.0
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TALCULATIONS ARE BASED O aeMoving 99,57 oF U aND Pu FrOM THE SPENT FUEL AT 150 DAYS AFTER DISCHARGE,

3000. Y
G.D
8.63R-08
2. u"F- ‘!2
2,17e-07
0.0
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n.0
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1, 98E-08
9.57%-08
L.23%-13
1. 16E-08
0.0
1. 26B-06
1. 128-06
5.128-12
3.727-06
£,88%-04
1. E0R=-05
3. 79R-09
1. 0NR=-11
2, 9Lv-05
2. 987-05%
1.258-04%
1. 29P- 91
1. 73E-0%
2- SBP‘GS
‘ic 16?"06
1,327
1.55F-05
2.257-05
9,39%-130
9, 95%-07
1.012-1%
3.988-07
1.358=-08
2- 27?-—-1“
2.078-05
1., 445-08
9, 72%=-07
Y.656%~12
1. RRE-05
3.107-05
7.267-08
7.138-12
0.0
5.59F-07
8, 73%=-07
0.0
5.072-01
8.08%-06

TaeLE A-15, Isotopic TrervaL Power (W), AS A FimcrIon OF TiME AFTER PROCESSING, OF THE ACTINIDES AND TrEIR DAUGHTERS

10000, ¥

1,727=-12
6, 81F=-0%
n.n

7.35F-05
1,527 =06
2.087=-11
Jo04F-00
3.89%~05%
£,798-05
5. 18R-09
4, CER-11%
2. 7CF-0L
1.27F =04
T. 737 =0¢F
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1, 0P=-08
2.3237-01L
J.5RP=-DE
L,547-"%1
9,707=-065%
2., 07F=-0%
$.28R-09
1,387 =06k
h, 19T =11
3.68F-06
7,917-0%
a,23F-14
1,917=04
1,977=-08
£,36F~-12
1.,337-04
3.92E-11%
1.68F-0L
1, 0%7=00
9.%1%r-08
2,807-1%1
Nn.0

5.59F~07
1.19F-0%
0.0

5.07F7-04
£.08F-06

100000, ¥

0.0

8.95F7=-07
1.956F- 10
L, 65F-05

S22
DD O

1.U9%=-C1
9.16E-07
9.08F-07
2.57E-11
5.38F=-05
0.0

B, R1P=-08
$.052-05
3. 23E-10
T, 96F-0N
3.07E-0L
5.95F-00
3,587-08
£.31F=-190
f.29E-03
1.0%1E~-03
1. 1BE=-05%
T AP0
7,99%7-04
5.U2F-03
1. 098-05
7.35F-10
M. 48E-CU
4,B81F-03
R.B67=N9
9,39F-N6
5. 36F-10
B,52%=05
6,25F=-01
1.438-132
t,o88-073
1. 35E-07
9,868E=-11
%, 17E-05
6.09F-1%0
3.91E-013
6.23R-0L
2.78R=-07
4,50E-10
0.0

5.59E-07
8.,257-08
0.0

4,93%-04
3.08E-05

0gl
POWER=

pa23t
U232
U233
g23a
U235
U236
u237
p238
p239
uzud
¥p236
XF237
¥P238
¥E239
yp240H
¥p2u0
TH236
U238
PUZ39
a1 d OV
ji
Ty2u2
TU243
pU2L4
rU24%
rM281
L1H282H
242
anm2u3
AM20l
AM2u5
cH2u2
TH243
cMz2oy

BR24Y
BR250
CF2u9
CF250
Cr281
CF252
CFP253
Cr2su
F52%3
TOTAL

TaaLe A-16 (conNTINUED)

REFTERENCR PWP® EQUILIBHTUOM FUFL CYCLE -- WRSTE DECRAY TTIMES

CHLPGE
D.0
0.0
G.0
4,71E=02
1.96%=03

- - - - a - * - - . - - - - .
wn
I
|
D
LF%

» -
DCDC)Oflflfi)O%DQDO(DC)Q<3C3OCDC)OIDEDCZO-3(7C>C’O(BCBC)O<DCDC)O¢DC)O-JC}O

¢ o 90 e

a & ¢ B 5 8 & & B & &

mC)CJOCSCJCDOC)KPC!OtBC)fi)O‘DCDCDC)O(3<3<DC)C!O<JC>O(3C?CJC)OCJC}O\313<)C)&)O=D
O

¢ a s & & @

t
T2E-02

30,00MK, BURNUD=

DISCHARCGE

2.86F=0¢
1.20E~-06
6.,72F=~09
1, 09E-01
2,37p-08
3.917=08
8, 42E-06
3.978-0%5
CIC’
2.103‘20
2.35E-55
9.99”'03
2. 40%-20
2.468-02
2.738‘17
3.0
5.898~05
L. E8E=-01
5.02F=02
7.3fl?-02
13r=-02
2.0LE-0D4
1e79R-12
6001?‘19
0.0
5.307 GO
2.608=-03
1.228-02
b.637=01
4.19%-20
7|012’11
5,278 02
1.35E-01
B, 41E 01
1.078=02
2.24E-03
7.93%-09
I.DOE‘O7
1F-1h
1 0”‘?-
6. 27”-07
8,25E-158
1, 46E-07
1.38E-65
9.81E=-09
3.27E-06
59273-12
2.03B=-10
3.35%58-09
7.18E 02

33000. MV,

1. ¥
1.447~08
1.62F=06
5.37Fr=-08
1. 13E=-04
2. 37e=06
3.918-058
7.83r-06
30973‘05
0.0
7.618=18

4. 31V-05
2.68% 00O
3,028~-02
B.19E=02
2.04F¥-02
2,04E=00
3.58F=10
1.69E-16
0.0

5.317 00
2.5%E~-03
1e21¥~02
6., 63801
£.,90F~20
3,13F-11
1.33% 02
1.328-01
8.09f% 01
1.07E-02
2,24¥%~03
7.93E’09
1,008=07
3.028=-20
1.07%-13
2.8B0E-07
8:25E‘16
2.B0F=07
1.305~06
9.80E-09
2.513’06
3.533-18
3,10%=-12
2.53F=-11
2,23 02

BASTS

3. ¥
1.43E-D8
2,1%E-06
1.83F=07
1.28E-04
2,37®=-08
3.9?2-05

« 12F=06
3 97e-0F

-

w
4
1
Py
~

2 EC)DCDKJO
o
o
'
<
N

¢ a

U1OLR&JN«#@Lflu}w&).n”(fla(fih}@
°
< o

358 080
2.57F-D3
1.20E-402
6.63E~01
1.76%8-19
65.2L0E-12
5.21F 00
1. 27701
7.508 01
1,078=-02
2.2”E'03
T.938=-09
10002“01
1-35?'32
1.078-13
5.E58E-08
B.2U4E-15
3,65%-07
1117E-05
9,7BE-09
1.49E~-06
1.588-30
7. 1BE-16
6.,62F<25
9,07F 01

FLUX= 2.92F 13N/CH*%2-SEC

300. ¥
1. 43P-08
1. 83F-07
1. 30r=-05
1.117=-03
2. 3%9F-08
L,10%~058
5. 32E~-06
3,977~ 0%
¢,Q
2‘21F-15
0.0
1.04F=02
.0
2,397-02
13?5E_1u
[

1. 12F=38
5, 18P=-01
5.868=-02
2.67E-01
1. 3%F-05
2. 19E-0L
3.538%-10
5, 087=-10
6.0

3.65E 690
6.627-054
3,10%-03
6, 8ZF=-01
1. 76717
&, ¢

T,038-02
2,03F-08
8, 60F=-08
1. 0BE-02
2,15%-03
7.93F-09
1, 00F=-07
0,0

1. 05E=13
G.0

8315E“16
2, 16F-07
1.75F=-13
7. 7BE=(9

U1 T O
- PP D

.
-
‘e
*
-

1000, ¥
1.83%-08
2. 172=10
4b,u458-05
1,278=-03
2.L2F-06
b.55E-05
5101?‘09
3.978-0%
0.9
7, 58E~- 15
G. 0
1.08E-02
2.0
2, 20F-02
3.828=-14

o
0‘3

BQW’C?
:378-02

d.LS? ¢1
1. 31E=-05
2.26R-01
3. 58F=-10C

m~JQ<3

1. 688=-13
O!O

14 20F 20
2.728-05
1. 28E-04
6.66?‘&1
5.878~17
0,0

2. 898-03
5.28F-11
2, 23E-15
9,86F-03
1.90E-03
7. 938=-09
1.00E=07
0.0

1, 037-13
G.0

7,928~ 185
5.E3E=-08
3031E'15
4, 54r-09
6.0

0.0

0.0

0,3

2, 17 00

NOCLIDE THYRM2AI DOWRER, WATTS
= MT OF HERAVY MTTRY CHA®GED TO PFACTOR
10. ¥ 30. ¥ 100, ¥
1. 03808 1.83%¥-08 1,83%-08
2.807=06 2,URF-06 1, 25F=06
4.LQE~-0T7 1,20F-06 4,28F-06
1.82%-04  3,22%-04 46,80E-0L
2.378-06 2,378-06 2,3BE-06
3.91E~-05 3.92%¥-0% 3,9€E-0F
5, 11E-06 1,98%~-06 7,A5E~-08
3,97%-05 3,97%8-05 3,97%-05
g.0 8.0 Q.0
7.598=-17 2,28%¥-15 7,5BF-16
0.0 8.0 0.0
1.00%-02 1,00%=-02 1,01
0.0 0.0 Q‘O
2,458-02 2,058-02 2,437-02
3.83F-16 1,15%=-15 3,83F=15
0.0 G0 0.0
,828-06 3,72E-08 1,80P-15
3,088 00 2,.87% 90 1,62% D
5. 06E-02 5,.07F-02 S, 18F-02
1. 38F=-0%  2.118=-D1 2 68F~01
1:33E°02 ga15E-D} ng‘fi&
2.058=00 2,067-0L 2, 11F-Qu
3.58%=-16 3,3RE-10 3, 58%-1D
1. 68%¥=-15 5,0%5%¥-15 1, 68BF-14
0.0 0,0 0.0
5,837 00 5,47% 00 5,02F Q0
2,498-03 2,27¥-03 1, 65F=-03
1, 17802 1.06¥-02 7.73F-~-03
s 63801 6.61E-01 €,57P~09
5.88%-19 1,76P-18 5,88%=18
2:21E=-14 2, 19%-2% §.0
2.688«01 2,41E-01 1, 75E-CH
1.09%-01 7,058-02 1,55E-02
5,738 01 2,66% 01  1,83F 00
1. 078=-02 1.07%-D2 1.06F-02
2, 24F-03 2,2372-03 2,21F-03
7.938-09 7,93E-09 7,93F-09
1.00E-07  1,00F=07 1,00F-07
Q.0 0.0 0,0
1.07E-13 1.487P-13 1. 0BE-13
1., 98B-10 1.982-17 0.0
8,24B=18 B,28Y-16 8,21F=16
3.818-07 2,67¥-07 3,208-07
B.098-07 2,.80%-0"7 £,87E-09
9,73%-09% 9,.58¥-09 ©,08E-DC
2.38E~-07 1. 26fi°09 1. 37817
0.6 0. 0.0
1.36F-28 Oufl 0.0
0.0 0.0 n,0
6.71E 01 3.61% 01 9,69F 00

30000 ¢
1, 43F-08
9, L18B-19
1.372-04
1.26E-03
2. 56E~-0F
5.&65E-05
4,2tE-09
3. 97E-05

.
~2
tad

<
Lfl
1 i
o —a
b2 =2

O{Dafldfib—flCJM~9
-
Oc}*twf)dtjmja

m~ 02
B-13

m~4'

5, 0Uv=-13
G.0

5.75%=-02
2.978-G9
1.398R-08
5. 05E=01
T. 76818
D0

3. 17w-07
9., 06%0=30
B, 26F= 1A
8.33%-03
1. 44%8-03
7.93E-09
G,88%-08
0,0

9, 47g- 10
0.0

?0322‘16
1.06E‘09
3,0688=1%
9,738~-10

10000, ¥ 100000, ¢
1.43%-0R 1,037=-08
0.0 0.0
b,55E-04 3, 75F-03
1,248=03 <,73E-04
3,23F=-0F 9.79F-08
8.24%=-05 1,08BR-04
2.357=-09 1,24F-12
3,.979-0%  3,97E-05
6.0 0.5
7.51F=-14 §/,88%=13
.0 0.9

1. 10F=02 1.07E-C2
0.0 .0
9,92%-03 2,BS5E=05
3,787-13  3,47F=-12
C".O 0.0

0.0 G.0
9,3RF-2% L.
1.28F=01 1.80%~-02
Q,87F-02 O,83FE-08
£, 1ur-08 3,23E-09
2,308 Z2,078-0u4
3.878-10 3,58F=10
1,87P=92 1,5838=-11%
0,0 .0
R,otw-(:3 2,74E-06
L,06%-23 0.0
1.80%-22 6,0

2, 68F=-01 7,708-05
R.82r=-16 5,337-1%
fi.o 0.0
4,33P-2% 0.0

0.0 0.0

2. T3F=-15 2.51E=- 14
L.3F=-03 2.LL¥-04
5.15%8-0D4 2,13F=-10
7.93F-00  7,90E-D9
9,8%8-0N8 §,25F=-08
6,0 0.0

7. 16E=-%8 1, QQE—15
0.0 0.
E.S4F-1486 1, 53fl-fl7
1.097-45 0,0
2.31P=15 B, 481E=17
4,u57=-12 0.0

0.0 .0

0,0 0.0

9.0 0.0

6.0 n.o
5.30F7=01 6,53F-02

1£1
TaaLe A-17, Swmary TABLE OF THE RetaATIVE INHALATION HAZARDS OF [SOTOPES OF THE ACTINICE ELEMENTS AND THEIR DAUGHTERS

THE RELATIVE INHALATION HAZARD 1S DEFINED AS THE VOLLME OF AIR (M) REQUIRED TO DILUTE THE RADIGACTIVITY [N WASTE TO
THE 12VELS GIVEN In TapiE 1T, Coiwmn 1, oF 10 TFR 20, NUCLIDES WHOSE HAZARD MEASURE IS LESS THAN I M3 OF AIR AT A
TIME AFTER PROCESSING 0F 30 VEARS ARE EXCLULED,

RFFERENCE PRP FQDIITRRIOM FUEL CYCLFY -~ HASTE DECAY TTNMFS

POWEP= 30,00MW, BURNUP= 33000.K¥D, FLUX= 2.92F 13N/CH**2-SEC
HUCLIDF IT¥HAIRTION HRAZRTD, M**3 OF RIR AT PCG
BASIS = T OF HYAVY MFTAL CHARGEY TOD REACTOR
CEAPGE TISCHAPGE 3. 1 30, ¥ 300, Y 3000, T100000, Y
ac227 0.0 1.62% 07 4,31F 07 1.97E 8 3.%13E {8 3.58% 08 3,38F 09
TH227 0,0 1.23F 05 3.40® 05 1,557 C6 2,47E 06 2.82F 06 2,67% 07
TH228 (.0 7.58% 09 2,68% 09 2,627 08 1,95E 07 9.83%F 02 6,207 04
TH229 0.0 1.75% 06 1.79% 06 4,94% 0% 3.15%F 08 3.02F 10 6,47F 12
TH230 0,0 2.5BF 08 2,%9F 0B 2.82F 08 1.313F ¢9 1.37F 10 2,.75F 1%
Pr2317 0,0 £.17E 08 6,17E OB 6, 18F 08 6.26F 08 7.756F (8 6§,76% 09
P2233 0.0 1708 07 1.70F% 07 1.T7T1® 07 4,77F 07 1,88% 07 1.83% 07
U233z 0.0 1.25% 07 2,278 07 2,55F 07 1.90% 05 9.787-06 0.0
0233 4.0 1. Y57 04 2,L6F 05 2,22F 06 2,237 D7 2,35F 08 §.4FE DG
t23: 8,187 %0 1,R9% ©8 2.23F 0B 5.59F 22 1.93F 09 2,19E 3¢ 1.69% 09
U235 31,54F 0% &,2BF 06 4.29F 06 u4,28F (& u,30F 06 L.61F (6 ¥,76F 07
7235 €.0 T.291F 07 7,218 07 7.23% 07 7.%6F 07 1.08%% 0B 1,.98F 08
U238 1,077 1% 5,287 0B 5,24E 08 5,24F 08 5.2UF 08 5,247 DB 5,28F 0OF
¥F237 0.0 3.40F 12 3.40F 12 3,428 12 3.5u4% 12 3.75E 12 3.65% 12
¥P239 0,0 £.DBEF DB 6.CF5F (B £,04F DB 5,897 08 L, 671F 0B 7,03F Ot
PU236 0.0 2.53€ 09 1.27F 09 {.7BE 06 5.368-23 0.0 0.9
PU238 C.90 2.02F 14 %,38F 15 1, %15F 15 41.79E 14 2,98F 08 0,0
PU239 C.0 2.6GE 13 2,69% 13 2,728 13 2.93F 13 d4,B68F 13 9,837 12
PU24¢ 0.0 3. 98F 13 5,LF 13 1.,13F 18 3.43F s 4.08F 14 S5.18F @9
PU24%Y 0.0 T.79F 14 4, 89% 94 4,367 13 3, tiF 1t 8,.87FE 10 2,.60F 07
BPR2E2 0,0 .95 11 1.15E 11 1. 16F 11 1,288 11 3.30F 11 1. 17" 11
AMZHT 0D 7.93% Y4 3,0%F 10 8.20F 18 S5, 47F 48 R,62%7 12 L, 117 08
BW222% 0.0 4,578 13 4,%1® 13 3.99F% 13 1, 16E 13 5,237 07 0.9
AM242 0.0 9.14F 09 9.028 09 7,98F G9 2,337 09 1.05F Q04 0.0
ER2E3 D.0 9,088 13 9,08% 13 9,08F 13 8,84F 13 6,92F 13 1, 05F 10
cx2L2 0,90 4,25° 1% 4.2%E 13 1.63F 312 O0,77F 11 2.15F 06 0.0
cH243 0,0 1.84F 13 §.72F 33 9,59F 12 2,77F 10 1, 109F7-15 0.0
cH2uk N0 B.0%F 1% 7. 34E 1% 2,54F 15 §,20F 10 7.87F-02 2.39% 00
crK28S 0,0 1.73E 12 1.71% 12 1. 70F 12 V,65F 12 4,337 12 3,89% 08
cw2u8 0.0 ALE2F 11 ILL2R Y ILLOF 11 3,27F 3 20208 19 1.39% (5
£x247 0.0 1.,26% 06 1,267 06 1.26F 06 1,26F U6 1.26F 06 1,26% 06
TM248 0.0 3.95% 07 3,96F 97 3,96E 07 3,95F 07 3.93F 07 3,25% Q7
Cr2u49 0,0 T.80F 07 1.86F 08 1,86% 08 1,710F 08 S5.38% 05 0,0
CF250 0.0 1. 8UF 28 1.%57F 08 3.76F (7 2.38F 0% &, 70%-071 8.59F-03
CF2%% 0.0 £,57P Of u4,56% 06 t,LEF 0F 3,62F 6 4.53F 05 &.0
SUBTOT 1.,93FE 11 .37 16 9.75% 15 4, 84F 15 1.00F 18 2,38F i 2,02F 13
TOTALS 1.937 91 1,37E 16 9.75F 35 &, 8u4F 15 1.,00F 15 2,38F MW 2,.02F 913

Zel
Tapie A-18, Suwvary Tasle oF THE ReLaTive IngesTion Hazarns ofF IsoTores oF THE ACTINIDE ELEMENTS AND ThEIR DAUGHTERS

THE RELATIVE INGESTION HAZARD IS DEFINED AS THE VOLWME OF WATER (M3) REQUIRED TO DILUTE THE RADICACTIVITY IN THE WASTE
TO THE LEVELS GIVEN IN TasLe I, CoLtmn 2, oF 10 CFR 20, NUCLIDES WHOSE HAZARD MEASURE 1S LESS THAN 1 MO OF WATER AT
A TIME AFTER PROCESSING OF 3 YEARS ARE EXCLUDED,

REFERENCE PWR FQUILIBRIOM FURYL CYCLE -~ YASTF DECAY TIMES
POWEE= 30.00MW, BURNUP= 33000, H¥D, PLUX= 2.92F {13N/CM**2-5RC

NUCLIDE INGESTION HRZARD, Mx%x3 CF WATER AT ©LG

BRSTS = MT OF HEAVY METAL CHARGEDT TO RTACTOR

CHAPGE DISCHARGE | 3. ¥ 30, ¥ 300. ¥ 3000. Y100000. Y
NP237 0.0 1.13% 05 1,13E 05 1. 14E 05 1.18F 05 1.28F 0% 1.22% 05
¥Pz39 0.0 1.82F 05 1.82% 05 1.81F 05 1,778 05 1,38E 0% 2,118 01
Pu238 0,0 Z.8B2E 06 1,98E 97 1.61F 07 2.50F {6 &,15% 00 €.0
Ey239 ¢.0 3,23F 05 3.23E 05 2,26%® 05 3,52F 05 5.57% 0% 1, 16® €5
puza80 0,0 4,77F 0% B,17% 05 1.35F 06 1,71T {6 1.30F 06 &, 22F% 01
P21 0.0 2,57 06 2,23% 06 £,20F D5 1,€67F 03 1,33F 03 3,90F-01
Anm241 0.0 3.97% 07 4.C19 07 4,10E D7 2.73% 07 4,31% 05 2,067 01
am2u2om 0.0 2,29E C& 2.26% 06 1.99F 06 5.82F 05 2,61E 00 0.0
RmM2L2 0.0 9. 14F O 9,02E O& 7,987 G4 2,33%F 0k 1,05F-01 0.0
EM2L3 0,0 L,54F 06 L,S4R 06 B,53F 06 4.42T% 06 3,86F 06 5,278 02
cw2e2 0,0 B,51F 08 8,428 06 3,27F 05 9,58F Q2 4,30FP-01 0.0
cM2t3 0.0 7.35E 05 6.89%9F 0§85 3,84% 05 1,11F (3 &,39F~-23 0.0
cHMz4t 0,90 3.43F 08 3,.06F 08 1,098 08 3,51F 03 3.37F-09 1,02E-07
cm2es 5.0 8.54F O B.S3E 04 B,52F 04 8,32F 04 6,647 (4 1,9LE 01
cMz2a8 0.0 1.71F 04 1,71 048 1.70F O 1,6BE 04 1,10F 04 6,95F-013
SUBTOT 0.0 1.25F 0% 3.8%E 08B Y., 76F (8 3,74% 07 6,09% 06 2,38F 05

TOTALS 6,50F 04 1,257 09 3.BSE 08 1.76F% 08 3.74F 07 6, 12F 06 1,86F 06

£el
TaBLE A-19, SuvmaRy TASLE OF RADIOACTIVITY OF THE FIsSION PRODUCTS AS A FuMCTioN OF TiMe AFTER ProcESSING
MuCLIDES WHOSE RADIOACTIVITY EXCEEDS 0,001 C1/METRIC TON OF U CHARGED TO THE REACTOR ARE INCLUDED. IT IS
ASSUMED THAT, AT THE TIME OF PROCESSING, 1007 OF THE X& AND KR IN THE WASTE IS REMOVED,
PEFTERFNCE P¥FR EQUITLIRBPIUM TOFLI CYCIE -~ WASTE DECRY M™THES
PAVER= 30.00!“, BURNG P= 33000.M¥D, FLUX= 2,92F% 13I/CH**2=SEC

NUCLIDE RADIOACTIVITY, CUPTES

Bi5TS = BT OF HERYY ¥ETAL CHARGEL TO PEALTOP
CHBAFGE DISCHARGE 3. ¥ 30. Y 309, ¥ 2000, ¥Y100000. %
g 3 0.C 5,917 02 5,84F 02 1.27F7 02 3.14%-05 0.0 0.0
SE 79 0.0 3.98B-01 3.987-01 3.98F-01 3,97%-01 3.867-0% 1,37%-01
sr 9C 0.0 7.687 04 7,13F 0L 3,667 O0U B,.A9F 0% S5,5ur-28 0.0
T 90 0.0 J.68E CL 7.%3F 04 3.66F 08 U4,69F 0% 5.54r-28 0.0
Z? 93 0.0 1.89E 00 1.89F 00 .3¢% 00 1.89% 00 11.B8F 060 1,80F 00
EB 93% 0.0 1.838-01 4,288-901 9,52% 00 1.89F O0 1.88BF 00 3,807 0O
TC 99 0.0 1.437 01 9,437 01 1.83F 01 1,437 01 1,827 0% 9,037 01
D107 0.0 1 10F=01 1, 108-01 1.10F-01 1.107-0% 1,107-0% 1,NAP-014
Cptiim 0.0 1.037 071 8.86F 00 2.33F GO 3.64F-06 0.0 0.0
5BI25 0,0 7.89E 03 3,H5E 03 3,56F 00 0,9 0,0 G.0
TFI25M 0,0 3.%9E 03 3,5%F 03 1.487 90 0,9 2.0 .0
sS¥126 0.0 5.467-01 5, 4€E-01 5.46F-01 5.85E-01 5.3%E-0% 2,73E-01
Ssi126m 0.0 S5,48P=01 5, 86P-09 S5,L6P-01 5, 86F-01 5,35F-01% 2,73%-01
SB126 0.0 5,43E-01 5.449%~01% 5,8%8-01 S.LOE-09 S5.30F-01 2.70F-01
Ti29 0,0 3.747-02 3,78F~02 3,7LF-02 3,78E-02 3.74F-02 3,73F-02
csi3t 0.0 2.%2F 05 7,70% OU B.LCGF 00 0,0 n.0 0.0
€s125 0.0 2.867-01 2,85F~01 2.86¥%=-01 2.86E-07 2,B6F-01% 2.807-01
£8137 0.0 1.07F 05 9,98F CO4 5,347 04 %,04FR 02 8,37F-26 0.0
BR137M 0.0 9.38F 04 9,318 G4 4,997 OHU 9,75F D1 7,.B2R-28 0,0
PHILT 0,0 2.73F 04 4,uQ% €4 3,477 G171 0.0 0.0 0.0
5¥151 0.0 1.25F 03 t,22% 03 9,837 02 1.,14% 02 5.23%-08 0,0
U152 0.9 1.227 01 1,03E 01 2.18% D0 3,6LE-07 2.0 0.0
RUI5L 0.0 £.86% 03 6,02E 03 1.87% 03 1.55F-02 €.0C 0.0
¥U1S5 0.0 £,33% 03 2,01E 03 6,u8F=-02 0.0 0.0 0.0
SgRTO™ 0.0 6,967 05 4.7%" 05 1,.BOF 0% 4.30F% 02 2,04% 01 1,537 01
TOT2LS 0.0 L 1AE OB 6,77F N5 1, 80F 05 4,308 02 2,04F 07 1.53F D4

FEL
Taste A-20, Suwaary TapLe oF RewaTive InmaLarion Hazaros oF THE Fission PRODUCTS In THE WASTE RESULTING FROM A
MeTric Ton oF Urantum CHARGED TO A PR

RELATIVE INHALATION HAZARD 1S DEFINED AS THE VOLWE OF AIR (3) REQUIRED TO DILUTE THE RADICACTIVITY IN THE WASTE
To THE LEVELS GIVEN IN TaBLE 11, Coui 1, oF 10 CFR 20, NUCLIDES WHOSE HAZARD MEASURE s BELOW 106 M3 oF AIR AT
A TIME AFTER PROCESSING OF 30 YEARS ARE EXCLUDED., IT IS ASSWMED THAT, AT THE TIME OF processing, 100% oF THE KR
AND XE IN THE WASTE [S REMOVED,

REFPEFENCE PWE EQUILIBRIUM FUEL CYCLE -- WASTE D¥CRY ™IMESR
POWER= 30.00MW, BURXUP= 33000, ¥WD, FLUX= 2,92% 13N/CH**2+-SEC

WUHCLIDE INHRALRTION HRAZAF®D, WM¥%3 OF RTE BT PCG

BASTE = BT OF HERVY METAL CHARGEL TC REACTOR
CHAPGE DISCHARGY 3. ¥ 3¢, ¥ 300, ¥ 3000. Y100000. Y
8 3 0.0 3,86E 09 2,928 09 6.37F 08 1.57F (2 0.0 0.0
SFE 80 0.0 2,58¥% 15 2,38F 15 1,227 15 1,56F 12 1,8%E-17 0.0
Y ¢ 0.0 2.56% 13 2.38F 13 1,22F 13 Y, 56F 10 1,85%-19 0.0
ZR 93 0.0 4,727 08 L.72F 08 4,72F 08 4,727 08 4,71F 08 U, 50F 08
NB Q3% 0.0 4,578 67 1,067 08 3,79F 08 4.72F 08 4,.7%R 08 4,50F 08
TC 99 0.0 7.178 69 7,17% 09 7,17F 09 7.16E 0% 7.10F 09 5.17F 09
RUI0E Q.0 2.01t= 15 2,58F 14 2,.07F (6 0.0 0.6 0.0
SB125 0.0 B.77% 12 4,06F 12 3,967 09 0.0 .0 0.0
TE125M €.0 7.977 11 3.79F% 1% 3.69F 08 0.0 ¢.0 0.0
T129 0.0 1.87F 09 1,87F 0% 1.87F 0% 1,87F 09 1.B7E 09 1.826% 09
cs138 0.0 5.31F 186 1, 93F 18 2.10F 10 0.0 ¢.0 0.0
€8135 0.0 Q,55% 07 9,54F 07 9.54F 07 9.38F 07 9.353F 07 9,.32% 07
€5137 0.0 2.13F 14 1,99E 14 1.07F 14 2.068% 11 1,67E-16 (.0
PHTLT 0,0 4,878 13 2,20E 13 1.74F 10 0.0 0.0 .0
S¥ist 0.0 6,247 11 £.09F 11 4,91F 11 5,72E 10 2. 61F 01 0.0
EU152 6.0 3.06% 10 2.57E 10 5,40F 09 S.097 02 0.0 0.0
9154 0.0 £.86F 13 6,028 13 1,87F 13 1. 55E 08 0.0 8.0
FU155 0.0 2.11E 12 6.69E 11 2. 16% 07 0.0 0.0 0.0
SUBTOT 0.0 S.57E 15 3, 13E 15 1,36E 15 1.85E 12 1.00% 10 B, 03® 09
TOTRALS 0,0 1.01% 16 3,39% 15 1. 36F 1% 1.85F 12 1.00F 10 B.03F 09

Ggel
TagLe A-21, Susary TABLE oF RELATIVE INGESTION HAZARDS OF THE F1SS10N PRODUCTS IN THE WASTE RESULTING FROM A
VETrRIC Ton oF Uraniwm CHARSED TO A PWR

RELATIVE INGESTION HAZARD 1S DEFINED AS THE VOLLME OF WATER (M3) REQUIRED TO DILUYE THE RADIOACTIVITY IN THE
WASTE TO THE tEVELS GIVEN iN Tasie {i, oLty 2, oF 10 CFR 20, MNUCLIDES WHOSE HAZARD MEASURE 1S BELOW 1 MO oF
WATER AT A TIME AFTER PROCESSING OF ) YEARS ARE EXCLUDED, [T 1S ASSWMED THAT, AT THE TIME OF PROCESSING,
1007 oF THE KR AND XE IN THE WASTE IS REMOVED.

FEFERENCT PHE FQUTLIBRIUK FUORBY CYCLP == WASTP DFCAY TTHMERES

POWER= 3C.00MW, BURNUP= 33000.94D, FLUI= 2,928 13N/CH**2-35FEC

NUCLIDE INGESTTOK HAZAPD, M*%3 0OF HATER a™ ¥CG

ERSTS = MT OF HEAYY MFTAL CHARGET ™0 PFACTOR
CHAPGE DISCHARGE 3. v 30. ¥ 300. ¥ 3000. TIO00D0O0, Y
H 3 2,0 -3CE 05 1,9E5F 05 BL,25F 4 1,05E-02 0.0 C. 0
SP 90 0.0 2,5€% 1% 2,38% 11 1.22% 11 1.56F 08 %.85F-21 0.0
Y 90 0.0 3.84F 09 3,57% €9 1,837 09 2,35F 06 2,77F-23 0.0
T™C 99 9.9 To17E 0L 7,377 0t 7.17F LU TL16F Q08 7, 30F 04 S, 17F 04
SBi125 0.0 7.89E 07 3.65% 07 3.36F 08 0.0 G. 0 0.0
TE125M 0,0 3,192 07 1.518 07 4.UBF 0 0.0 .0 0.0
T129 0.0 5.24F 05 6,2L7 DS €,28F 0% 6,24% 05 6,288 05 6.217 05
cs13s 0.0 2.36F 10 8,%56E 09 9.323% 0% 0.0 0.0 0.0
cs137 0,0 5.34F 09 4.98% 09 2,€7F 09 5.21F 06 4,1318E-21 0,0
BR137k¥ 0.0 9.,98F 04 3.21F 0L 4,997 Qu 9,75% {% 7.82F-26 0,0
PM1UT 0.0 L.87E 08 2.20E 08 1.74% {5 £.0 0.0 O,
38157 6.0 3.12F 06 3.C8E 06 2.U6F 06 2,867 €5 1,317=-04 D.G
ED152 0.0 1.53F 05 1.,28E 05 2,70F Ob 4,552-C3 0,0 0.0
Ep154 0.0 3,437 08 3.0G18 08 9,38F 07 7.77F 02 0.0 0,0
sSyBTOT? 0.0 2,80F 31 2.55E 11 1.27F% 11 1,65FE 08 6.95F 0S5 6.73F 05
TOTRLS (.0 L.u9% 19 2,66F 11 1,277 11 1,65% 08 T7.05F OG5 6.83F 05

?¢el
THEAN

(M7V)
3.00F-01
6.30E=01

Tagte A-22, Twewve-Enerey-Growp PHoTon SPECTRUM AS A FUNeTIoN oF TIME FOR FISSION PRODUCTS IN THE HASTE RESULTING
FROM A METRIC ToM OF Uranium CHARGED TO A PWR

[T IS ASSUMED THAT, AT THE TIME OF PROCESSING, 1007 oF THE KR AND XE IN THE WASTE IS REMOVED,

REFERFNCE PWR EQUILIBRTUM FUFL CYCLE -- WASTY® DECAY TINES
PORER= 30,00 #%, BURNUDP= 33000.M¥D, FLU¥= 2,928 13 N**2-357C

TY¥FLVE GROUF PHOTCN EFELERSE RATFES, PHOTONS/SEC

1I1OE
1,558
1. 99F
2,38F
2.75%
3.25¥%
3,70F
b,22¥%
L.70E
5.25%

00
oe
00
00
o0
00
00
G0
oe
00

TOTAL

MEV/SEC

E¥EAN
(MEY)
3- DOE-
6.308-
1. 108
1. 55%
1.99%
2.38E
2.75%
3,258
3,708
L, 228
4,70F
5.25%

ToT

GAMMR WATTS

01
01
oo
00
oe
00
00
00
00
00
0¢
00

AL

BASTS = #7 OF HERVY METAT CHARGED TO RERCTOT

IRTTIAL 1. ¥ 3, Y 0. ¥ . ¥ 100, ¥ 300. ¥ 1000, ¥ 3000. Y 10000, Y
8.00F 15 3.U41F 15 8,312 14 1.70F 16 9,78% 13 1,727 13 1,48F 11 6.36F 09 BH.2%F D0 5,967 [¢
6.20% 156 2. 14E 16 1.14% 16 3,87% 15 2,00 15 3,91E ¢ 3,90F% 12 7T,.51E 10 7,408 10 7,05% 10
1.507 15 8,.51F 1& 3.69E 1¢  1,32F 18 5,267 13 2,97¢ 12 &,718 09 ©,u6F 05 2,98® 05 5,.22F 03
5,188 18 2,86% 1% A.10F 14 9.1%F 12 A.34® 11 1,10% 11 2,u43% 09 1,65F 0% 1,53% 0% 1.35F 00
2,66F 14 1.12F 14 2,037 13 Q.6%F W 1,848% 10 3,28F 09 2,38F 07 7T,u7P-01 2,79%-22 0.0
2,687 13 1.317 13 3,277 12 2.57F 1 2,60% 04 2,7€r-17 0.0 0.9 0.0 0.0
2,018 12 1,09% 12 2,%3F7 1% 2,02% 09 2,0%E 03 2.18°P-18 0.0 0.0 ¢.0 0.0
6.33F 10 3.17E 10 7.9%E 0% 6,398 07 6.50% 01 A.91E-20 0,0 0. Gu0 ¢.0

0.0 0.0 0.0 ¢.0 0.0 0.0 0.0 .0 0.0 0,0

0.0 .0 g.0 0.0 .0 0.0 0.0 0.0 0.0 0. ¢

6.0 0.0 0.0 £.0 0.9 .0 0.0 B.C 0.0 0. C

0.0 6.0 0.0 0.0 0.0 g.0 0.0 0.0 .0 2.0
T7.83FE 16 2,61F 16 1.2BF 16 U, 188 15 2,1%8 15 L,11F 14 u,05®% 12 8,31F 10 8.1%% 10 7,807 10
4.58F 16 1.62F 16 8,09t 15 2.6%® 15 1,357 1% 2,55% 14 2,51F 12 5.18% 10 S.,10F 10 4,86F 10

TWELVYE GPQUP ENTRCY RELEASF RATES, MEV/WATT-SEC
BRSYS = ®T OF HFRVY METAL CHARGED TO BRACTOR

THNITTRL . ¥ 3, ¥ W. ¥ 30. Y 100, ¥ 300. Y 1600. Y 3000. ¥ 10000, Y
8,008 07 3.41E C7 B.S1E 06 1,70R 086 9,7UE §S 1,727 05 1,BLF 03 6,.36F 0t 6.25F CG1  5,.96F 0%
1.34% 09 a,50F 08B 2.L0E 08 8,128 07 &£,20% 07 B,21F 06 8,18% 0L 1,58F 03 1.36% 03 1, 48T 03
5.64% 07 3.12F 07 1.35FE 07 &.83r 06 1.938 06 1.09F (5 1,73F 02 3.4877-02 1,09P-02 1,927-0n
2.688 07 t.u48F 07 35.70F 06 2,752 0% 3,28F OU 5.6BF 03 1.26E 02 B8,52F 01 8,L0% 01 8.01F 01
1.77E 07 7.42F 06 1.35F 06 6.38E 03 1,228 03 2,.17F 02 1.57E 00 4,957-08B 1,8%5E-29 0.0
2.12E 06 1.0QUE €6 2,59 05 2.04%F 03 2,06%-03 2,19E-24 Q.0 0.0 0.0 0.0
1,847 05 9,22 O4 2,32E D4 1.,85% ¢2 1,8B%-00 2,00E-25 0.0 0.0 0.0 8.0
6,867 03 3.84F 03 8.65F 02 6,928 00 7.04%=-06 7,89%-27 0,0 0.0 ¢.0 0.0

.0 0.0 0.0 0.0 0.0 0.0 3.0 0.0 0.0 0.0

0.0 0.0 0.0 .0 0.0 0.0 0.0 .0 0.0 0.0

0.0 0.0 0.0 G.0 0.0 0.0 4,0 .0 0.0 0,0

8.0 6.0 0.0 0.0 0.0 0.9 0.0 0.0 0.0 0.0
1.53% 09 S5.38F 08 2,70F 08B 8,82F 07 4,497 07 8,50F 06 8.,36F O 1.73F% 03 1.70F 03 1.627 D3
7.38F 03 2.59F 03 1.30® 03 4,24® 02 2.16% 02 4,09% 01 8,02r-01 8,3DE-03 B,18R-03 7,79F-03

100000, ¥
3.272 09
3.78% 10
0.0
8,307 08
g.0
0.0
n.C
0.0
0.0
g.0
0,0
0.0
4,198 10
2,81%F 10

100000, ¥
3.272 01
7,947 02
0.0
L,29% 01
0.0
O.D
0.0
8.0
0.0
0.0
0!0
0.0
B,5%E 02
8,18%=03

£E1
BIZ291%
BT212
BT213
20210
PO211
PO242
0213
0295
20215
PO215
EO218
AT217
RE219
?N220
FN222
¥r221
r2223
PA224
RR226
12225
ac227
227
TH228
my229
TH230
TH232
PR231

U232

w233

7230

U235

G23fF

U238
NP237
U235
FU233
Pr23¢
PU2u9d
U249
U242
pu24at
AMz2uy
EM243
cM2i42
cM213
cM2Ll
cM285
CH2LG
CcCK247
CH248
BK249
Cr249
cT250
CF251
CF2582
CF253
cr254
P5253
TOTAL

Tapte A-23, NEUTRON SOURCE. AS A FUNCTION OF TiMe AFTER PROCESSING, FOR [sOTOPES OF ACTINIDE ELEMENTS PRESENT IN
T WaASTE ResuLting From A MeTric Ton ofF Uraniwv CHARGED 76 A PR

[T IS ASSLMED THAT, AT THE TIME GF PROCESSING. 99,57 oF THE il AaD PU IN THE WASTE 1S REMOVED,

INITIRL
4,318-03
a.Sl‘E‘E‘O.‘
3.2uF-09
G Uer-07
2.057-05
1.61% 01
2. 95?'0‘4
1.,287=-04
6.64F-03
9.76F 00
SOUBF-OS
?.63E-Gfi
4,98%=-03
7.39% 00
I.TIE-05
';u OE“E—GQ
2.858=-03
f.0N3% 00
2.22E-05
T.8LE-05
8- 32“" ‘32
2.797-03
4,337 00
b,86%-05
2.28E-02
1.997-08
3.61%-02
£§.,577-02
Z‘SHF'Ofl
b.86% 00
8,85E-02
T.37F 00
1.96T GO
u,33% 02
3737 09
Z.79F 0%
2.53F 03
3.77F 03
6.239-10
8,957 00
2.24E-b
3.22T% 05
5.12E {0
€,95% 07
1. 068 Ok
3.79% 085
5.54F 02
1,307 02
fio 1 1F—Oa
1.%3E-01
1.,327-12
1.38F=-02
1. 11E~-01
-,t 15F7=004
1.518 00
2.87F- 1L
4,578-04
3029E‘0fl
5.58E 07

1. ¢
7.25%=03
1.0BE=01
3.26E-09
1.958~06
3. U58-05
1.13% 01
2.97F-08
T B3E-0L
T.12E-02
6.85% 00
7\90T‘05
106“E'0u
B8,378~03
5.91%E 00
5,37%~05
1.06F=04
4,79%7=-03
3.582 00
3.21E~05
7.%0E-0%
1.31E=11
L,E78~-03
3,028 Q0
8,087E=05
2.28F=-02
1.99F-08
3.67E-02
E,.668-02
2,27F=03
4,658 00
B.BRE-D2
1,37 00
1.%6E 00
L,33% 02
2,928 00
1.608 05
2.53F 03
a4,%%® 33
5.948-10
8.95% 40
6.297-12
3.23F 05
FL.11R 0L
1.08F 07
1.04% Ot
5.587™ 06
5.54% 02
1307 02
b, 19e-04
1.93=2-01
5.89F-13
2.63E-O2
1.06F=-01
7.98®=004
1.178 0D
1.92E-20
6.962-06
2.58E=-09
T.6ER 07

ARFFFRENCE PHP FQUILIEDTOM FO®L CYCIE -- ¥ASTE DECAY TIHNES

RALPHA-¥

3. ¥
1.23¥%=02
5.43F=-02
3.33F-09
5.26%-06
SCBRE‘OS
5.67FE 20
3. 03E-0%
2. 9‘5?‘"-0&
1.89%-02
J.U8% 00
1.28F7-04
1.67TE-DU
1. 82E-02
2.63% 00
8' 70E-05
1. 0BF=-0u
8. HUE—O3
T, 797 00
5.20E=-0%
8,057=-05
2. 21E-11
7.‘?2?’03
1.52F 00
5.06F~0%
2.249¥%-02
2.30F=38
3.64%E~-02
1.208-01
5. OSE-@:S
3.27F QD
B.85E-02
1.37E 00
1.16F 00
4,34F 92
1.80F 4D
1.9%¢% 05
2.53F 03
L.87F 03
5.80E+-1%0
8.96E 40
1.88F-11
3.25F 05
T.Y1E @b
4,977 05
9.9%F D3
5.317F 0%
5.54F 02
1.3CF €2
1.93E-01
1.17E-13
3.8L7-02
9.09%-02
7- 172"0“
6,90F-01
B.62F-33
T, 61E=09
5.50F=20
5.24F 0%

NFOTRON SOU=CE

BASTS =
10. ¥
2.752-02
9.51FE~03
3.,95F7-09
3.20%-~-05
1.318~04
9.93F-01
3.60?‘0h
SQQSE"OH
L,23%-02
£,03E-0%
3.017-05
1. 9BE-04
3.17E=Q2
L,57E=-0%
2, 047=-0%
?.38?'0&
1, BiF-02
3.18E-011
1.228=-0t
9.558=-05
L,QU4E-11
1, 73E-02
2,658=01
5,018-05
2.33%-02
2.038-08
3.E1E-N2
1e547-01
T RER-02
TL.LBE 00
R.BSE~{2
1,377 0D
1368 00
L, 3w 932
3.28%-01
1.832 05
2.54% 03
5.,99F 03
3,.87F-10
B.99% 00
6.27%=11
3.30F 05
RL1ME GO
2.08% Qu
8,557 03
3.95%7 05
E.58F% 02
.30 D2
4, 19v-08
1.93P-01
B,16F-16
3.59E~C2
€.558-02
T.138-04
T, 10P-01
0.0
3,05%=-22
0.0
4,56% 0%

IN DISCHA®GED PNTFL,

NFUTRONS/SRC

W OF HFAYY MPTAL CHAPGED TO REFAUTOR

30, ¥
5.607=02
51 2qE‘03
9. 19E~-0%
1. 55204
2.E7P-0h
5, 538=71
8. 37F=-04
1.877-03
8.63F-02
3. 36FE-0%
8, 11E-01
fl.61E-0u
6- u—'?’fiz
2.5472-01
5.51R=-34
2. 98E-0b
3.70%8-02
1.75F-01
3.307-08
2.22F-04
3. 01F=-10
3.53E~02
1.89F~C%
1. 40E~08
2,507-02
2, 122=08
3.828-02
1. 35E=-01
5.L6E~-02
1.32% 01
8,362-02
1.37E 00
1. 368 00
4,357 02
2,532-0%
1.59% 0%
2.58% 03
5.07% D4
i« 50E~- 10
9.067% 0D
1. 888~ 10
3,337 05
E.10F O
1,998 04
5.58% 03
1.RHEE 06
5.53% 02
1,308 02
b, 11R=-04
1.93%-01
i, 437-23
3.“53-02
2'27E_02
7. 02704
5. 84704

h2E 06

o O

.0
.0
.0
-

0o, ¥
B,LTF~-02
2.707F=03
§,818~08
1,23%-03
i, N3E-D8
2,82%-01
§.202-03
7.00E-03
%.30R=-01
1. 7¥E-G1
3,03%-03
3,422-03
9,.77P-02
1.308-01

. 26%=03
2,.212-03
5.59E-02
R.9ZE=~02
3.237-03
1,65F=-03
te B3E- 10
5E.33F-02
7.618-02
1.7418-03
3,707=-02
2. U4E=-D3
3.63%-02
5, 88R-02
1.89%-01
2.807 O
8.B7E~02
1.39% 00
1. 167 30
4,40 D2
1.028-10
9.67% 0G4
2,51 03
Y. 3RF 04
%.207-12
9.27% 00
6.27%-10
3,08% 05
5.07% 04
1. 399 ou
1.22% 03
1,267 05
S.U3F 02
1.29E 02
4, 31%=08
1.93%-01
0.0
3.09E=-02
c.06R-04
f.65F-08
£.337-12
.0

i

-
, UD

by

&

M D3O D

.O
.0
o3

300. ¥
£,897-02
3. 9LE-OU
5.858-07
E.22%-03
i, 23F~-04
4, 1%E-02
5.332-02
3.808-02
. 377~01
2. 508-02
1. SQE-OZ
2. QHE*OZ
1. 038-01
1.89%=-02
1, 128~-02
1. 90E-02
5.B6%-02
1. 3CE=-02
6. 68%8=-03
1. 82R=-02
1. 602-10
5.608-02
1. 11202
8,91F-03
©.96%-02
3, 35E-08
3. 67E-02
1. 008-02
E.50E-01
4,557 01
8.90P-02
1. 407 00
1. 167 00
L.531F 02
7.61F-32
2.4078 0L
2.75% 03
. 35E 7%
4. OuF-13
.63% 00
1.88E-09
2,227 05
k,e82 ¢4
£.56% 03
1. 60F 07
5. 938 01
5.uCP 02
1.25% 02
4, 19F=-0L
1.93%-01
0.0
2,038-02
f.41F7-08

10000 Y
9, 2LF~02
RO7SE_O7
6. BE6F~D%
1.037-01
0, anr-oy
4, 96F~05
5.898-01%
3,83%-01
1.862P=-0%
3, G1E-05
1. T2E-0%
3, 24701
1, 07E-01
2.28F=05
1. STE=-01
2. 30E-07
6.30F=02
1. B7E=-05
7.00E-02
1.57F=-01
1. 66F=-10
5. 81F=-02
1. 34F=-05
9, 8uP-02
3.858-01%
6. B0%-08
3, 80°-02
1. I9E-05
1.588% DD
5.208 €19
9, QuUF-02
1.60% 00
1. 16¥ 00
4,707 02
0.0
u4,30F 02
323 93
. 267 (4
3.81¥-13
9, 93F 0C
6. 26F-09
7,287 0&
4,678 08
2.29f7 02
L, 15pP-06
$,BUF-10
5,09 02
1.137 02
4, 1IFP-04
1.93F-01

3000. Y
1,02%=-01
1,98%-08
5. 62%-05
7.83E-01
5, B5F-04
2.077-0%
5. 12F 00
3.028 00
1.5372-0%
1. 26F=D6
1.317 00
2. 82 00
1. 1B®E-01
9,54%7-07
B.FAF~-07
1. 82F 09
5.737-02
5.5%F-07
1.38F D0
1.83E-10
B UIE-N2Z
5.59%-07
R, 55R-01
1,218 00
1, RS E-07
8, 19F-952
5.16F=-1%4
©.79¥% 46¢
£.197 01
9,53F7=-02
17,997 090
1. 18E 00
L.7BE 02
2.0
£,N9F-02
b.36F O3
1. 03% 0o
3.22%-13
1.018 Q1
1.88E~08
3.80F% 03
3.90F QU
2.512-02
6-33E'25
5-69?'11
4,31 02
8.39% 01
4. 34E-04
Te92%-01
0.0
9,95P-n%
2.47E-10

10oenn, Y
193QF'01
R, N6®~=08
5.16%-04
4, 58% 070
£, F18=-04
B, 42E-05
a,7ce 01
1.778 D
2.1 R=-01
L. 12FE=0%
J7.65E 0D
2.5¢% Q1
1. F0E=-01
3.87%7-06
5,202 0D
T« 67E 04
g, 1RR=-02
2.8567-06
3. %%% 00
7.25% 0%
2,50P-10
B. 75P-02
2.27r-06
7. B6™ 00
3.97® 00
7.581%8~-07
S.72%=-02
0.0

1,937 01
5.09% 0%
te 218=01
2. 897 00
1, 16% 00
b, 78F 02
0.0

E,5GR~15
R.L2P 03
S.DRE 03
1., 79%= 133
1, 057 03
£,21F-08
3.00% G2
2.07® (¢t
3,4027=-1%
0.0

1. 887~ 10
2.39% 02
3.008 0%
G, 11E=004
1.89%=01
n. 0

1. 028-10
1.878-10
3. 26E-07

100000, Y
9,61v-09
1,257-0¢6
1.20P=-02
3.62F7 01
u,58%7-03
1.31F-0C4
1.907 03
1,407 02
1,087 00
7.94F-0%
f.0ur N1
£.037 02
1.19F 08
B. 01E=-05
b, 107 01
3.90nF 02
£.,357-01
L, 3$37-05
2.8 04
2.99F Q2
T. T3P=00
£, 05F=0¢
3,827-0F
1.83% 02
2.0b% 04
1.167=-0%
3.987-017
n.“
1.5¢F 02
g, Hor 01
3.682-01
3.73% 0O
1.16¥F 00
L,65F 02
0,3
0.3
9, 0Ly 02
4,99R-01
9,L3F-97
G,00% o0
CL.ROF-0T
1.67F=-81
5. 927 00
0.0
0.0
t.737-09
1.267-07
5.3%F-05
unOQF-Ou
t.BRE-0O1

8¢Cl
PUz38
PUZL0
TU242
PUZHL
cu2i?
CM284
cH2L6
CH248
CM250
CF2E0
CF252
CF25L

TOTAL

THITIAL
1,937 03
1.027 04
3.54F 03
2.87%=-09
1. 01 08
1.38F 08
2.0LT 06
8.11F 03
1,22F-03
3.87% 03
1.97E 05
2.65F% 01

L,42% 08

1. ¥
1,117 04
1. 128 04
3.54% 03
B.06E=NT
2.14w 07
3.26F 08
2,08% 06
B, 127 03
1,22%-03
3.672 03
1.52% 08
u,03r=-01

3.89F 08

L A R AR D MR MR AT R A 0

4.97% 08

3.€67 08

Taple A-23 (CONTINUED)

RFFEFPENCE PWR EQUILTBRTUM TUEL CYCLE -- WAST® DECAY TINWS
SPONTANECUS PISSTON WEUTRON SNUECE I DISCHARGED FURL, NEUTROHS/SEC
#7 OF HERVY METAL CHATGED TO RERCTOR

3. ¥
1.33®% ¢t
1,327 04
3.54% 03
2.817=06
9.99% 05
3.02% 08
2.04E D€
8., 12F 03
1&222‘03
3.30F 03
8.97F 08
9.34F~-05

3.05% 08

3,11® 08

BRETS =

10, Y
1,278 0Ot
1.83F 04
3.55E 03
E.OUE-GG
8,258 04
2,317 98
2,08 06
B, 128 03
1,22F-03
2,288 03
1.L3F 00
1,778-17

2.33% 08

2,37E 08

30, Y
1. 1GE 08
Z.89% 08
3.588 03
2,41p-05
3.8B8% 04
1.078 €8
2. DUE D6
B.12% 03
1.22F-03
7.89E 02
7.59F% 0%
0.0

1.09E 08

1, 12F 08

100. ¥
« 71F 03
3.67% OO
3.667 03
g8.00E~05
2.82F 08
7358 06
2. 01F 06
8, 12F 03
1-22?‘&3
7. 93E 01
8.2&3’07
0.0

9. 447 06

1.01% 07

0. ¥
. 7T1E 03
3. h6E DU
3.80% 03
2, W1E-CU
1, 13E 04
3.46F 03
1. 96F 06
g.11® 03
1.2718-03
n-913-04
8.0
0.0

2,028 086

2,347 06

1000, Y
3.06E 01
3, 1QF Qb
3.92r €3
B.03F-0b
4, 65E 02
8.98F-09
1.76E 06
8. 10E 03
1. 17E~03
9. 30E“06
0.0C
6.0

1. 818 268

1. 957 06

inge. Y
2'! 8”?"03
2. 77E 04
4,01r 03
2., 409-03
5. 10E-02
3.32E-0¢
1.31F 0§
8. 07E 83
1. 08F-03
8. SGE-QE
0.0
0.0

1. 35E 06

1.81F 06

10000, Y 100000, ¥

3.887=17
1. 357 04
L, 148 03
7. 96E-03
£,9588-1%
1. 10E-08
4.89F 05
7.96% 03
8, 20%-04
6.50E~-06

5.28% 05

0.0
1.33F 00
3.5%9F 03
7.29E-02
0.0
t.01r-07
R.32E-D1
6. 67F 03
2.278-05
0.0
0.0

1.038 Ju

R S M AT R SETY T R W Y T WD W = 3 e e R P D WD D P W MR DR M R S A e W R W A A L WS L e A e W TG L WL A D SR el e e ok Al e e W A e M L e kol Al s e W W

1.87F Qb

6€L
Taae A-24,
FLEMENTS PRESENT IN THE WASTE RESULTING FRoM A MeTrIC Ton oF Uranim CHARGED TO A PR

[T 1S ASSUMED THAT, AT THE TIME OF PROCESSING, 99.5% oF THE U AND PU IS REMOVED FROM THE WASTE,

RFFEFENCPY DWR FQUTLIEPTUM FUEL CYCLE --
POHFR= 30,00 M#, BURNUR= 33000, MWD,

WLSTE DFCRY TINMES
PIOT= 2.92F 13 ¥Rx2-S7C

RCTYXTIDE PAOTOR TFLEASF RATES, PHOTOWS/SEC

BASTS = MT OF HFAYY METAL CHARG®ED TO RFRCTOR
EMEAR TTMFT AFTFP DISCHARGE

{METY INTITIML 1. 1 3. ¥ . ¥ 30. ¥ 100. ¥ 300. Y 1000. ¥
3.00E-02 1.73F 91 1.73F 41 1,.74F 31 1.7T7E 31 1.78F 11 1. 64 11 9.20F 71 LL.OBE 10
L.00P=-02 1.1%P 12 ©,20F 71 8.62%F 11 B8.5%0F 11 28,732 11 6.68F 11 4,157 11 2.39F 11
£.008=-02 2.77E 12 2.78F 12 2,79F 12 2,82F 12 2.84F 12 2.65F 12 2.06F 1z 1,08BF 12
1, 008-01  3.27F% 10 1.22F 10 7,007 09 S,4UF 09 5,848 0% 5,087 09 L4,38F 09 3.22F (¢
1,508-01  3.237 91 3,127 19 3,09F %% 3,09F 11 3,08%® 1t 3.08% 9% 3,00® 1% 2,8B2F i1
2, 00P-01 T 56F 11 1.55F 11 11,547 ¢ 1.,51F 11 1,057 % 1.338 31y 1,287 11 1.20F 11
3.00E-01 1.17F 11 TL96F 1Y 1.%EF %% 40437 11 1,087 11 1.00F 11 9.66R 10 G.13F 10
£,308=-0% 6,5LF 11 5.65% ¥1 5,422 11 5,40F 11 5,398 §1 5,358 %1 5,257 Yy 4,537 %1
1, 10F 20 1.38% 11 9,38F 11 1.38F% 41 4,387 31 4.37E 1% 1. 37F 31 1,38F 17 1, 26F 1
1.55% o 2,006F 08 1.88F 08 1.37F 03 1,0F 0% 4 ,B9M Q7 L,2%% 06 9,367 05 3,687 06
1,995 0¢ 1.07¢ 08 &.338 €7 7,22F 07 5.50® 07 2,588 07 2.2%2 06 4,558 05 4,98F OF
2.38% 00 5,32F 07 4.40F 07 3,597 07 2,74F 07 1,292 07 1.10E 05 2.3RF 0S5 3.75F 05
2.75% 00 5.37% 7 3.987 D7 2,70FE 07 4,08E H7  7,00F 06 1,02F 06 3.7BE NS5 Q,61%F 44
3.25% 00 1.54% 07 1,20F 07 1,04 07 T7,98% 05 3,737 086 3,17F 05 6,478 0L 5,82F 0%
3,70% 00 9.89% 06 7.70F OF B,683F D€ 5,107 06 Z, 400F U6 2.04F D5 4,11% 0% 3,68F N4
G.22F 90 E.Z4E 06 L.BEE 08 £,.227 06 3.227 05 1.51% 06 1.29% G5 2.59F 04 2,32F 04
U,707 00 2.957 0% 2.30F 06 2.D0F D6 t,52F 06 7,158 05 £.09E Ok 3,23% 04 1.10FE O
5.25% 00 9.86F 086 1.L5F 06 1.26R 06 9.%58% 05 &,.50® 05 3.83F 04 7,727 03 6.99F 03
TOTAL  5.5CF 12 5.47F 12 5.09% 12 S.94F 12 S5.07% 12 4.66F 12 3. RIE 12 2.07F 32
MEV/SEC 9.00F 1% 8.31F 11 B.,14F 11 8.142F 11 A.37% 11 7.83%3F 11 7,28F 11 6.19% 119

ACTTNTDY THERGY PELFRSE RATRS, ¥PY/WRATT-SFC

BASTS = AT OF HERVY METAL CHARPGED TO PRACTOT

FMERY Tr AFIF® DTSCHAPGE

{HEW INITIRL t. ¥ 3. ¥ 0. 7 30, Y 100. ¥ 300, ¥ 1000. Y
3.00E-02 1.73F 02 1.73F 02 1.,74¥ 02 1,77FE 02 1,78% 02 1.84F 02 1.20F% 02 4,087 01
4,002-02 1.,52F 03 1.238 03 1,158 03 1,73% ¢3 1,.0BE 02 S,91F 02 5,53F 02 3,%8F 02
8.008~02 5.54% 03 S.56F N3 5K.5BF €3 S5.62PF 03 5,672 03 65,297 03 4,187 03 2,967 02
1,00E-01 1.09% 02 4.07F 0% 2,33% 0% 2.95F 01 1,957 01 1.4%F €% 1.,45% 0% 1.07F% 01
1.508=~01 1.612 03  1.56F 03 1.5%% 03 1,50F 03 1,58% 03 1.%3% 03 1.50F 03 1. 01% O3
2.C0FR-01 1,04® 93 4,048% 03 1,637 03 1,061F 03 ¢.%7% 02 B.8S5F 02 8.51% 02 7,987 CZ
I.O0F«5Y 1,977 03 9.96F N3 1,.16E 03 f,13% 03 1,08% 03 1.00% 03 9,66 02 S.713F D2
6.30E~01  1.37F 04 10197 0% 1, 14F oL 1, 43P U6 1,33% 0% 4, 12F 98 1,10F 00 1,0UF 08
1.90F 00 5.07% 03 S5.06F 03 S,C6¥ 03 E,052 €03 E5.04% 03 E.0%F 03 4.92F 03 0.61F 03
1.%5F 00 1.05E 01 8.15F 00 7.08% 00 S.38%7 00 2,53% 00 2.37E-0%1 L.BYF-D2 H.ABT-{2
3.99% 00 7.11F 00 S5.%3% OC 4,79 OO 3.65FE 00 1.71F 00 1.47E-01 3.022-02 Z,30P-02
2,388 00 u4,22% 00 3,208 00 2.85% ¢C 2.18F 00 1,02%7 00 B.73E~02 1.89¢-02 2.977-02
2,75F 00 4.92F 0D 3.63% 0D 2,478 00 9.34F 00 €,.Uu4F-0%  9,358-02 1,63E-02 B.BIF-03
3,258 00 1.67% 00 $.30F 00 1,%3P 00 B,61F-07 0,08P=01 3,80E-02 £.94F-03 6,.307-03
3.707 06 1.22F 00 9.80F-01 B,24P-01 6£.29F7=01 2.958-01 2.51E~02 5.079-03 &,84F-03
4,22% 90 B,78®-071 6.83F-01 S,93w-01 4,53F-01 2.13%-01 1.8%E~02 3,6%W-ND3 3,26F-03
4,708 N0 L.63F-01 3,&CF=-01 3,13w-0% 2,39F-0%  1,.128-09 9,54F~03 1.92F-G3 1.72F-03
5,258 A 3,25E-01 2.53F-D%  2,29®-09 3,682-0% 7,87F-02 6,70P~03 4,.35®-03 1,21%-03
TOTAY  3.00F 0L 2.77F 04 2,7%E Qu 2,7%F DL 2,69F O0x 2.60F 05 2,39F 04 2.06F OU
GAM®MA WATTS ToBLF=01  %,33F=01 1,30F-0% 1,30%~01 1.29%-071 1,258-01 1.%6%=01 9,9%927-02

3000, ¥
4,297 09
1.92F 113
5,278 1%
2.58% 09
2.35% 11
9.c9r 10
7.76% 10
L,971F 11
T.05F 11
T.65% 06
1,067 D6
1,097 06
9,817 04
B.9&r D4
2.75F 04
T.74% QU
8.22% 03
5.17 03

T.65F %2

h,e37 11

3000, Y
L, 28% 0D
2,56% 02
1,08% 03
8. 60F 00
I.18% 03
6,667 02
7,797 N2
B,88F 03
3,.83® 0%
3,957=01
7, 06E~02
1y 187=01
8.998-03
5. 37E"03
3.80m=03
2 BUE=03
1.298-03
9,.05F-0t

t.H54F 04

7.908=-02

C IGHTEEN-CNERGY-GROUP PHOTON SPECTRUM, AS A FuNCTION OF TiME AFTER PROCESSING, FOR iSOTOPES OF ACTINIIE

10000. Y
2.55% 09
907 ¢
2. 21% 0¢
1. 257 1%
5.3%% 10
2,437 10
7. 187 11
5.5%7F 10
. 337 07
0.5%9F D&
7.919% 0OF
1. 96F 05
5.458% 08
1. 01F DU
6.3RF 03
3,017 03
1, B9F 03

g, 7T1F 11

2.52% 11

10000, ¥
2.55% 00
1,327 02
B, 83F 02
7. 35F 00
5. 2uF 02
3, 54% 02
houzs D2
b, 59% D3
2.08% 03
2,247 o0
3- OSE‘OT
6.277-01
1, 797-N2
5. 93F-03
1, 247=073
8., 95%¥-0u
a4, 72F-04
3.317-01

., 727 03

B.20®-02

100000. ¥
2.33% 09
2.9%8 09
3.06E 00
2,95F 09
1.757 09
1.66F 09
7.30F 09
5,03% 09
2.72% U8R
b.,11% 08
3.54F 07
B,207 07
1.387 06
3.08% 05
2,117 02
1.33F 02
5.30% 01

3,92 01
2.66F 10

7,09F D¢

100000, ¥
2.332 00
3.,9a% 00
6£.13% 00
9.62% 00
8.72% 00
1. 11F 01
7,108 04
8,L7F 01
2,978 00
2,12F 071
2,35% 00
1,928 00
1.2LE-0%
3,352-02
2.508-05
1.,877-05%
9.878-05%
£.947-0¢%

2.3¢6% 02

ort
141

ORNT.-L628

UC-32 — Mathematics and Computers

INTERNAL DISTRIBUTION

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1h2

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K. T. Thomas, Atomic Energy Lgtabjzuhmgnt Trombay, Bombay 85, India.
E. Wallauschek, OECD-ENEA, 2 Rue Andre Pascal, Paris 16%, France.

H., O, G, Witte, Nukem, éh) Hanau Postfach 809, West Germany.

Philip Garrett, Dept. of Chemistry, University of California at

Los Angeles, Los Angeles, Californis 9002k,

Juris A. Balodis, NL Industries, Inc., Nuclear Division, Foot of
West Street, Wilmington, Delaware 198C1.

Virgil E. Schrock, Dept. of Nuclear Engineering, University of
California, Berkeley, California 94720

Robert W. McKee, Battelle Northwest Lab01a+0V1es, Battelle Boulevard,
Richland, Washington 9935z,

Joe Fouguets, Boeing Computer Service, 36801 South Cliver, Wichita,
Kansas 67210.

William Morgan, Linde Division, Union Carbide Corp., N.F.R.C.C,
(Bldg. 11), P.0. Box 4k, Tonawanda, New York 1h150.

John R. Fisher, Nuclear Associates International Corp., 12601 Twin-
brook Parkway, Rockville, Maryland 20852,

D. C. Keeton, Supervisor, Nuclear Section, Tennessee Valley Authority,
Chattanocoza, Tennessee 37HOL.

Peter Kirkegaard, Research FEstablishment RISO, DK-L0CO Roskilde,
Denmark,

A. Whittaker, UKAEA, Windscale and Calder Works, Sellafield, Seascale,
Cumberland, fngland.

Miss Dorothy Trend, ATCOR, Inc., 5 Westchester Plaza, Elmsford,

New York 10523,

Simcha Golan, Atomices International, P.0. Box 309, Canoga Park,
California 91305,

Manson Benedict, Dept. of NWuclear Engineering, Massachusetts
Institute of Technology, Cambridge, Mass. 02139.

Migs Carol Grote, Thermal Systems Division, Battelle Columbus
Laboratories, 505 King Ave., Columbus, Chio 43201,

E. T. Merrill, Battelle Pacific Northwest Laboratorlies, P.0, Box 999,
Richland, Washington G935Z.

James W, Thiesing, Senior Ingineer - Nuclear Products, Boelng Compuler
Services, Inc,, 3801 South Oliver, Wichita, Kansas 67210,
1hh

209, H. R. Brooks, OR Section, BNFL, Windscale Works, Cumberland, FEngland.

210, J. Saidl, Gesellschaft fiir Kernforschung M.B.H., 75 Karlsruhe 1,
Postfach 36L0, Karlsruhe, Germany.

211. J. D. Rollins, Nuclear Fuel Services, Inc., Wheaton Plaza Bldg.,
Suite 906, Wheaton, Maryland 20902,

212. (. Lanzsno, Ufficio Di Rappresentanza, C.N,E.N., 818 18th Street N.W.,
Suite 500, Washington, D.C. 20006,

213, G. M. Gasparini, C.N.E.N, -~ C.S.N., Casaccia, Lab. Chimica Industriale,
5.P. Anguillarese km, T + 300, Roma, Ltaly.

214, Ralph Best, Nuclear Fuels Services, Inc., 6000 Executive Blvd.,
Suite 600, Rockville, Maryland 20852,

215, TIng. Andres Gandellini, AGIP Nucleare S.P.A., Corso di Porta Romana, 68,
20122 Milanco, Iltaly.

216. J. F. Strahl, NUS Corp., 4 Research Place, Rockville, Maryland 20850.

217. Raymond Sund, Gulf Energy and Fnvironmental Systems, P.0. Box 608,
San Diego, California 92112,

218, Tal Fngland, Group T2, Los Alamos Scientific Taboratory, P.O. Box
1663, Los Alamos, New Mexico 8754k,

219, Capt. Joseph A. Angelo, Jr., 1035 USAF FI.D Acty Gp (Ig. Comd.),
Patrick Air Force Base, Florida 32925.

220-425, Given distribution as shown in TLD-4500 under Mathematics and

Computers category (25 copies -~ NTIS).