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LOCKHEED MARTIN ENERGY RESEARCH LIBRARIES

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S OO ____ LEGAL MOTICE oo

This report was prepared 0z an’ nccount of Government sponsered work. Maither the United States,

nor the Commission, nof any pe:er)n acting on behell of the Commission:

AL Makms any warranty or répresentution, expressed or implied, with respeu‘lz fa the accuracy,
completennss, or usefulneis of the information contained in this report, or that the use of
any  informnrion, appumiufiz, mefhod, or process djisc!ased in this report mny ner infringe
privately owned rigiv‘rs; ar : :

B. Assumes uny lighilities with 1espect 1o the use of, or for damnges resuiting from the use of
cm.'y information, apparaius, method, or process disclesed in this report,

As used in the above, '‘person acting on behuolf of *%é Commission’ includes any employes or

contraptor of the Commission, or emplnyse of such co;ni“racfor, to the extent that suchk 2mployee

or cor}trlx:?or of the Commission, er employee of such ceohinctor prepares, disseminates, or
provides uecess fo, any information pursuant to his employwent or controct wifl".; the Commission,

or his gmployment with such cantrecter,

 

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ORNL-TM-3053
Contract No. W-T4O5-eng-26

CHEMICAL TECHNOLOGY DIVISION

ENGINEERING DEVELOPMENT STUDIES FOR
MOLTEN-SALT BREEDER REACTOR PROCESSING NO. 1

L. E. McNeese

NOVEMBER 1970

OAK RIDGE NATIONAL LABORATORY
Oak Ridge, Tennesgsee
operated by
UNION CARBIDE CORPORATION
for the
U.S. ATOMIC ENERGY COMMISSION

LGCKHEED MARTIN ENERGY RESEARCH LIBRARIES

(AR

3 4456 0514237 9

 
11

Reports previously issued in this series are as follows:

ORNL ~4094
ORNL~4139
ORNL-4204
ORNL-4234
ORNL-L4235
ORNL-4364
ORNL-4365
ORNL-"3%66

Period
Period
Period
Period
Period
Period
Period

Period

Ending
Ending
Ending
Ending
Ending
Ending
Ending
Ending

December 1966
March 1967
June 1967
September 1967
December 1967
March 1968
June 1968
September 1968
iidi

CONTENTS

Page
SUMMARIES . e o e s . e . . . v
1. INTRODUCTION + ¢ v v o o v v o o o v o o s 0 o o o & o » 1
2. SEMICONTINUQUS ENGINEERING EXPERIMENTS ON REDUCTIVE EXTRACTION 1
2.1 General Operating Procedure . . . . . . . . . 5
2.2  Description of Major Processing Equipment . . . . 3
2.% Extraction Column . . . « .« « .« . . D
2. Jackleg e e e e e e e e e e e e 5
2.5 Feed and Catch Tanks for Salt and Metal . . . . 6
2.6 Treatment Vessel for Salt and Metal . . 6
2.7 Tank Samplers . . . . . . . . . . . o
2.8 Filters, Freeze Valves, and Lines 9
2.9 Instrumentation and Control . .+ ¢« « « « « « + 9
2.10 Gas Purification and Supply Systems 12
%. ELECTROLYTIC CELL DEVELOFENT . . « « ¢« ¢« ¢« ¢ o & o « « « « & 1h
5.1 Experimental Equipment . . . . 15
3.2  Results 16
., SEPARATION OF RARE EARTHS FROM THORIUM BY FRACTIONAL CRYSTALLIZATION
FROM BISMUTH + v ¢ ¢ v o & o o s o o o o o o o s o o 22
4.1  Physical Properties of Materials Considered . . . . . . 27
4.2 Conceptual Design of a ThBi, Precipitator . . . 2k

4.3  Estimation of the Minimum Cross Section for the Precipitator
SECEION + o v v+ « o s 4 2 4 v e e e e e e e e e e e 26
h.4  Estimated Length of Precipitator Section . . . . . 28
L.5  Summary and Conclusions . « « ¢« o « + o o o o &+ o« & 37
5. MATERIAL BALANCE CALCULATIONS FOR AN MSBR . . . 35
5.1 Compilation of MSBR Nuclear Data . . « « « « « « « o 33
5.2 Material Balance Equations . « « « « + « « + & 30
5.3 Computation of Neutron Reaction Rates . . . . b1
iv

CONTENTS (Continued)

Page
5.4  Model for Diffusion of Noble Gases into Graphite . . . Lo

5.5 Model for the Migration of Noble Gases and Noble Metals to
Circulating Helium Bubbles . . . ¢« + « « « « o « « o & L5
5.6 Assumed Chemical Behavior of Fission Products . . . . . L6

5.7 Material Balance Calculations for a 1000 Mw(electrical)

Sil’lgle"’F].Uid MSBR . . . . . . . . . . . . . . . . . . . )4'7
6. REFERENCES L9
APPENDIX A. LIBRARY OF NUCLEAR DATA FOR MSBR APPLICATIONS . . . 51

APPENDIX B. TYPICAL MATADOR OUTPUT FOR A 2250-Mw(thermal) SINCLE -
FLUID MSBR + « = v v o e v e e e e e e e e e e e 67
SUMMARIES

SEMICONTINTOUS ENGINEERING EXPERIMENTS
ON REDUCTIVE EXTRACTICN

Equipment has been installed in Bldg. 5592 to permit engineering
studies on reductive extracticn in countercurrent centactcecrs. The
system will allow the countercurrent contact of up to 15 liters each of
molten salt and bismuth at flow rates of 0.0% to 0.5 liter/minfi Almost
all of the componentg that contact sgalt or bismuth are fabricated of
carben steel. The contactor presently being studied is a 0.82«in. ~ID,

2-ft-long column (excluding end sections) that is packed with solid

1/4~in. right circular cylinders of molybdenum.

The salt and bismuth can be purified by contact with H,-HF mixtures

7
‘J.,J
o
followed by filtration thrvough porcus melybdenum filters. The two phases

can be gampled at varicus poicts in the sgystem.
ELECTROLYTIC CELL DEVELGPMENT

The flowsheet under consgideration for processing fuel from the
proposed MSBR uses an electrelytic cell. Fluorides of thoriuvm or
lithium in a molten-salt stream are rveduced at the bismuth cathode,
while metals that are extracted into bismuth are coxidized at the
bismuth anode. Preliminary experiments made in static cells con-
structed of quartz show that the current variss linearly with the
applied potential. This indicates the absence of a limiting current in
the range of the experiments for which the highest average current

_— 2
density was 4.35 amp/cm .

SEPARATION OF RARE EARTHES FROM THORIUM BY
FRACTIONAL CRYSTALLIZATION FROM BISMUTH

The feasibility of separating rare earths from thorium in a bismuth

golution by fractional crystallization of ThBi, was sxamined. A possible

2
Vi

equipment configuration was considered, and an analysis was made of

factors affecting the fraction of ThBi, that could be potentially re-

2
covered. It was concluded that operation in the envisioned manner might

be difficult because of the need for close control of nucleation rates.

MATERTIAL BALANCE CALCULATIONS FOR AN MSBR

We have developed a computer code, MATADOR, to perform steady-state
material-balance calculations that describe the nuclear, chemical, and
physical processes occurring in the fuel stream of an MSBR. This code
allows us to investigate the effects of chemical processing on the
nuclear performance of an MSBR, to determine fission-product inventories
and heat-generation rates, and to specify flow rates of streams in the
chemical processing plant. The buildup of transuranium isotopes, the
production of activation products by neutron capture in the carrier salt,

and chain~branching in the decay fission products are considered.

The MATADOR code has been used to compute inventories and heat-
generation rates in the fuel stream of a 1000-Mw (electrical) single-

fluid MSBR; this information is summarized for the reference reactor.
e

1. TINTRCDUCTION

A molten-salt breeder reactor {MSBR) will be fueled with a molten
fluoride mixture that will circulate continuously through the blanket
and core regions of the reactor and through the primary heat exchanger.
We are developing methods for use in a close-coupled processing facility
for removing fission products, corrosion products, and fissile materials

from the molten fluoride mixture.

Several operations associated with MSBR precessing are under study.
This secticn describes: (1) a recently completed facility fer semi-
continuous engineering experiments on reductive extraction, (2) exper-
iments related to the development of electrolytic cells for use with
molten salt and bismuth, (3) consideration of selective crystallization
of thorium bismuthide from bismuth-thorium-vare earth solutions as a
means for separating thorium from the rare earths, and (I} a computer
code that calculates the nuclear, chemical, and physical processes
occurring in the fuel stream of an MSBR. This work was carried out ia
the Chemical Technology Division during the periced October through

December 1368.

2. SEMICONTINUQUS ENGINEERING EXPERIMENTS
ON REDUCTIVE EXTRACTION

L. E. McNeese B. A. Hannaford
H. D. Cochran, Jr.

The proposed MSBR processing method is based on reductive sxtraction,
uging countercurrent contact of molten salt and bismuth in multistage
contactors. Equipment has been fabricated and installed in Bldg. %592
for enginzering studies of reductive extraction in countercurrent con-
tactors. These studies will be made using molten salt {72-16-12 mole %
LiF-BeF2~ThFA) and 1liquid bismuth metal. Uranium {about ©¢.3 mole % UF4
in the salt) will be transferred between the salt and the metal, using
thorium as the reductant in the bismuth. 7The salt and the metal will be

contacted countercurrently at 600°C.
One planned objective of these experiments is the investigation of
mass transfer between the salt and bismuth under different flow condi-
tions in various contacting devices. The effective overall mass-transfer
coefficient (or, equivalently, the height equivalent to a theoretical
stage) will be determined in several experiments with various contactors
which include packed and baffled columns. The mass-transfer performance
is determined, in part, by the hydrodynamic conditions in the contactor;
information on hydrodynamic conditions in packed columns will be inferred
from measurements of the pressure drop through the column by analogy
to a water-mercury system being studied by WatSOn.l The experiments
should answer the following questions: (1) What is the limiting flow
rate beyond which the column will flood? (2) Is the bismuth well
dispersed, or does channel type flow occur? (%) How much interfacial
area exists for mass transfer? (&) Is disengagement of the phases
complete in the end sections, or does entrainment present a problem?

(5) How severe a problem will be caused by axial backmixing, particularly

in the salt phase at high metal rates?

A second objective is the evaluation of the performance of aux-
iliary equipment necessary to perform experiments of this type. Such
information will be used in designing subseqQuent experimental facil-
ities. The following components will be included in the evaluation:
freeze valves, filters, instrumentation, and supply systems for argon,

hydrogen, and hydrogen fluoride.

We plan to determine the probable lifetime for freeze valves
subjected to repeated freeze-thaw cycles since we expect them to fail
eventually under such stress; in addition, we will study the perform-
ance of freeze valves containing two fluid phases. The performance of
filters with the possible entrainment of a second fluid is also of
interest. As a part of these studies, we wish to determine whether
carbon steel is a suitable structural material for short-term use in
experiments of this kind, and whether graphite is a suitable material

in which to hydrofluorinate the salt and metal mixture.
In carrying out the experiments outlined above, we will gain oper-
ating experience and confidence in handling the process fluids. We will
also uncover areas of unforeseen difficulty, where further dzvelopmental

work may be needed.

2.1 General Cperating Procedure

Prior to an experiment, slightly more than 15 liters of salt and
15 liters of bismuth will be present in the treatment vessel. This
material will be hydrofluorinated to return lithium, thovium, uranium,
etc. to the salt phase, and to remove oxides from the salt. After
suitable sparging with argon to remove HF and H., salt (15 liters) will
be transferred to the salt feed tank, leaving amheel about 1/2 in. deep
in the treatment vessel. Then bismuth {15 liters) will be transfarred
to the bismuth feed tank, leaving an additicnal heel of abeout 1 in.
Finally, reductant will be added to the bismuth in the metal feed

tank. Samples of galt and metal feed will be withdrawn.

During an experiment, salt and metal may be transferred through the
column at controlled flow rates from 0.05 to 0.5 liter/min. During this
transfer, the pressure drop acreoss the column can be monitored, and
samples can be taken from the salt and the metal streams exiting from
the column. After an experiment, the salt and the metal may be sampled
in the catch tanks before being transferred back to the treatment veszsel.
Hydrofluorination would be repeated to return lithium, thorium, and
uranium to the salt phase prior to the next run. Thus, there will be a
constant amount of each comperent in the system {notably uranium),
except for a known amount of thorium which will be added to the system
in each run. Material-balance determinations will be greatly facilitated

by this fact.

2.2 Description of Major Processing Equipment

All componentg that contact molten salt or bismuth are fabricated of
carbon steel, except as noted. The major components in the gystem
for handling salt and metal are described below and are shown schematically

in Fig. 1.
ORNL-DWG 68-14347 A

 

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SALT AND METAL
TREATMENT VESSEL

SALT FEED AND
COLLECTION TANK

METAL FEED AND
COLLECTIOM TANK

£ and Metal Filowsheet.

-~

ied Sal

Simplif

1.

Fig.
T

2.% Extraction Column

The four contactors that have been fabricated have the same physical
dimensions: 0.82 in. ID x 2 ft long, excluding end sections. In each,
bismuth is introduced through a tube (0.259 in. ID, 0.058-in. wall
thickness) that projects at right angles into the end section about 7/16
in. above a slotted grid. The grid acts as a distributor and restrainer
for the packing. Salt is withdrawn through an overflow line 1-11/16 in.
above the bismuth feed port. 1In the bottem end section, salt is intro-
duced through a 0.259~in. tube at right angles to the columo 7/16 in.
below a slotted restraining grid similar to that at the top. Bismuth
flows from the bottom of the end section threough a tube 1-11/16 in.

below the salt feed port.

Internally, the four columns contain one of the following: (1) 1/h-
in. right circular cylinders of molybdenum (void fraction, about 40%);
(2) 1/8-in. right circular cylinders of molybdenum {void fraction, about
Lo%Y; (3) segmental baffles covering 96% of the column cross section at
1/2-in. spacing; or (&) open column area that could be packed later or
could be used as a spray column. On the basis of studies with the water-
mercury system, the 1/lL-in. packing looks most promising. Therefore,

it will be studied first.

2.4 Jackleg

The pressurs drop across the column will be measured with a jackleg
by using the following procedure. The salt level in the jackleg will be
measured using an argon bubbler. The sum of the pregsure resulting from
this head of salt and the difference in the pressures in the gas spaces
above the fluids in the jackleg and the column will be equal to the salt
pressure at the bottom of the column. The pressure at the bottom of the
column will, in turn, equal the pressure drop across the columm. The
gsalt head in the column, the bismuth held up in the column, and the

vigscous drag in the column will contribute to thig pressure drop.
The jackleg can accommodate a head of approximately 4 ft of salt.
Preliminary estimates indicate that the pressure drop across the column
may be 3 to 6 ft of salt under conditions of maximum flow. The jackleg
will be pressurized in order to operate under conditions where the

pressure drop is greater than 4 ft of salt.

2.5 Feed and Catch Tanks for Salt and Metal

The duplex feed and catch tanks for salt and bismuth are identical
in construction. The feed tank, an inner cylinder of 8-in. sched 80
pipe, is designed to operate at pressures up to 50 psig at 600°C. Both
the inner feed tank and the outer catch tank will hold about 20 liters
of fluid. We plan to use only about 15 liters of salt and 15 liters of

bismuth.

The top of each feed tank contains seven ports: (1) an inlet port
(1/2~in. pipe with a fitting for %/8-in. tubing), which does not extend
into the tank; (2) an outlet line (1/2-in. pipe with a fitting for 3/8-
in. tubing), which extends to within 1/2 in. of the bottom of the tank;
(3) a sparge and pressurization port (with a fitting for 3/8-in. tubing),
which extends to within 1/2 in. of the bottom of the tank; (4) a 1/2-in.
pipe (with a fitting for %/8-in. tubing) used as a thermocouple well,
which extends to within 1/2 in. of the bottom of the tank; (5) a 1/2-in.
pipe with a fitting for a 1/2~in. ball valve and sampler and a {itting
for 1/4-in. tubing below the valve; (6) a 1-in. pipe with a l-in. ball
valve as an addition port; and (7) a 1/2-in. capped pipe as a spare port.
Each catch tank has the same ports as the feed tanks except that no
addition port is provided. The outer surfaces of the feed and catch

tanks are coated with nickel aluminide to retard oxidation.

2.6 Treatment Vessel for Salt and Metal

The treatment vessel consists of a 304L stainless steel pressure

vessel that holds a graphite crucible. The cylindrical portion of the
pressure vessel is 26.5 in. long (1/4-in. wall thickness) and has a
standard pipe cap on ecach end. It is designed to withstand H, -HF at
600°C at a pressure of 50 psig. -

The inner crucible, machined of graphitej% has an outer diameter of
16.75 in. and is 26.7% in. (overall) high. The wall thickness tapers
from 1.75 in. at the bottom to 0.75 ia. at 16.75 in. from the bottom, and
is uniform from there to the top. The bottom of the crucible is 1.75
in. thick. The crucible has a 16.75~-in.-diam 1id, whose thickness
varies from 1 in. at the rim to 0.5 in. at the center. The graphite
crucible rests on a support plate inside the pressure vessel, and the
1id is held loosely in position by three gtuds projecting from inside
the top of the pressure vessel. The vesgel has 15 nozzles, which are

described in Table 1.

2.7 Tank Samplers

The treatment vessal and the feed and catch tanks are each pro-
vided with a 1/2~-in. sched 40 pipe nozzle fitted with a ball valve and
sampler. These tank samplers hold four fritted filter sticks that
extend through a Teflon plug in the top and can be lowered (while the
gystem is under argon pressure) through the ball wvalve into the tank
below. Samples can be drawn into the filter sticks by vacuum. Four

samples can be taken during one run.

In addition to the five samplers on the vessels, there are two
flowing-stream samplers, which operate in a manner similar to that of
the tank samplers. These flowing-stream samplers allow seven samples
to be taken from each of two flowing streams during column operation.
One sampler is located on the salt return line (between the column
and the salt catch tank), and one is located on the metal return line

(between the column and the metal catch tank).

 

¥
No. 8735, Speer Carbon Co., a Division of Air Reduction Co., St. Marys,

Pa.
Table 1. Description of Nozzles on Treatment Vessel

 

 

Nozzle
No. Used For Description
1 Bismuth charging Z2-in. sched 40 pipe, flanged at the top to accom-
modate a chute for loading bismuth. The graphite
1id below this nozzle has a 1.625-in.-diam hole
with a removable plug.

2 Bismuth sampling; salt 0.5-in. sched "0 pipe with ball valve and sampler.
sampling; gas-phase pres- The lid is fitted with a l-in.-ID graphite pipe
sure connection. into which the C.%-in. pipe slips. The graphite

pipe extends through the graphite lid and into the
crucible for a distance of 1 in.

= Returning salt from the 0.5-in. sched 40 pipe nozzle containing a sleeved
salt receiver 0.379=in.-0D tube. Below the carbon-steel-to-~

molybdenum transition, the 0.375-in.-0D molybdenum
tubing extends 4 in. below the graphite 1id.

ly Returning bismuth from the Identical to nozzle No. 3.
bismuth receiver

5 Transferring bismuth to 0.5-in. sched 40 pipe nozzle containing a sleeved
bismuth feed tank 0.375-in.-0D tube that extends to within 0.5 in.

of the bottom of the crucible. The tubing that
extends inte the crucible is made of molyhdenum.

6 Transferring salt to the Similar to nozzle No. 5; set so that 1% liters of
salt feed tank salt can be transferred rto the salt feed tank,

leaving a 0.5-in. heel of salt on top of the
bismuath.

T Monitoring liquid level® Similar to nozzle No. 5.

& Sparging with H,-HF Similar to nozzle No. 5.

9 Adding salt Similar to nozzle No. 3.

10 Spare Similatr to nozzle No. 3.

11 Thermocouple well 0.5-in. sched %0 pipe with fittings for 0.375-in.-
0D tubing

12 Making miscellaneous ad- l-in. sched 4C pipe, with ball valve.
ditions, or vessel venting

13 Draining vessel 0.5-in. sched 4C pipe extending from the bottom of

the pressure vessel; this line is capped.

 

“Acts as a bubbler type of liquid-level monitor.
9

2.8 Filters, Freeze Valves, and Lines

The experimental facility has two filters, one of which is located
on each of the lines between the treatment vessel and the salt and metal
feed tanks. These filters, made of fritted molybdenum. have.a nominal
pore size of 25 py. The permeability of each filter was measured before
and after fabrication, and was found to be about 40O cm’ (sTP) em™>
(cm Hg)_l at a pressure differential of 1.5 c¢m Hg. Both filters can be

bypassed if necessary.

Salt and metal flows through the facility are directed by 10 freeze
valves in the transfer lines, located as indicated in Fig. 1. These
valves are simply dips (in the carbon steel tubing), which are fitted
with air cooling linesn Those freeze valves that must be closed before
any salt or metal can be transferred from the Creatment vessel were
equipped with small reservoirs {about 50 cmB) of bismuth prior to being
welded into the lines. The facility, which is of welded construction,
contains approximately 200 ft of salt and metal transfer lines (3/8-in.
and 1/2-in. pressure tubing).

2.9 Instrumentation and Control

The principal cbjective of the instrumentation and control system
is to provide closely~regulated flows of bismuth and molten salt to the
extraction column. The range of flow rates provided for both bismuth
and molten salt is nominally 40 to 500 ml/min, corresponding to experi-
ment durations of about 5 to 0.5 hr. Pressures and liquid levels in
the six vessels (treatment vessel, feed and catch tanks, and jackleg)
of the facility are sensed by Foxboro differential-pressure transmitters,
which send signals to miniature pneumatic recorders or controllers.
Liquid level is inferred from the pressure of the argon that is supplied
to a dip-leg bubbler in each tank. Flow rates of bismuth and salt to
the column are controlled by regulating the rate of change of liquid

level in the twe feed tanks. The locations of galt-argon and salt-
LO

bismuth interfaces in the column are not directly measured, but can be
determined from pressure measurements. The feed and catch tanks and the
treatment vessel are maintained at the desired temperatures by automatic
controllers; transf-r-line temperatures and temperatures of small com-
ponents are controlled by manually regulating the appropriate voltage

transformers that supply power to Calrod tubular heaters.

Figure 2 is a schematic diagram of the control system that reg-
ulates the flow of bismuth or salt to the extraction column. It is
designed to circumvent the flow-control problems that sometimes occur
when gas pressure is used to maintain a constant flow of liquid from a
heated feed tank. An adjustable ramp generator and an electric-to-
pneumatic converter are used to linearly decrease the set point of a
controller that senses liquid level in the feed tank and controls the
level by controlling the flow rate of pressurizing argon to the gas
space of the feed tank. The result should be a uniformly decreasing
bismuth level and, hence, a uniform discharge rate of bismuth or salt
from the tank. This control system should be unaffected by small
increases in back pressure caused by changing column hydraulics, par-
tial plugging of transfer lines, decreasing feed tank level, etc., or
leakage of pressurizing argon (a small argon bleed is provided to
improve pressure control). Small gas pressure oscillations caused by
the temperature cycling of a conventional temperature controller will
be minimized by the time-~-proportioning controller. Rates of transfer
of salt and metal between the collection tanks and the treatment
vessel need not be closely regulated; therefore, manual control of

pressurization is used.

Heating circuits are manually controlled for 11 transfer lines,
5 flowing-stream samplers, the salt jackleg, and the extraction column.
On the transfer lines, the Calrodsrated at 230 v are run at 1h0 v or
less, and provide up to 185 w per foot of line. Typically, temperatures
at three points on each line are recorded. Approximately 100 points

are recorded for the system.

For obvious reasons the gas bubbler method for measuring static

head cannot be used directly in the small-diameter extraction column.
11

ORNL DWG 7O-4574R4

 

 

 

 

FOXBORO
ADJUSTAR RAMP
? STABLE RAMP ! cONVERTER E/P ot RECORDER
GENERATOR (E vst) CONTROLLER

 

 

 

 

 

 

 

A

7

A

’

 

 

d / P ?{l Ily r.l'( ?.{I t’i’ '_’f’ 7# In{/ )7” 3
CELL

 

 

 

 

 

ARGON
PURGE ] —D<G—= ARGON BLEED

 

BISMUTH OUT ey
50-500 m!/min.

 

 

 

  
 
  
 
   

LEN
TEMPERATURE
RECORDER
CONTROLLER
{(TIME
PROPORTIONING)

 

 

 

 

 

 

 

 

 

Fig. 2. Schematic Diagram of Control System for Metering Bismuth
from the Pressurized Feed Tank, T-l.
12

However, the bubbler that terminates near the bottom of the jackleg can
be used to determine the pressure at the base of the columm. This liquid
level measurement, in conjunction with the measurement of gas phase pres-
sure in the jackleg, will accommodate a bismuth holdup in the column

approaching 100% of the open column volume.

2.10 Gas Purification and Supply Systems

Three gases are required for the experimental facility: HF, hy-
drogen, and argon. Because of the highly deleterious effect of small
amounts of oxygen, the nominally pure bottled hydrogen and argon are
further purified to remove traces of oxygen or water. The anhydrous
HF is given no additional purification; it, along with hydrogen, is
used only in the treatment vessel for hydrofluorination of the metal
and the salt. A schematic diagram for each of the three supply systems

is shown in Fig. 3.

Highly purified argon is used for all applications requiring an
inert gas: pressurization of tanks for trangferring bismuth and molten
salt, dip-leg bubblers for liquid-level measurements, purging of appa-
ratus for sampling bismuth and salt, etc. Cylinder argon with a mini-
mum purity of 99.995% is fed, first, to a bed of molecular sieves [Fig.
%2(a)), which reduces the water content to about 2 ppm (-100°F dew point).
The argon thenflows through a bed of uranium metal turnings, where the
remaining oxygen and water are removed. A porous stainless steel filter
removes any uranivm oxide dust that might be carried from the uranium
bed by the gas stream. The maximum argon flow rate, based on the ca-

pacity of the molecular sieve bed, is about & scfm.

The hydrogen purification system is a commercially avilable device*
that purifies hydrogen by the selective diffusion of hydrogen across a
palladium alloy barrier. Impurities, along with a small flow of hydrogen,
are continuously bled from the upstream side of the barrier. The capacity

of the unit is 15 scfh. Controls for the purifier are self-contained.

 

*
Serfass Hydrogen Purifier, product of Milton Roy Co., St. Petersburg, Fla.
15

ORNL DWG 702801

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

(a)
MOISTURE
- MONITOR. s
X ) X
?—] MOLECULAR SiEVE BED LS URANIUM CHIP BED ~380
X { WATER REMOVAL.) w (OXYGEN REMOVAL) FILTER e sccth
~28080 ~65O°AC { max.)
ARGON
CYLINDERS (4)  ARGON PURIFICATION SYSTEM
IMPURITIES BLEED
(b} t
i l SERFASS ~{5
A} - HYDROGEN » scfh
PURIFIER {max.)
HYDROGEN
CYLINDERS (2}
" HYDROGEN PURIFICATION SYSTEM o
(c)
! WEIGH
CELL
7 o ~Glb/hr
b {mox.)

 

 

 

pp
HOT WATER SUPPLY HOT AIR BATH

e FOR CAPILLARIES
TANK

   

 

HOT WATER BATH PRESSURE
RECORDER
CONTROLLER

 

 

HF SUPPLY SYSTEM .

Fig. 3. Simplified Diagram of the Gas Supply Systems.
14

The anhydrous HF supply system utilizes small capillaries for
metering; a pneumatic controller maintains a specified pressure drop
across a capillary by controlling the HF gas supply pressure. This is
achieved by regulating the temperature of the water bath in which the
HF supply tank is suspended. Accidental overheating of the HF supply
tank is prevented by a switch that releases cold water into the bathifl
the temperature exceeds 60°C. The minimum flow range for the HF supply is
nominally O to 0.25 1b of HF per hour; the maximum range is O Lo “ 1b
per hour. A calibrated weigh cell provides a means of checking the

rate of HI delivery and the HF inventory.

5. ELECTROLYTIC CELL DEVELOPMENT

M. S. Lin L. E. McNeese

In the proposed MSBR fuel flowsheet2 using reductive extraction, an
oxidizer-reducer is required (1) to convert extracted materials to their
fluorides in the presence of a salt stream, and (2) to reduce the fluorides
of lithium and thorium at a bismuth cathode. Electrolytic cells for

simultaneously carrying out these operations are being developed.
The advantages of using an electrolytic cell are as follows:

1. The oxidizer and reducer are coupled together; thus the amounts
of the oxidized and reduced products are always in the correct
proportion.

2. A cell can be adapted for continuous operation.

3. The rate of oxidation-reduction can be regulated by varying

the current flowing through the cell.

L. Use of a cell provides a closed system and makes the use of

additional materials unnecessary.

The major information needed for designing an electrolytic cell is

similar to that needed for designing a conventional chemical reactor,
15

namely, information concerning capacity, efficiency, and suitable materi-
als of construction. The capacity is mainly determined by the current
density obtainable in a practical cell configuraticen. The obtainable
current densgity, in turn, is determined by the electrede kinetics, which
must be evaluated experimentally. The cell configuration depends upon
the state of the reactants and the method for digsipating the heat that
igs generated by the cell resistance. Factors which should be considered
are: (1) the oxidaticn-reduction potential of the redox reactiocn, (2)
the energy spent in overcoming the internal cell resistance, (%) the
overvoltage caused by diffusion polarization, if any, and (%) the

occurrence of side reactions between the oxidation and reduction products.

Some of this information can be estimated from currently available
data. V¥For example, consideration was given initially to selectively
oxidizing metals, such as uranium, at the anode. However, we then
realized that, under this condition, the operating current density would
be limited by the rate of transfer of the material to be oxidized to the
anode surface. 1In the case of uranium with a concentration of 0.0016
mole fraction in the bismuth, the estimated limiting current density is
0.15 amp/cm2 {based on a uranium diffusivity in ’t)is:m;th.f3 of 2.5 x 10—5
cmg/sec, an estimated diffusion layver thickness of 5 x 10_5 cm, and a
bismuth volume of 21.3 cc/g-atom). A current density this low would
require an anode area of 21.7 ft2 for the protactinium isolation system,
which is larger than desired. The alternative is to oxidize a major
component, bismuth, at the anode to produce bismuth fluoride. An addi-
tional salt-metal contacter would be used to simultaneocusly reduce the
bismuth fluoride and oxidize the metals (uranium, lithium, thorium, etc.)
in the bismuth stream from the reductive extraction contactor. The net

effect is the same as for direct, selective oxidation at the anode.

3.1 Experimental Equipment

Experimental work to date has consisted of experiments in simple
static cells constructed of quartz. Quartz, a transparent material that

is compatible with bismuth, is a good electrical insulator. Although it
16

is attacked slowly by fluoride salt, it has proved to be quite satis-
factory for these experiments. The flat-bottomed quartz tube (4 in. OD)
shown in Fig. 4 was potted to a metal flange by using a silicone rubber
preparation.2 The boltom of the cell is separated into two equal com-
partments by a vertical quartz divider % in. high. The compartments were
filled with bismuth to within about 1/2 in. of the top of the divider to
produce electrodes having an exposed area of about 30 cm2 each. A 6-in.-
deep layer of molten salt (66-34% mole % LiF—BeFE) covering the electrodes
served as the electrolyte. 7Two molybdenum tubes contained within quartz
sleeves were introduced from the top of the vessel; they extended through
the molten salt and terminated near the bottom of the electrode compart-
ments, serving as the electrode leads as well as gas sparge lines. These
two tubes were electrically insulated from the argon supply line with
short sectionsg of plastic tubing. Means for obtaining filtered samples of

salt or bismuth were provided.

Prior to each experiment, the bismuth was sparged with hydrogen at
TOO°C for about 16 hr. About 1.8 kg of molten salt, which had been pre-
viously purified by hydrofluorination, hydrogen reduction, and filtration,
was then introduced into the cell. Viewing slits were provided in the
furnace to allow observation of the salt-bismuth interface in the vicinity
of the quartz divider. Prior to the transfer of molten salt to the cell,
the bismuth surface was clean and shiny altbough it contained a small
amount of film. After its transfer to the cell, the salt appeared to be
colorless and quite transparent. To prevent air inleakage, a slight
positive pressure was maintained in the gas space above the salt by a
continuous flow of argon gas. Figure 5 shows the quartz cell after
installation. A O- to 12-v dc power supply was used that had a maximum
output of 250 amp at 12 v. Both the cell current and the voltage dif-

ference between electrodes were recorded continuously.

5.2 Results

Two series of experiments have been made in cells of this type.

During each series of experiments, the voltage applied across the
Fig. 4.

Static Electrolytic Cell Made

of Quartz.

PHOTO 93288

 

L1
18

™
™
<
o
O
—_
O
&
o

 

10n.

Cell After Installati

1cC

ic Electrolyt

Stat

>

Fig
19

electrodes was increased incrementally from an initial value of 2.6 v,

in steps of about 0.6 v, and operation of the cell was observed. Neither
the salt nor the bismuth electrodes were sparged with gas during the
first series of experiments; however, the cathode was sparged with argon

during most of the second series of experiments.

The initial potential difference between the bismuth electrodes was
less than 0.05 v (below recorder sensitivity) before dc voltage was
applied to the cell. The cell potential (measured with the power supply
turned off ) increased rapidly to 2 v after the passage of 60 coulombs in
10 sec, to 2.1 v after the passage of 625 coulombs in 125 sec, and to
2.25 v after the passage of 9300 coulombs in 61 min. The cell potential
remained at about 2.2 v thereafter. The cell potential was decreased when
the cathode was mixed via argon sparging, but sparging the anode produced
no change in cell potential. This indicates that, as expected, the com-
position within the bismuth phase of the anode compartment does not change,
but that the bismuth in the cathode contained lithium after the passage of

electrical current.

The current-vs-voltage plot obtained from the experimental data
(Fig. 6) suggests that essentially no limiting current exists in the
range covered by the experiments. The slight upward trend seen in one
of the curves indicates a slight decrease in cell resistance, which can
be attributed to an increase in cell temperature. This effect is con-
sistent with values calculated from the published equationl+ for specific
conductivity of the molten salt as a function of temperature. The
hightest average current density obtained was L.35 am_p/cm2 (Loko amp/ftz).
Higher current densities would be expected as the applied potential is

increased.

During each series of runs, the formation of a very finely divided
dark material was noted at the anode. With the first cell, the material
was observed to spread slowly throughout the salt during the first 10 min
of operation. This cell was operated without externally induced circu-
lation; circulation was due only to thermal convection. The salt remained
opaque during the remaining cell operation; however, it became transparent

after the cell had stood overnight, and only a small amount of dark
20

ORNL-DWG 69-6045

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

5.0 ,
4.5 f=0.10a —F 2
t=540°Cc "
[ ]
4.0
J
< s Y
N
€ /
= R=0.07 /° d
E 25 f=550-+650°C _¢" 7
3 ’ /'
> //./
= 4 &
S 25 R=0.06 &
L] F=715°C Y7
o/
— /
z 20 S
& -~ /f=500°c
© {5 s -2
0/ /
9
5
10 = 7=540°C A A:/
R=0.102 L* v
0.5 /
0
2 4 6 8 10 {2 14

APPLIED VOLTAGE (V)

Fig. 6. Variation of Current Density with Applied Potential for
Quartz Cell Experiments.
material was noted at the salt-bismuth interface. After the second cell
had been operated for 10 sec (i.e., 60 coulombs had been passed), the
salt immediately above the anode appeared to be light brown. At this
point the cathode was sparged with argon; the salt remained clear.

Then the anode was stirred by an argon sparge, which resulted in disper-~
sion of the material above the anode throughout the salt. The forma-
tion of black material at the anode continued for an additional 125 sec
(passage of 625 additional coulombs). After the cell had stood over-
night, the salt became clear and contained only a small amount of black
material. No further formation of black material was noted throughout
the cell operation that followed. During thig time (i.e., a period of

several hours), circulation of the salt was promoted by an argon sparge

in the cathode chamber.

Gas was evolved from the anode during the electrolytic process, even
at an average current density as low as 0.15 amp/cme. There was no
evidence of fluorine evolution. A starch solution, through which the cell
off-gas bubbled, remained clear throughout the cell operation although
it did become slightly tinted at the end of the experiment when the cell
was internally shorted and arcing was noted between the electrodes.

Mass spectrometric analysis of the collected off-gas indicated that the
gas evolved from the anode was SiFu and that the SiFljr concentration in

the samples increased as the current density of the cell was increased.
The gas was produced on the anode side of the quartz divider which
separated the bismuth anode and the cathode. It was produced only during,
or immediately after, the passage of current. These observations strongly
suggest that the gas evolution was the result of a reaction of BiF5
(produced at the anode) with the quartz divider.

Sparging the cathode with avgon improved the convective heat transfer
in the cell and kept the temperature low in the vicinity of the quartz
divider. This allowed operation with a higher average current density

2
(L.35 amp/cm with sparging vs 2.5 amp/cme without sparging).
22

The concentration of bismuth (probably present as BiF5) in the salt
increased with the number of coulombs passed through the cell, although
the concentration was only 10 to 50% of that which would result if only

BiF  were produced and it all remained in the salt.

5

The following conclusions have been drawn from the experimental

results:

1. There is no evidence of a limiting current. Operation of the
cell at a higher current density will depend on the availability
of a suitable means for removing the heat that is generated

by the internal cell resistance.

2. A suitable electrical insulator that will withstand the cell
environment is needed. Attention is being given to the use
of frozen salt, which is a sufficiently good electrical

insulator.

3. The current efficiency for the cell can be measured only in
a flow cell. Use of a static cell results in rapid attainment
of steady state, where the net effect of cell operation is

the transfer of bismuth from the anode to the cathode.

L. A more-detailed study of the heat-removal problem should be

made.

L. SEPARATION OF RARE EARTHS FROM THORIUM
BY FRACTIONAL CRYSTALLIZATION FROM BISMUTH

J. R. Hightower, Jr. L. E. McNeese

As presently envisioned, removal of the lanthanide fission products

>

from an MSBR™ will be effected by a multistage reductive-extraction system

5

from which there will be a daily discard of about 0.5 ft” of salt con-
taining 0.69 mole % rare-earth fluorides. The metal stream leaving the
lower contactor of the rare~earth removal system will contain appreciable

concentrations of thorium and the rare earths. Since the solubility
23

of thorium in bismuth is significantly lower than that of the rare
earths,6 much of the thorium could possibly be separated from the rare
earths by selectively precipitating thorium {(as ThBiE) from the metal
stream. Ideally, the precipitated thorium would be redissolved in
bismuth for return to the rare-earth rvemoval system. The potential
benefits of such operation are twofold: (1) the required capacity of
the electrolytic cell used in the system would be reduced, and (2) an
appreciable separation of the rare earths from thorium might be

achieved.

Although the physical chemistry involved in the above procedure
appears favorable, the practicability of the operation has not been
established. However, we have attempted to evaluate the feasibility
of such an operation by considering possible equipment configurations,

the bismuth holdup required, and anticipated areas of difficulty.

L.1 Physical Properties of Materials Considered

Bismuth melts at 271°C. At 350°C it has a density of 9.97 g/cmj
and a viscosity of 1.37 centipoises; at 600°C it has a density5 of 9.66
g/cm§ and a viscosity of 1.0 centipoise. Thorium is believed to exist
in a bismgth solution as dissolved ThBig. The density of ThBi2 is‘
11.5 g/cmj at 25°C; its density has been estimated6 to be 11.4 g/cm5 at

550°C. Thus, ThBi, particles should settle in liquid bismuth.

2
When a thorium~bismuth solution (containing 5 to 10 wt % ThBip) is

cooled rapidly from 1000°C (complete solution) to 600°C, ThBi, precipi-

tates in the form of fine platelets having diameter/thicknessaratios
greater than 50. If these platelets are heat-treated for 20 min at
800°C, or for 5 min at 900°C, dispersions of ThBi, particles having
maximum dimensions of about 100 y and diameter/thickness ratios equal

to or less than % are produced.

In batch precipitation experiments with a Th~Bi solution that was

rapidly cooled, the rate of nucleation on the vessel wall was not
detectably greater than that in the bulk of the solution. However,

when the Th-Bi solution was cooled slowly, ThBi, plates nucleated at

2
the wall and tended to remain there. This tendency can be reduced by
vigorous agitation.

4.2  Conceptual Design of a ThBi, Precipitator

2

A possible design for a ThBi2 preciptator is shown schematically
in Fig. 7. Bismuth that is fed to the precipitator is assumed to contain
rare earths and to be saturated with thorium at 600°C. The precipitator
consists of three sections. The feed enters the precipitation section
(section 1 on the diagram) at 10 gpm, and is cooled to about 350°C.
Particles of ThBi2 start to grow, and are carried upward until they
grow large enough to have a terminal velocity greater than the velocity
of the upflowing bismuth. Thus, for a given bismuth flow rate, the cross

section of the precipitator determines the size of the ThBi, particles

2
that will settle out. The length of the precipitator section will be

determined by the growth rate of the ThBi, particles.

2
The precipitated Th312 particles produced in section 1 pass through
section 2 against an upward flow of lanthanide-free bismuth. The purpose
of the upward bismuth flow is to minimize mixing between the feed stream,
which contains a high concentration of lanthanides, and the stream into
which the ThBi? is redissolved. The velocity should be sufficiently
high to preveng backmixing but must be lower than the settling velocity
of the particles. The section must be of sufficient length to provide
the desired resistance to backmixing between the two streams. In the
final section, the ThBi2 particles are dissolved in bismuth; this
section will probably consist of a length of pipe at about 600°C. An
analysis of the precipitator section is made in the sections that follow.

The analyses of the other sections will be made at a later date.
25

ORNL DWG 70-4589

 

 

 

Th

Ln T

SECTION 4

Th-Ln~B8i
- Feed Solution

 

 

 

 

  
  
 
  
 

FALLING
PARTICLES SECTION 3

SECTION 2

RISING
BISMUTH

 

 

 

 

Fig. 7. Conceptual Flow Diagram of a Thorium Bismuthide Precipitator.
26

4.3 Estimation of the Minimum Cross Section
for the Precipitator Section

The fluid velocity in the precipitation section must be less than

the terminal velocity of the ThBi. particles that are produced. These

2
particles were assumed to be right-circular cylinders with a diameter/
length ratio of 20. This ratio was assumed to be constant during the

entire particle growth period.

For circular cylinders, the "sphericity" (i.e., the ratio of the
surface area of a sphere having the volume of the particle to the surface

area of the particle) can be showm to be:
o(3 /)23
¥ = 2/% 1 ) (1)
AT (l + i_ )

where ¥ = sphericity,

A= DP/E’
£ = length of the cylinder,
Dp = diameter of the cylinder.

For a cylinder with a diametev/length ratio of 20, the sphericity is
0.339. The drag coefficient for a particle having a sphericity of 0.3

can be estimated from the curves in ref. 8, as follows:

~ 10
CD = N 2 (2)
Re
where CD = the drag coefficient, D p
NRe = the Reynolds number of the particle = —7?~ )
v = velocity of the particle,
p = density of the fluid through which the particle is moving,

L = viscogity of the fluid through which the particle is moving.
27

When a particle is falling at its terminal velocity, the downward force on

the particle exerted by gravity is equal to the force produced by the

9

drag of the fluid, and the following relation holds;

HB“S;' = g(l - D/OS)} (3)

where v, = terminal velocity of the particle,

{

= density of the particle,

i

Pg

g = gravitational acceleration.
Substituting Eq. (2) into Eq. (3) and solving for the terminal velocity
yields:
glp, - o)
v, 7 et Di (4)
2251

This equation is valid when NRe < 1. Using the values Py = 11.4 g/cmj,
p = 9.97 g/cmB, and L = 0.0137 g/cm.sec, Eq. (’4) becomes:

2
v, = 1948 Dp , (5)

where v, :as units of cm/%ec and Dp has units of cm.

This equation provides a sufficiently good estimate of terminal veloc-

ities of single particles having diameters of less than 100 u.

Assuming that the precipitation of 100-p-diam particles is desired
(larger particles would require a longer column, whereas smaller
particles would require a larger cross section), the minimum cross
section will be the cross section that results in a fluid velocity equal
to the terminal velocity of  100-p-diam particles. For a bismuth flow
of 10 gpm, the minimum precipitator cross section necegsary for the

D
production of 100-p-diam particles would be 3.4 ft~, which corresponds
28

to a precipitator diameter of 2.1 ft. The cross-sectional area calcu-
lated in this manner must be regatrded as the minimum area since, in the
event that the particle concentration is sufficiently high, the terminal
velocity of the particles will be a hindered settling velocity instead
of the single-particle terminal velocity. For very thick slurries,

the hindered settling velocity could be as much as two orders of

magnitude less than the single-particle terminal velocity.

4.4 Estimated Length of Precipitator Section

The length of the precipitator section will depend on the growth
rate of the Th312 particles since the particles must rvemain in this
section until they are large enough to have a terminal velocity greater
than that of the upflowing bismuth. The longer it takes a particle to
grow to this size, the longer the precipitator section will be. A

rough estimate of the required precipitator length is made below.

Crystallization from a solution takes place in two steps: nucle-
ation and growth. We will assume that the nucleation rate can be con-
trolled. However, this assumption may be unwarranted. Consider a
single crystal that is growing in a solution containing y mole fraction
of a solute. Let Y be the mole fraction of solute at saturation and
y' the concentration of the solute at the interface between the crystal
and the liquid. If supersaturation occurs, this will allow y' to be

greater than Yo In this case, the rate of mass transfer from the bulk

liquid to the interface is given by:

dm

ido - 50 -9 (6)

where dm is the number of moles of solute transferred to the crystal
across an area A in time d@, and ky is a mass-transfer coefficient.
Assuming that the rate of reaction is proportional to the extent of

supersaturation at the interface, the following equation applies:
29

dm N
Fao = k0 - ) (7)

 

where k  is a reaction rate constaat. Eliminating y' from Eqs. (6) and
s

(7), one obtains:

dm (v -v)
Ado (L/k, +1/k]) - (8)

 

Mass~transfer coefficients for crystal growth, ky, have been

correlated by the equation

k DM D vp 0.6 0.5
LB o) e K , (9)
eD U D ’

where ky = mass~-transfer coefficient,

D = diffusivity of solute in solvent,

v = velocity of particle relative to liquid,

D = particle diameter, |

pp = density of liquid,

fi = average molecular weight of liquid,

L = viscosity of liquid,

@ = a constant (assumed to be 0.2 for this study).

If we assume that v is the previously estimated terminal velocity of the
single particle and D is 10_5 cme/sec, and if we use the values 209
g/g-mole, 9.97 g/cmB, and 1.37 centipoises (corresponding to a temper-
ature of 350°C) for fi,p, and p, respectively, in Eq. (9), the following

expression for the mass-transfer coefficient is obtained:

= Oo 5 —5 0.8
ky (2.051 x 10 )Dp , (10)
30

where ky has the units of g-mole per square centimeter per second per

unit mole fraction, and Dp has the units of centimeter.

Values for the surface reaction-rate constant ks are not available.
Therefore, we will assume that the surface reaction takes place infi-
nitely fast. This may be a poor assumption; however, it will place a
lower limit on the length of time required to grow 100-p-diam particles.

Equation (8) then becomes:

dm
ias Ny (y - v.) (11)

Equation (11) will be used to estimate the growth rate of the ThBi,
particles, as follows. The surface area of a cylinder with a diameter

length ratio of A is given by:
2
A= (1/2 + ngnp, (12)

and the volume of a cylinder with a diameter/length ratio of A is given
by: 3
y V = (m/MA)Dp, (13)

Thus, the number of moles of ThBi, in one particle is obtained from:

2
o
m = fi% Di fii’, (14)

where Py = the density of solid ThB:’L2 = 11.4 g/cmj,

M = 650 g/g-mole,

I

. the molecular weight of ThBi2

Differentiating Eq. (14) results in:

. 0D
T S 2
5\ Ms Dp de, (15)

dm = 5

Substitution of Eqs. (12) and (15) into Eq. (11) gives the following

equation for the rate of increase of particle diameter:

A M
5+ 1 5;‘ ky (v -v.), (16)

o] .
Q¢a°
N[
A1

where Dp is the particle diameter in cm,
¢ is the time in sec,

y is the mole fraction ol Th in Bi.

The reduction of the bulk golute concentration as ThBi_, is precip-

2
itated must also be taken into account. Some simplifying assumptions

are necessary. We will assume the system is at steady state, with a
constant concentration of nuclei (N per cmz) in the incoming bismuth
stream. We will further assume that (1) as these nuclei grow into

larger particles, the concentration of particles does not change; (2)

only mass transfer to rising particles is important; and (5) mass transfer
to falling particles can be neglected. Although these assumptions will
produce an error in the nuclei concentration necessary to decrease the
thorium concentration to an acceptable value while 100-p~diam particles
are growing, the sensitivity necessary in controlling nucleation rates

can be seen. The required column length calculated in this manner will

be indicative of that required in an actual precipitator.

A ThBi2 balance over a differential section of the precipitator

yields the following differential equation:

V dy
= k NI
dg y

 

1 1
._..+-- - T
where N = number of nuclei per cmi,
y = mole fraction of ThB12 at point §,
E = distance above feed inlet point in precipitator,
A = cross section of precipitator,

V = molar flow rate of bismuth in precipitator,

k = mass-transfer coefficient to growing crystal.

Substitution of Eq. (10) into Eq. (17), with the condition that A = 20,

yields the following relationship:

NA

d - - > )
a'}é = -(5.54L x 107°) ~ Df) 5 (v - vy, ) (18)
32

Equation (18) can be transformed from an equation in & (spatial coordi-
nate) to one in 6 (temporal coordinate) by using the following relation-

ship:

T-F % (19)

where £ = O is taken to be the bottom of the precipitator section. In
dg
do
itator walls and is given by:

this case, is the velocity of a particle with respect to the precip-

d
S=U -, (20)

where U = velocity of the fluid,

<
fi

velocity of the particle with respect to the fluid (which is

assumed to be equal to the single-particle terminal velocity).

Substituting Eqs. (18) and (20) into Eq. (19), and using Eq. (5) for v

t)
yields the following equation:
NA
dy -3 c 2.8 P
q5 = ~(Gokx107) = D, (U - 1948D ) (v - v,), (21)
Ppi"

 

where U = velocity of the fluid = MA

. . . Bi ¢ .
V = flow rate in precipitator, g-moles Bi/sec,

- e
AC = cross=-sectional area, cm ,
€ = time, sec,
N = nuclei=cm§,
y = mole fraction of ThBi, in bismuth,

2
55

density of bismuth, g/cmz,

Ogn. =
"Bi
MBi = molecular weight of bismuth = 2009,
Yo = mole fraction of ThBi2 at saturation.

This equation must be solved simultaneously with Eq. (16), using the

conditions y = 0.00165 and Dp = O when 6 = 0.

As the particles move in the precipitator, the distance from the

feed inlet can be determined by integrating Eq. (20) to obtain:

o
£ = j U - v [Dp (6)] do. (22)

-

Equations (16), (21}, and (22) were solved numerically; results are
-1

shown in Figs. 8 and 9 for a V/AC ratio of 0.5776 g-mole cmvg sec ,

which represents a fluid velocity equal to the terminal velocity of
a 100~y ~-diam ThBi2 particle. The initial ThBip concentration was
0.00165 mole fraction, and an operating temperature equivalent to Yo

0.00003 mole fraction (i.e., about 370°C) was assumed.

Under the assumptions of the previous calculations, the nuclei
concentration necessary for a specified recovery of thorium (from the
bottom of the precipitator) as ThBip platelets of a specified diameter
can be determined by material balanée. A material balance on thorium

yields the following relation:
34

ORNL DWG 70-4593

 

 

 

 

 

 

1000 -

500 |-
c
S 200 F
e
O
l...
<
-
o
o 100 B
- |
s
" _
O -
I
L |
2
= 50 -
wd

20 -

10 ] | ]

104 2 5 10° 2

N, NUCLE! /cm

Fig. 8. Effect of Nuclei Concentration on Length of Precipitator
Required to Grow 100-p-diam Particles When Fluid Velocity Equals Settling
Velocity of 10C-p-diam Particle.
N
A

ORNL DWG 70—-459¢

100 ;
30
80

70

 

Ll

50

30

20

THORIUM RECOVERED (%)

 

 

 

 

O e
9 L
8 -
7 -
6 L
5 -
4 |
3 ..
2 |
i | | ] L 1
104 2 3 5 7 10° 2

N, NUCLE!l / cm

Fig. 9. Effect of Nuclei Concentration on the Fraction of Thorium
Recovered as ThBie Particles from the Bottom of a 272-cm-long ThBins Pre-
cipitator Producing 100-p~diam Particles.
36

where R = percent of initial thorium recovered,
y, = inlet thorium mole fraction (0.00165 in this case),

N = nuclei/cmi,

and the other quantities are as defined previously.

The maximum amount of thorium that can be recovered in a precipitator
which cools bismuth containing 0.00165 mole fraction of thorium to
570°C (the temperature at which the bismuth contains only 0.0000% mole
fraction of thorium) is 98.2% of the initial thorium present. If one

desires to recover 99% of this value, or 97% of the initial thorium

5 5

present, then, according to Eq. (23), one needs 1.109 x 107 nuclei/cm
in a precipitator producing 100-p-~diam particles. From Fig. 8, the
length of the precipitator necessary to produce 100-p-diam particles
and give 9T% thorium recovery is 272 cm. Equation (23) shows that, in
order to recover a higher fraction of the initial thorium, one must
have a higher nuclei concentration, N; Fig. 8, in turn, shows that the
precipitator must be longer. To obtain the maximum recovery possible,
one would need 1.122 x 105 nuclei/cm5 and an infinitely long precip-

itator.

In order to obtain a high thorium recovery from the precipitator,
one must be able to control the initial concentration of nuclei pre-
cisely. Figure 9 illustrates the sensitivity of the thorium recovery
to the nuclei concentration in a 272-cm-long precipitator producing
100-p-diam particles. The optimum operating point in this case is
just at the peak of the curve. 1If the nuclei concentration in the
feed were to decrease (because of imperfect control), the recovery of
thorium as ThBi, would decrease proportionally, according to Eq. (23).

2

However, if the nuclei concentration should increase, no recovery could
bt

occur because there would not be enough thorium to allow the increased
number of particles to attain a diameter of 100 u; the smaller particles
would be swept through the precipitator. Thus, it is obvious that

control of nucleation rate will be extremely important.

In commercial crystallization operations, nucleation is controlled
by seeding the supersaturated feed solution. This type of nucleation
control is not likely to be possible in the present case since solids
handling would be involved. Programmed cooling of the feed to the
precipitator might be used for controlling the extent of nucleation.
However, no satisfactory method for predicting the rate of nucleation
from solutions11 ig available at the present time. It is obvious that

control of the nucleation rate must be considered further.

L.5 Summary and Conclusions

Even without examining the seccond and third sections of the pre-
cipitator-redissolver complex closely, one can conclude that the op-
eration of a ThBi2 precipitator in the described manuner will be dif-
ficult. The estimated bismuth holdup in the precipitator section 1is

about 30 ft5

, and additional volumes will be held up by the other
sections. The economic penalty associated with this holdup could be

significant.

Three factors that could make the process unsuitable are: (1)
the requirement for precise control of nucleation rate, (2) the im-~-
possibility of rapid particle growth at low temperatures due to a
temperature-sensitive surface reaction, and {3) coprecipitation of
the thorium and rare earths. Further study will be required to com-
pletely assess the feasibility of selective crystallization for sep-

arating thorium and the rare earths.
38

5. MATERIAL BALANCE CALCULATIONS FOR AN MSBR

M. J. Bell L. E. McNeese

A computer code, MATADOR, has been developed to perform steady-state
material-balance calculations that describe, in detail, the nuclear,
chemical, and physical processes taking place in the fuel stream of an
MSBR. Such calculations are necessary to determine fission-product
inventories and heat-generagtion rates, to specify flow rates of streams
in the chemical processing plant, and to investigate the effects of
changes in chemical processing on the nuclear performance of the MSBR.
MATADOR also takes into account the buildup of transuranium isotopes,
the production of activation products by neutron capture in the carrier
salt, and chain-branching in the fission-product decay schemes not

i . . . . . 12
included in earlier investigations.

5.1 Compilation of MSBR Nuclear Data

In order to perform the steady-state material-balance calculations,
we have compiled a library of nuclear data for MSBR applications. This
library contains half-lives and radioactive decay schemesg, three-group
neutron-capture cross sections, and beta and gross gamma disintegration
energies for 667 nuclides. Of these, 178 are isotopes of elements that
comprise the carrier salt, graphite, and structural materials and their
activation products; 461 are fission products and their daughters;and 48
are isotopes of the actinide elements and their daughters. Each isotope
in the library is identified by its chemical symbol, its atomic weight,
and its isomeric state (a blank for the ground state and the character
"M" for an isomeric state). Several nuclides appear in more than one
place in the library; for example, 5H is included in both the fission
products and the activation products. The radioactive decay schemes
allowed include beta and positron emission (to isomeric states and
ground states of daughter nuclides), alpha emission, and isomeric transi-
tion. These decay schemes are based, primarily, on the compilation of

13

Lederer et al. The three-group cross-section library consists of a

thermal cross section, a resonance integral, and a fast cross section
29

: i : : . 14,15
which was generated by averaging over MSR spectra given by Prince
for E > 1 Mev. In addition to the total neutron-absorption cross section,
the library also contains, for each group, the fractions of neutron cap-
tures that lead to fission and to (n,y), (n,@), (n,p), and (n,20) reac-

tions. These data are based on the compilations of Stehn et al., and

N

The fission-product library includes a compilation of direct
2 235 238 232
55U, ij, 2 U, 2 Th, and

Drake.
fission yields from five figsile speciesg -
259Pu — based on the data of Katcoff.l The beta disintegration ener-
gies were calculated by using the computer ccde SPECTRA. This code was
written by Arnold, of ORNL, to compute the average energy of a beta
particle by integration of the Fermi beta-ray spectrum, taking into

19

account changes in spin and parity. A listing of the computer library
is presented in Appendix A. A computer code that reads the data in the
nuclear library from cards has been written. The code also prepares an
array of transition coefficients to be used in the material balance

calculations described below.

5.2 Material Balance Equations

For many purposes, it is adequate to consider the recirculating
fuel salt in a proposed MSBR to be a well-mixed fluid at steady state.
In this case, the average concentration of a nuclide i is defined by

the equation

afi
O = Ve, ., A, + 0V f_ 0. +Ag. . +Ah _+0Vy .0..) N,
_ ( 13°] c ij ] g%ij b1 ClefJ) j
j
+ FN, -(AV+0,0V_+F +AG, +AH +P )N, (2h)
io i i“ e g i bi i i
where Ab = surface area of circulating bubbles, cm?,
A = surface area of graphite, cm?,
F = volumetric flow rate of fuel salt to the reactor, cc/sec,
Gi = coefficient for loss of species i by diffusion into graphite,

cm/sec,
Lo

H, = coefficient for loss of species i by migration to bubbles,
cm/sec,
N, = concentration of species i, moles/cc,
Nio = feed concentration of species i, moles/cc,
i effective chemical processing rate for species i, ce/sec,
= volume of fuel salt, cec,
o ¥ volume of fuel salt in core, cc,
i3 = fraction of disintegrations by species j which lead to
formation of species i,
fij = fraction of neutron captures by species j which lead to
formation of species i,
gij = coefficient for production of species i by diffusion of
species j into graphite, cm/sec,
hij = coefficient for production of species 1 by migration of
species j to gas bubbles, cm/sec,
yij = fission yield of species i from fission of species j,
Ri = radioactive disintegration constant of species i, secbl,
Ui = average neutron-capture cross section of species i, cm ,
0., = average fission cross section of species 1, cm?,
d = average neutron flux, cm"2 secml.

This equation states that, under steady-state conditions, the rate of
input of species i to the fuel salt by direct feed, fission, and radio-
active decay and neutron capture in the fuel salt, graphite, and circu-
lating bubbles must equal the rate of loss of species 1 from the salt
by radiocactive decay, neutron capture, diffusion into the graphite,

migration to gas bubbles, salt discard, and chemical processing.

For the conditions of interest, Eq. (24) is a simultaneous system

of N linear algebraic equations in N unknowms:

0 :2\J a X +b, i=1,2,..,N.
=1

To solve this system of equations, MATADOR employs the Gauss-Seidel
successive substitution algorithm, which is a well-known iterative

2
technique for solving systems of equations of this type. 0

(25)
b1

5.4 Computation of Neutron Reaction Rates

A oumber of quantities must be computed by the code for use in
Eq. (2&). Most important of these are the neutron flux, the average
neutron cross sections, the coefficients for diffusion into the graphite
and migration to the gas bubbles, and the chemical processing rates. The
average neutron cross sections are computed from the 2200-m/sec cross
sections, Infinite dilution resonance integrals, and fast average cross
sections contained in the nuclear library by using a modification of a
convention discussed by Stoughton and Halpe:a:in.g1 In this treatment,

the spectrum-averaged neutron reaction rate of an isotope is:

R = nv [THERM x o(th) + BES x RI + FAST x o([)]. (26)
Here, THERM is defined as the ratio of the reaction rate of a 1/v
absorber with a Maxwell-Boltzmann distribution of neutrons at tempera-
ture T to the reaction rate of the absorber with neutrons whose velocity
is 2200 m/sec (i.e., T TO/MT); RES is the ratio of the resonance flux
per unit lethargy to the average thermal flux; FAST is the ratio of the
neutron flux with energy greater than 1 Mev to the average thermal flux,
and RI is the resonance integral of the isoctope corrected for self-
shielding. Also, o(th) is the cross section of the isotope for 2200-
m/sec neutrons multiplied by the Wescott correction for non-1/v behavior,
and o(f) is a neutron cross section, averaged over a fission spectrum,
for reactions with a high-energy threshold. The value of THERM is
readily computed from the reactor temperature. Values for nv and RES
are obtained from the output of the ROD reactor design code for a given
reactor configuration and processing scheme. (ROD is a wultiregion,
nine-energy-group diffusion code used for the primary design calculations
for the MSBRJE% ROD supplies, for the important neutron absorbers,
average neutron reaction rates that take into account deviations of their
crogss sections from 1/v behavior and resonance self-shielding. For these
materials, the MATADOR cross sections and resonance integrals have been
adjusted to yield the same average reaction rates predicted by ROD.
The value of FAST was estimated by numerically integrating typical MSR

_ « 1,15
spectra reported by Prince.
Lo

5.4 Model for Diffusion of Noble Gases into Graphite

Coefficients for the loss of noble gases by diffusion into the
graphite moderator and for the production of daughters by radioactive
decay and neutron capture are computed in MATADOR, using a model devel-
oped by Kedl and H.outzeel.25 The model replaces the graphite prisms of
the moderator with semi-infinite solid cylinders of the same total area
and surface-to-volume ratio. The surface of the graphite is assumed to
be coated with a low~permeability material to a depth of 1 mil. Dif-
fusion of gases to the bulk graphite is assumed to occur through an
external liquid film and the coating, using a lumped-resistance model.
The concentration of a noble gas isotope in the graphite moderator under
steady-state conditions is described by the following time-independent

diffusion equation in cylindrical coordinates (z, r):

 

vy - (A + o0y, (27)

\

Here, D is the diffusion coefficient of the gas in the bulk graphite,

0- 2
r

oL,
=

in cm?/secJ and Vs is the concentration of the gas per unit volume of
voids in the graphite. Equation (27) must be solved subject to the
conditions of zero concentration gradient at the graphite center line
and equality of flux across the outer surface of the graphite cylinder

of radius R. One obtains the following solution:

hi (mR) kx
y. (r) = 2 -
i hI_(mR) + Dem I,{mR) ~

 

(28)

where X, = concentration of noble gas i dissolved in the fuel salt,
moles/cc,
= void fraction of the bulk graphite,
k = Henry's law constant for the gas in the fuel salt,

mole/cc of void
mole/cc of liquid

 

>
A, + 0,0 1/2
m = characteristic reciprocal length E‘ - D -
Ip(x) = modified Bessel function of the first kind or order p,
Dlelhl

h = lumped surface-film resistance = ETETE“:“ETE 3

cc of void 5

 

2
sec (cm of graphite)
D' = diffusion coefficient of the noble gas in the graphite

coatings,

t = thickness of graphite coating,
€' = porosity of graphite coating,
h' = mags~-transfer coefficient through the salt layer at the

graphite surface, cm/sec.

In obtaining the expression for h, both layers are assumed to be suf-
ficiently thin that the effects of curvature and nuclear transmutation
within the layers are negligible. The rate at which a noble gas isotope
is lost from the fuel salt per unit area of graphite surface is equal to

the flow rate of gas i to the surface of the graphite:

dy Demhk Il(mR) X,
dr R © T h IO(mR) + Dem Il(mR) | (29)

 

The poisoning per unit surface area of graphite by a noble gas isotope
that has diffused into the graphite may be computed by multiplying the
concentration of noble gas by the average neutron reaction rate per
absorber atom in the graphite (assumed to be constant at the same value

as for fuel salt) and integrating over the radius of the rod as follows:

ehk Il(mR) X,
h IO(mR) + Dem t[](mR)'

 

vy (r)dr =% (30)

<0

Similarly, the deposition of a nonvolatile daughter of a noble gas per

square centimeter of graphite surface is:
by

R
A, chk Il(mR)xi

£ - X .
Ai R ' yi(r) dr = m h Io(mR) + Dem Il(mR) (51)
o

 

The concentration of a volatile daughter in the graphite can be

obtained by solving the diffusion equation with a distributed source,

$
dy . }
b a [ 9 |
- T YT | - +~ g & = - v
r dr \r dr ) (kj POgE) vy = et (), (32)
'
subject to the conditions of zero flux at the graphite center line and

continuity of flux at the outer surface,
&
-De & I = h[yj(R) -k Xj)- (33)
'r = R
For the concentration of the daughter as a function of position, one

obtains:

Q; .
h k[ %, + xJ] Io(fir) Ohk IO(mR) X,

Yj(r) = 4% I_(#R) + Des T, (4R) ~ & I_(mR) + Dem I, (mR) - (3k)

 

where ¢ is the characteristic reciprocal length for species j defined

by £
. - A, ~0,0).
j i i

(Aj + OjQ)/D), and & is the dimensionless ratio & = —ejiki/(hj +

The flow rate of material j across a unit surface into the fuel salt
is given by:
f hoka T (£R) h°ka I (mR) |
h [y.(R) - kx.] = « 2 - 2 " x
i i 1 h IO(ER) + Def I, (4R) h I_(mR) + Dem Il(mR); i

 

 

“ hkDe£ I, (£R) “ | -
& I_(#R) + Def I,(4R) | Xy
-J.

 

(35)

S
J4.5

The quantity in the first bracket on the right-hand side of Eq. (35) is
the coefficient for the production of species j in the fuel salt by
diffusion of species i into the graphite, introduced as gji in Eq. (24);
the quantity in the second bracket is the coefficient for the loss of
material j by diffusion into the graphite, Gi- Expressions for the poi-
soning by material j And the deposition cate due to the decay of
species j {which has diffused into the graphite) may also be obtained
by integrating the concentration as a function of position over the
volume of the moderator, but they are not presented here. MATADOR uses
these expressions to compute: (1) the concentrations of the noble gases
in the fuel salt, and (2) the poisoning and the deposition rates, in the
graphite of the noble gases and their first-generation nonvolatile

daughters.

5.5 Model for the Migration of Noble Gases and Noble Metals to
Circulating Helium Bubbles

A model for the migration of noble gases and noble metals to helium
bubbles that are circulating in the MSBR fuel salt has been developed
for use in the MATADOR code. This model is an extension of the model
proposed by Kedl and Houtzeel to treat xenon poisoning in the T.VI,S'RJ‘:?;E3
it treats the bubbles as a separate well-mixed volume in contact with the
fuel salt, and makes use of Kedl's results,gh which demonstrate that the
concentration of noble gas in the bubbles is sufficiently low that it can
be neglected when calculating the rate of transfer of noble gases from
the fuel salt to the helium. It is assumed that a fraction of the bubbles
is stripped on each complete pass of the fuel salt through the primary
salt loop. Nonvolatile daughters of the noble gases and noble metals
are assumed to return immediately to the fuel salt. With these assump-
tions, one may write:

1

O =hAX, + 5—.*‘ (eijhjvb + fijchI)Vb)Nj

]
i
- (\V, + o0V +EQ) N, (36)
L6

where Ab = surface area of circulating bubbles, cme,
ES = efficiency with which the gas bubbles are stripped of i,
Ni = concentration of species i in the gas bubbles, moles/cc,

Qb = volumetric flow rate of the gas bubbles, cc/sec,

Vy = volume of bubbles, cc,
xi = concentration of species i in the fuel salt, moles/cc,
hb = film coefficient for mass transfer to the bubbles, cm/sec.

The other terms have been defined earlier; the prime on the summation
sign indicates that the sum includes only the noble gases and noble
metals. There is one equation of this type [i.e., Eq. (36)] for each
noble-gas and noble-metal isotope; and, since the equations are linear,

the system can easily be solved by standard techniques.

5.6 Assumed Chemical Behavior of Fission Products

The MATADOR code treats the chemical processing of the fuel salt
by combining the figsion products into groups of elements of similar
chemical behavior. Each group of elements is assumed to be processed
on a characteristic cycle, and individual elements are assigned a |
removal efficiency. Thus, with this procedure, the removal time for
each element is equal to the cycle time for its characteristic group
divided by its removal efficiency. The principal groups of chemical
elements and their processing cycle times are given in Table 2. The
efficiency for each element except europium (efficiency, 0.222) is,

at present, equal to 1.0.
W

Table 2. Chemical Groups and Process Cycle Times in Reference MSBR

 

 

Chemical Principal Processing
Groups Elements Cycle Time
Noble gases Kr, Xe 50 sec
Noble metals As, Se, Nb, Mo, Tc, ]
Ru, Rh, Pd, Ag, Te o0 sec
Seminoble metals Zn, Ga, Ge, Zr, Cd,
In, Sn, Sb 200 days
Rare earths Y, La, Ce, Pr, Nd, Pm, .
Sm, Eu, Gd, Tb, Dy, Ho, Er oL days
Halogens Br, 1 50 days
Active metals Rb, Sr, Cs, Ba 5000 days

 

5.7 Material Balance Calculations for a 1000-Mw (electrical)
Single-Fluid MSBR

The MATADOR code has been used to compute inventories and heat-
generation rates in the fuel stream of a 1000-Mw (electrical) single-
fluid MSBR [which is equivalent to a 2250-Mw {thermal) single-fluid
MSBR]. The reactor is fueled with 1461 ft5 of salt having the nominal

composition TL.7-—16.0—12.0-~0.% mole % LiF -BeF —ThFM—UF Protactinium

2 '
is removed from the system on a 3~day cycle, and fuel salt is discarded
on a 3000-day cycle. The fission products are removed as described in
Sect. 4.4.6. Typical MATADOR output is given in Appendix B. Table B-1
includes pertinent input data (such as reactor power, thermal neutron
flux, spectral indexes and parameters for diffusion of noble gases to
the graphite) for the calculation. Removal times for the chemical
elements are given in Table B-2. Table B-5 gives the molar density,
mole fraction, neutron absorptions, activity, specific heat~generation
rate, specific gamma power, and molar processing rate for each isotope
in the fuel salt. This table concludes with summaries of the specific
heat -generation rates, neutron absorption rates, and chemical processing

rates for the elements. Table B-4 lists: (1) the 25 most important
L8

fission products and heat sources in the fuel salt, (2) the most con-
centrated isotopes in each of the streams of fission products leaving
the primary salt circuit, and (3) the most important heat sources in

each of the fission-product streams. Table B-5 gives the flow rates

and heat-generation rates of each of the fission-product streams.

Table B-6 includes a material balance for thorium consumption in the

reactor.
10.

11.

12.

15.

4.

15.

16.

e
6. REFERENCES

M. E. Whatley et al., Unit Operations Section Quarterly Progress
Report, July-September 1968, ORNL -Lz 7 |

 

 

L. E. McNeese and M. E. Whatley, MSR Program Semiann. Progr. Rept.
Feb. 29, 1968, ORNL-425k4, p. 248.

J. C. Hesson, H. E. Hootman,and L. Burris, Jr., Electrochem. Technol.

3, 20k (1965).

 

J. W. Cooke, ORNL-TM-2316, p. 1lhi.

L. E. McNeese, MSR Program Semiann. Progr. Rept. Feb. 28, 1969,
ORNL-L296, p. 273.

 

J. A. Lane, H. G. MacPherson, and F. Maslan, Fluid Fueled Reactors,
p. 275, Addison-Wesley Publishing Co., Inc., Reading, Mass., 1958.

 

J. Brynner, Progr. Rept. Nucl. Engr. Dept., May 1-Sept. 30, 1957,
BNL-LT7T.

 

A. S. Foust et al., Principles of lnit Operations, p. 450, Wiley,

Evwen r—

New York, 196L.

 

Tbid, p. 451.

W. L. McCabe and J. C. Smith, Unit Operations of Chemical Engineering,
p. 815, McGraw-Hill, New York, 1956.

 

C. S. Grove, Jn, et al., "Crystallization from Solution," p. 22 in

Advances in Chemical Engineering, vol.3, ed. by T. B. Drew et al.,

 

Academic, New York, 1962.

J. S. Watson, L. E. McNeese, and W. L. Carter, MSR Program Semiann.
Progr. Rept. Aug. 31, 1967, ORNL-~4191.

 

 

 

C. M. Lederer, J. M. Hollander, and I. Periman, Table of Isotopes,
6th ed., Wiley, New York, 1967.

 

B. E. Prince, MSR Program Semiann. Progr. Rept. Feb. 28, 1967,
ORNL-L4119, pp. T9-83.

 

B. E. Prince, MSR Program Semiann. Progr. Rept. Aug. 31, 1967,
ORNL-4191, pp. 50-53.

 

J. R. Stehn et al., Neutron Cross Sectioms, BNL-325, suppl. 2,
2d ed. (196L4), pp. 1-111.

M. K. Drake, Nucleonics 24, 108 (1966).
18.
19.

20.

21.

22 .

0%,

2l .

50

S. Katcoff, Nucleonics 18, 163 (1960).

E. D. Arnold, Handbook of Shielding Requirements, ORNL-3576 (196k4),
p. 21 ff.

L. Lapidus, Digital Computation for Chemical Engineers, McGraw-Hill,
New York, 1967.

R. W. Stoughton and J. Halperin, Nucl.Sci. Eng. 6, 100-118 (1959).

0. L. Smith, W. R. Cobb;and H. T. Kerr, MSR Program Semiann. Progr.
Rept. Aug. 31, 1968, ORNL-h34L, p. 68.

 

 

J. Kedl and A. Houtzeel, Development of a Model for Computing
155Xe Migration in the MSRE, ORNL-4069 (1967).

 

R. J. Kedl, MSR Program Semiann. Progr. Rept. Aug. 31, 1968, ORNL-
Wshl, pp. T2-75.

 
APPENDIX A. LIBRARY OF NUCLEAR DATA FOR MSBR APPLICATIONS
NUCLEAR TRANSMLTATICN DATA

NUCL = NUCLIDE = 10000 * ATGMIC NO + 10 * MASS AC + ISCMERIC STAYE {C CR 1) DLAM = OECAY CONSTANT {1/5ECi.
FB, FP, FA, FT = FRACTIONAL DECAY BY BETA, POSITRCN {(OR ELECTRON CAPTUREJ}s ALPHA, INTERNAL TRANSITICN, FB = 1 - FP -~ FA - FY
F81, FPl, FNGLl, FN2N! = FRACTION OF BETA, POSITROM, N—-CAMMA, N-2N TRANSITICONS TO EXCITED STATE OF PRODUCY NUCLIDE
SIGTH, SIGNG, SIGF, SIGNA, SIGNP = THERMAL CROSS SECTICNS (BARMS) FOR ABSCRPTION, N—-GAMMA, FISSICN, N-ALPHE, N=PROTON.

SIGNG = SIGTH * (1 - FMA —-FAP)s SIGNA = SIGTH ¥ FNA. SIGNP = SIGTH * FMP. FNA, FNP = FRACTION THERMAL N-ALPHA, N=-PROTON.
RITH, RING, RIF, RINA, RINP = RESONANCE INTEGRAL FOR ABSCRPTIOM, N-GAMMA, FISSIOM, N-ALPHA, N=-PROTON,

RING = RITH * {1 = FINA ~ FIiNP)e RINA = RITH * FINA, RIAP = RITH * FINP, FINA, FINP = FRACTICON RESONANCE N~ALPHA, N-PROTON.
SIGMEV, SIGFF, SIGN2N, SIGNAF, SIGNPF = FAST CROSS SECTICNS (BARNS}) FOR ABSORPTICGN.FISSIONy N—2Ns N-ALPHA, N-~PROTON.

SIGN2N = SIGMEY #* (1 - FFMA = FFNP}. SIGNAF = SIGMEV * FFNA., SIGAPF = SIGMEY * FFNP. FFMAs FFNP = FRACTIOM FAST N=ALPHA, N=-P.
Y23, Y25, Y02, Y28, Y&9 = FISSION YIELD {(PERCENT! FROM 233-U, 235-U, 232-THe 238-U, 239- Pu,
QO = HEAT PER DISINTEGRATION, FG = FRACTICON CF HEAT IN GAMMAS CF ENERGY GREATER THAN 0.2 MEV,

EFFECTIVE CROSS SECTIONS FOR A VOLUME AVERACED THRERMaAL (LT 0,876 EV) FLUX ARE AS FOLLOWS.

N=GAMMA -~ SIGNMG % THERM + RING * RES,

FISSICN = SIGF * THERM + RIF % RES ¢ SICFF *x FAST,. THERM = 1/V CORRECTION FOR TRHERMAL SPECTRUM AMD TEMPERATURE.

N-2N - STGN2N % FAST. RES = RATIQ OF RESONANCE FLUX PER LETHARGY UNIT TO THERMAL FLUX.
N=ALPHA = SIGNA % THERM + RIMA # RES + SIGNAF ¥ FaST, FAST = RATIC OF FAST (GY 1.0 MEV) TO THERMAL FLUX.

N=PROTCN = SIGNP * THERM + RINP * RES + SIGNPF % FaS§T,
FLUX = 1.50E 13, THERM = 0.4360. RES C.0805, FAST 0.C762C FCR 235-U FUELED MSRE AT T.5 MW{TH)

FLUX = 2,7T0F 13, THERM = 0.4660y RES = £,1100, FAST = 0,043 FCR 233-1 FUELED MSRE AT 7.5 MW{TH}

FLUX = 3.70F 14, THERX = (0,379, PRES = G,1027, FAST = 0.05 FCR TWC REGICN MSBR AT 556 MW{TH)

FLUX = 4,90F 14, TFERM = 0.2791, RES = 0.1027, FAST = 0.05 FCR ONE REGION MSBR AT 4444 MWITH)

FLUX = 2,315 14, THERM = D.306, RES = 0,0693, FAST = 0.05 FCR STANGLE FLUID MSBR AT 2250 Me{TH)s CASE HK-G-30
REFERENCES

HALF LIVES, DECAY SCHEMES, AND THERNMAL POWER
£ M LEDERER, J M HOLLANDER, AND I PFRLMAN *TABLE OF [SCTCPES - SIXTH EDTTION® JOHN WILEY AND SONS, INC {1967}
B § QIHELEPOV AND L X PEKER 'OECAY SCHEMES OF RADIOCACTIVE NUCLEI* PERGAMMCN PRESS {1961
D T GCLDMAN AND JAMES R ROSSER 'CHART OF THE NUCLIDEST NINTH ETITION GENERAL ELECTYRIC €O (JULY 1566)
£ D ARNOLD *PROGRAM SPECTRA® APPENDYIX A OF CRNL-3576 {APRIL 1964}
CROSS SECTICNS AND FLUX SPECTRA

B F PRINCE *NEUTRON REACTION RATES IN THE MSRE SPECTRUM® ORNL-4119, PP T79-B83 {JULY 1967)

B E PRTNCE 'NEUTRON ENFRGY SPELTRA IN MSRE AND MSBR® ORNL-4191, PP 50-58 {0EC 1967)

M D GOLDBERG EY AL YNEUTRCN CROSS SECTIONS® BNL-325, SECCKD ED, SUPP NO 2 (MAY 19564 - AUG 19560 ALSD EARLIER EOITIONS

B T KERR, UNPUBLISHED FRC COMPILATION {FEER 15568)

M K DRAKE tA CCMPTLATION OF RESONANCE INTEGRALSY NUCLECMICS, VCL 24, NC 8, PP 108-111 {(aUG 19661}

BNWL STAFF * INVESTIGATION OF N-2N CROSS SECTIONS® BNWL-G8, PP 44-G8 {JUNE 1965)

H ALTER ANLC £ ¢ WEBER *PROUODUCTION OF H AND HE IN METALS CURING REACTCR IRRADTATION® J NUCL MATLS, VOL 18, PP 63-73 {1965)
Lt BENNETT YRECOMMENDED FISSION PRODUCTY CHAINS FOR USE IN REACTCR EVALUATION STUDIES' CRML-TM-1658 (SEPT 1955}

FISSICN PRDEUCY YIELDS
S XATCOFF * S1SSTCA PRCOUCT YIELDS FROFM NEUTRON INDUCET FISSICAN® NUCLEONICS, VOL 18y NO 11, (NOV 15609
4 H GOODE *HAY CFELL EVALUATION OF THE RELEASE OF TRITIUM AND 85-KR DURING PROCESSING OF U02-THO2 FUELST GRNL-3956 {JUNE 19661

A4
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NUCL DLAM F81 FP FP1 FT S IGNG RING FNGL Y23 Y25 Yoz Y28 Y49 C FG
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GD16Y 3,12E-03 0.0 0.0 0.0 Ce0 0.0 0.0 0.C L, 00E-05 T7.60E-05 1.00E-05 1,60E-03 2.90£-03 1.030 0.390
TB161 1.16E-06 0.0 0.0 0.0 0.0 Ce 0 6.0 C.50C 0.0 0.0 0.0 0.0 0.0 0.275 0,063
OY181 0.0 0.8 O 0 0,0 0.0 6« C0E 02 1.67E 032 0.0 Je 0 2.0 0.0 0.0 0.0 0.0 0.0
G162 2.20E-08 1,000 0.0 0.0 0.0 0.0 Ge0 0.0 2.7T0E-05 3.,90E-05 7.Q00E-06 8.00£-04 2.00£-03 0,574 C. 0
TB162M 1454E-03 0.0 0,0 0.0 0.0 Q.0 0.0 t.C Q.0 GC.0 0.0 0. 0 0.0 1,130 G.0
TB16? B8.75E-05 0.0 0,0 0.0 0.0 G0 0.0 0.C 0.0 0.0 0.0 Q. 0 0.0 1.130 ¢, 0
bYle2 0.0 0.0 0.0 0.0 0.0 1.60F D2 3.32E 03 C.0 0. ¢ 0.0 00 0.0 0.0 C.Q 0.0
TB143M 1.,65F-03 0.9 0.0 0.0 0.0 0.0 G.0 0.0 1. 20E-05 1.80E-05 0.9 1.B0E=-04 4.50E-04 0,825 0.3190
TB163 2.96E-05 0,0 0.0 0.0 0.0 0.0 0.C 0.0 J. 0 0.0 0.0 1., 80E-04 4.50E~04 0.825 0,310
DY1s63 0,0 0,¢ 0.0 0«0 Q0 1.258 €2 1.%56E 03 0.0 .0 0.0 0.0 0.0 0.0 0.0 0.0
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nyYies 0,0 0.0 0.0 0.0 0.0 2.TOE 03 3,77€ 02 0.74C 0.0 G.0 0.0 0.0 0.5 0.0 C.O
DY165M 2.,17£-03 0.0 0.0 0.0 0.0 0.0 0.0 Q.0 a0 Q.0 0.0 B, 60E-05 1.30E-04 C0.569 0,022
DY165 B,30E-0% 0.0 0-0 0.0 0.0 4. T0FE C3 0.0 0.0 C.0 C.0 0.0 0.0 0.0 0.53% 0.027
HO165 0.0 0.0 0.0 0.0 0.0 6. TCE 01 8.&0E 02 Ce015 Gu0 G0 3.0 0.0 C.C 0.0 Cel
DY166 2.36E~06 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0e 0 0.0 0.0 2e TOE-C5 £.B0E-05 0.143 8.0
HOl66M 1,.828-11 0,0 0.0 0.0 0.0 0.0 0.0 C.0 0.0 0.0 C.0 0.0 G.0 1. 817 (.88
HO166 T.16E-06 0,0 0.0 0.0 0.0 0.0 Q.0 0.0 0.0 D40 0.0 0.0 0.0 06739 (a0
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67

APPENDIX B. TYPICAL MATADOR OUTPUT FOR A 2250-Mw (thermal)
SINGLE-FLUID MSBR
68

Table B-1. Sample Conditions for a Typical MATADOR
Calculation for a 2250-Mw (thermal) MSBR

 

Mean thermal neutron flux, cm-gsecm1 6.62 x 1057
Power, Mw (thermal) 2250

Salt feed rate, g-atom/sec 0.02148
Thermal spectrum factor 0.5
Resonance spectrum factor 0.108

Fast spectrum factor 0.075
Graphite area, cm2 2.57 % 10T
Salt volume, e’ b1 x 107
Graphite rod radius, cm 3.1

, . id
Graphite porosity, %%—%%—é%i;%zgg 0.1

Mass transfer coefficient for Kr to graphite, cm/sec 9.2 x lO“Pr

Diffusivity of Kr in graphite pores, cmg/sec 3.1 x 10_’5

Solubility of Kr in fuel salt, _l,
(moles/cmd of salt)/(moles/cm® of gas) 5.0 x 10

Ratio of graphite volume to salt volume in core 2.0

Mass transfer coefficient of Xe to graphite, cm/sec 9.2 x lO-rr

Diffusivity of Xe in graphite pores, cmg/sec 2.5 x 10'5

Solubility of Xe in fuel salt, )
(moles/cm® of salt)/(moles/cm5 of gas) 2.0 x 10

 
69

 

 

Table B-<Z. Removal Times tor the Chemical Elements in a
Typical MSBR Reprocessing Plant
Atomic Removal Atomic Removal
No. Element Time No. Element Time
1 H 50 sec 51 Sb 200 days
2 He 50 sec 52 Te 50 sec
3 Li 3000 days 5% I 50 days
b Be 3000 days 54 Xe 50 sec
5 B 50 days 55 Cs 3000 days
6 C 3000 days 56 Ba 3000 days
T N 50 sec 5T La 50 days
& 0 50 days 58 Ce 50 days
9 F 3000 days 59 Pr 50 days
10 Ne 50 sec 60 Nd 50 days
11 Na 3000 days 61 Pm 50 days
12 Mg 3000 days 62 Sm 50 days
13 Al 3000 days 63 Eu 50 days
1h Si 50 days 6l Gd 50 days
15 P 50 days 65 Tb 50 days
16 S 50 days 66 Dy 50 days
17 cl 50 days 67 Ho 50 days
18 Ar 50 sec 68 Er 50 days
19 K 3000 days 69 Tm a
20 Ca 3000 days T0 Yb a
21 Sc 50 days 71 Lo a
22 Ti 50 days T2 Hf a
2% v 50 days T3 Ta a
ol Cr 200 days Th W 200 days
a5 Mn 200 days TS Re a
26 Fe 200 days 76 Os A
27 Co 200 days TT Ir a
o8 Ni 200 days 8 Pt a
29 Cu 200 days 79 Au a
30 Zn 200 days 80 Hg a
z] Ga 200 days 81 T1 200 days
2 Ce 200 days g2 Pb 200 days
332 As 50 sec 83 Bi 200 days
3 Se 50 sec 8L Pd 50 sec
35 Br 50 days 85 At 50 days
36 Kr 50 sec 86 Rn 50 sec
37 Rb 2000 days 87 Fr 3000 days
38 St Z000 days 88 Ra 3000 days
3G Y 50 days 89 Ac a
40 71 200 days 90 Th 3000 days
L1 Nb 50 sec 91 Pa % days
Lo Mo 50 sec 92 U 6200 days
Lz Te 50 sec 93 Np 8200 days
Ik Ru 50 sec gl Pu 8200 days
L5 Rh 50 sec 95 Am 50 days
L6 Pd 50 sec 96 Cm 50 days
b Ag 50 sec a7 Bk a
L8 cd 200 days 98 cf a
L9 In 200 days 99 Es a
50 Sn 200 days 100 Fm a

 

a
ILsotopes of these elements are not included in the calculations.
Table B-3. Calculated Nuclear Properties of Isotopes in the Fuel Salt

of a Typical 2250-Mw (thermal) Single-Fluid MSBR

STEADY STATE VALUES FOR THE L IGHT ELEMENTS

NUCLICE CONCENTRATION MOLE FRACTION DOISONING ACTIVITY POWER CENSITY GAMMA HEAY PRCCESS RATES
GM=-ATOM/CC ABS/ABS{FUEL) CURIES KW/t ITER KW/LITER MOLES/DAY
H 2 Nebhbhbbur-12 0.12391¢-10 0.0 GaTI556E 0D 0,666£TE-12 0.C 0. 56102E-01
H & 0.95425£-1€ C.18248¢E-173 0. 25204E-02 C.0 0.0 0.0 D« 6B26TE=-04
HE 32 0,57540E~19 Cs11063E-17 0. 32658F-146 C.0 0.0 0.0 Oa41164E=-08
HE 6 N.150138~-132 V. 2RBH5E=12 0.0 0.BESECE 07 0.19598E~-02 0.0 0.10T4CE-Q2
it 5 0.35120E-0¢6 Q.6 T526F=05 0.37753£=02 0.0 C.0 040 QeuBabEE-0Q2
Ly 7 0.327253E-C1 0.71525F 00 0.15634E-01 C.0 0.0 0.0 0.53409€ 03
Lt 8 0. 57809F-113 DJI1115E=-11 0.7 C.32148¢ 0B G,.39103E-01 0.0 Q0e79777E~-D9
R =® 0.12089c-1 0.23244E-15 C.0 0.56473¢ 08 e TEBLGE-C3 0.0 Oel5683C=12
8E 9 0.82966E-02 0.,159%2EF OO 01786701 0.0 0.0 0.0 D.11449E G3
8t 10 0.1£9A65.05 Q.22¢660E-04 C.0 0.10088E 02 0.0 0.0 De23441£-C1
B i Gs 400 39E-13 Q. 7h983E~-12 C,18112E~08 C.0 0.0 0.0 0.33152E-C7
8 1% 0. 566802E~30 0.128B484F=27 Ce 3580CE-31 0.0 0.0 0.0 0.552128-24
312 0. 32044F =44 Deb1612E~43 Ue 0 0.T4844E-22 Q.58625E-31 0.82350€-33 0.26533E£-323
T 12 0. Z28785F=-34 0.55346€E-33 Oa12121E=-35 c.0 G.0 C.0 0e39724E=-30C
€1z 0.,11703E-11 0.22502E-10 0. 22555E-13 a.C 0.0 0.0 Q. 16151E~07
€14 0.29841F-15 0.5737SE-14 0,0 0. 7T0SCE-06 0.,55222E-17 0.0 Oe%1180E=-11
N 13 0.2C624F-42 0.39654F-41 0.0 Celbl21E-24 Q.34412E-24 C.23400€E-34 0.14754E-31
N 1& C.5T195E-25 C.10997E-23 Gel3551E-23 J.90 0.0 0.0 0.40917E-14
N 18 0.715085¢€-35 Q.1374RBE-33 Da39971E-39 Q.0 0.0 G.0 0e51154E~-24
N 16 «13877E-12 D.266816-11 O.0 C.,91299E 07 0.98361E=-02 Q. 6491 8E~-02 0e99273E-02
G 16 0,5%492E=-0T 0.133%61£-08 0,12050E-07 €0 0.0 0.0 0+57540E-01
G 17 0. 14300F-12 Q. 27T4088-11 V.3E8TB2E-12 G.C 0.7 C.C D.11841E-0e
g 19 0,562624E5-132 0.12041E~-11 0.0 c.locave o7 0.393C9€-03 0.,16510E-03 0.51853E£~-07
F 19 G.81882E-01 « 157445 0L 0.21595E-01 Q.0 0.0 G.0 0.11300E D4
£ 20 0. 78740€~12 0.15139E-10 0.0 0«3343¢E 08 0.19785£-01 Vs771861£-02 0.10856€6E-07
NE 20 D.24808E~11 0.4T7Hh99E-10 0e 1849QE=-12 Ce0 0.0 Va0 0.17748E 00

0.
STEADY STATE VALUES FOR THE ACTINICES

NUCLIDE CONCENTRATION MOLE FRACTION PCISONING ACTIVITY POWER DENSITY GAMMA HEAT PROCESS RATES
Gm—ATOM/CC ABS/A3S{FUEL) CURIES KW /LITER KW/LITER MCLES/DaY
HE 4 0.16170€E-13 C.21090E-12 0.9 Ca0 0.0 0.0 O.11568E-02
Te208 0. 16564F-14 0.31847E-15 0.0 Ge41597€ 02 0.19656E-07 0.161685E~07 Oe342BTE-11
PB20R 0,29628E~-11 0.56965E5-10 0.0 Qa0 0.0 0.0 0,61329E-06
pp212 Da9aTITE-14 «28223E-12 0.0 O« 11556F O3 0.49512€-08 0.29806E-08 Je19619E-08
81212 0.89944E-15 J.172968-113 0.0 0.11%555E 03 D.44862E-Q7 0.14356F-08 0.18618E-05
pa212 Qa15831£-22 0.3043RF=-21 0.0 CeT3951E 02 0.94716E-C7 0.0 Oe11325E-11
PN21é 0.192112-16 0.3693RE-18 0eD 0.5982¢¢f 02 0.59123E-207 Q.0 COa 13744E-08
RN220 0.72033F=17 0,13880E=-15 0.0 C.60087€ 02 0.55059E-C7 0.0 0.51532E-0¢
RA224 D. 10582812 0.20245%E-11 0.1352CE=10 0,1%718F 03 0.13020E-C6 0.26040E=09 0.14603E-08
TH2238 0,203208-1 0.29069E-09 0,25962E=07 0.1574EF 03 Ne12465E~06 0.0 0,28041E-08
TH22C 0.29597E~CE& 0.56R99E-07 0.10082E=-08 C.£00CSE 01 0.43845£-CB 0.0 Ce40B2GE-04
TH230 0s2856331€-09 C.55050E~0D8 Q. 72860E-06 Cs52578E-D1 De3618%E-10 0.0 Ge 39511£~-05
TH231 Uel 5305E-CH Ce2C42TE-DB 0.0 Ca77516E 05 0.25896E-0C4 0.11135E-04 GeZ21121E-C5
TH232 0.621195-02 C.11944f 00 0,98176€ OC C.65215% 01 0.38120E~-08 0.0 0.B5T724E 02
TH223 Os58465F-08 0.,11241E-06 0.9B5646E~-04 0.2059¢% 10 Q0.12393E 0O 0.0 0e 80682804
PA231 0.49512E-09 0.95196E-08 0.16C3GE-06 (e 22551E QO 0.16632E-09 0.0 0.40996E-02
PAR32 T4 60710E-12 0.11673E-10 0.2 Ge24867E G4 0+19950E~-05 D T9800E-07 04 50268E~05
PA232 0.11674F~05 0, 22446E~04 0.37R87TE-02 Ce2303¢E 09 0.13465E-01 0.10772E-Cl 0.95664E 01
PA234LM 0. 61233E=-12 0.,117173E~-10 0.0 G.40744F O7 J.50726E~-03 0.T608BE-05 0.50701E-CS
PA234 0. 18886E-09 D.36%12E-08 0.0 Ce26305E 07 0.38421€E-03 0.T1621E-D3 0., 15637E-02
U232 G.12837E-08 De247TTBE-07 0.37273E-05% C.264S5E 03 0.20551£~-06 U0 O.551C8BE-CS
U233 0. 10690E-03 0.20553F=-02 (. 92&45E Q0 CaGT6TTE 04 0.58695E~038 C.0 3e54006E 00
1234 Ce38008E~-04 0.73078£-03 0.782C18-01 Q.22778E D4 0.15847£-05 G0 0.19202E CO
u23s 0. 9€£281E-0% C.18%125-03 0 73513E~01 Ce20CT4E~D2 Oe13459E-11 0.0 Oa486423E-0]
U236 0.11204E-04 0,21542€E-03 0,8£338€-02 £ 69393EF 01 Ou45463E-0R 0.0 0.56604E-01
yz237 0, 22585F-C7 0. 43367E=-06 0.0 Ve LEOGLE 08 Q.93555E-03 0e66523E-03 0013395€-03
U238 0.29200E~11 0.56144E-10 0. 156%2E-08 0.95841F=-08 0.58603£-17 0.0 O« 14T53E-07
uz3g D L2485E=16 L.24004E~-1% 0.0 Ce 13562 01 0.237ClE-CY Ve 0.563075E-13
NP23& D.19112F-172 C.367T4TE-12 0.0 0.,11273E 03 Q.768713E-C8 0.0 0.96559E-1C
NP23T O« 14659E-058 0.2837204F-04 0. 79206E-02 0.10147€ 02 0.0 0.0 0. 74110E-02
NP22 8 0. 63B20F-08 0.12273E-06 Q. 1CET4E-D2 O.16434E 08 0.203892-32 0.14068E-02 04 32248E-04
NP22G 0. T594BE=-14 De146032E-12 0.,48%19E-11 C.17473E 02 0,12517€~-08 0.81357E-Q9 0.38370E=-10
PL235 D. 54542E=11 D.12416E-09 0.,11€83E=37 Ca33523E 02 0.,28192€E-C17 0.0 D 32608E-07
py23R D.121205-05 0.23303E-04 Do T1E59E=C2 0.20158E 06 0.16135E-03 0.0 0.61232E-02
Py239 0,163 66E-05 0.37235E-05 D,67R28E-02 Cel174SE 03 0.8B2495-07 C.0 0,97840E-03
Py240 D 10604E=-06 0.2038BE-05 0. 258453E-02 Ca23220E 03 0.16816E-06 C.0 0 535 73E-03
PL241 0.91148E-27 0.17529E-05 0. 2453602 C.10381F 06 0.10411&-06 G0 0. 46060E-03
PU242 0.17727E-06 C.34084£~-05 0,55991£~03 G.469237E 01 0,49398E-08 0.0 0.89561E=-0%
PU2432 0.45198F-10 0.856902E-09 C. 0 0.11777€ 07 0e404G2E-CQ4 Qe 76935606 0. 22B35E-06
AM24 1 0.52521E-09 C.1C009EE-07 0.10388E-04 G« 16975E 02 0.13619E~CT 0.0 De43487E-03
AMR42M 0. 10542E-10 0.20270E-09 0. 8580CE-06 Ce10267E D21 C.70602E-11 Ce0 0.87290E-05
AmM242 0.216542~11 D.422115-10 Cs 6TTESE-07 0.17804F% 05 0.573%52E-Ch C.0 0.18178E-D5
AMZ473 0. 6S017E£-98 0.13270E-08 Go48205E~04 C.13358E 22 J.95835E-08 Q.0 Oe57T140E-C2
AM244M 0., 31895E-12 0.461324F-11 0.0 D.95502E 05 0., 82093E~-0F% G0 Oe 26409E=-06¢
AM244 Oabt242E-12 G.83506FE-11 0. 1{835E-07 0., 5868398 04 0.92016E-CH 0.8097T4E~D6 O« 36032E-06
CM242 0. 75904E=10 C.14786E-08 Os 24565E-07 £.2550%E 04 0.2272GE-C5 0.0 0.63H675E=04
CM243 0. 29493E-12 Ce56T707E-11 Da28637GE-CE Ce13643E 0D D.12042E~C9 0.0 De26421E~06
CM244 0. 62007E-09 0.12114E-07 0. 11314E-05 CeS51529E 03 D.42818E-06 Q.0 0.521T0E-03

1L
STEADY STATE VALUES FCR THE FISSICN PRODUCTS

NUCLIDE CONCENTRATICN MOLE FRACYINON POISCNING ACTIVITY POWER DENSITY GAMMA HEAT PROCESS RATES
GM=ATOM/CC ARS/ABS(FYEL) CURIES KW/LITER KW/LITER MCLES/DAY
H 2 0. 157903E-13 0.303455E-12 J.0 C.19CQ8&E-01 0.52280E-13 0.0 0.11298E-02
IN T2 0.126225-1 0.242609E-10 0.0 D.35222E 04 0.12413E-08 0.104627E-0T 0.26128E-06
GA 72 0. 3B8112E-22 0.73279E-11 0.0 C.35073E 04 0.,1738&6E~-05 De149528-05 0.73892E-01
GF 72 0.89427E=1C 0.17i94£-08 0.92313E-08 Cel 0.0 0.0 D.18511E-04%
GA 73 Qe 1531F-12 CeT7922E-11 0.9 C.10733E Q5 0.10348E-0CS 0.0 0.83B898E-07
GE 73 0.27250E-09 0.52587E=-08 0. 407TCE-07 Ce0 C.0 0.0 Qe 58615E-04
GA 74 0.18633¢-13 0.35634F-12 Va0 0.18284¢ 05 0.10545E=-04 0.75922E-05 G.38364E-08
GE T4 0.47028FE-09 0.90440E-08 Us22528E-08 Ca0 0.0 0.0 0.97368E-04
GA 75 0,139237~13 0.26T69E=-12 Oe0 C.54196E G5 0.15T762E-04 Qeh4921E-08 0.286820E-08
GE 75m 0.52463c-14 0.10279E-12 0.0 C.52030¢ 05 0.10436E-05 B.0 G.110467E~-08
GE 75 0. 57N6k&E-12 0.109T2E-1D 0.27342E-1C 0.54178E 05 0.36015E-05 0.25570E-06 O.11812E-06
AS 75 0.40367F-14 Ca776T1E-13 De584T6E-12 0.0 0.0 0.0 0.28899E-03
GA 76 D.631469F-14 O.121465-12 2.0 C.92212E 05 De43232E-04 0, 13664E-05 0. 12076E-C8
GE 76 0. 23639E-08 T.65451¢C-07 J.98765E-08 C.0 0.0 0.0 De48932E-0C3
AS 76 0.86538F=-22 0.16548E-20 0.0 Cea2390E-06 Ue11569E-14 0.20823&-15 0.19811E-1C
SE Ts De1454F=25 DeHb0BROE-24 0. 284£GF=22 .0 0,0 Q.0 C.1B0B4E~-13
GE 77w 0.276215-13 D.53106£-12 0.0 C«23BS3E 06 0.37654E-C4 Q.64012E-06 0.57175E-08
GE 77 0.17426F-10 0.33505E-09 0.0 0.20010F 06 0.507T42E~Cé 0.32489E-04 0.386072E-0GS
AS 17 0,28312F=12 0.54435E~12 0.0 CeS4926E 02 0.10223E-07 0+21468E-09 0+20263E-0C2
SE 7M™ 0.T0890E-20 C.13620E-13 0.0 C.1B923¢f 0O 0e17904E~-10 0.0 0.71508E-C9
77 0. 7038717 U.13528F-15 Je 3615£E-14 0.0 0.0 C.0 0.16109E-05
GE 78 3.12341F-10 0e23T727F-09 0.0 C.10893E 07 0.,81307TE~-04 0.43906E-04 De25545E-05
AS 78 0. 80309€-12 N.15441F-11 0.0 U+ 6870858 04 0. T0199E-05 0.25272E-05% 0.56661E=-02
SF 718 0.50974F~-15 C.98B00BF-14& Ga23338E-14 C.0 0.0 0.0 0.11559E-02
AS T¢ 0.12968E~172 De24T41F=11 0.0 C.11131E 06 0.0 0.0 0.806€64E-02
SE T79M 0.71928E-14 0.13°30E-12 0.C C.14359¢€ 05 0.12504E-05 0.0 0.12471E=02
SE 79 0.10653E-14 0.20482E-13 0.4%492908-13 C.2426CE-06 0.33211E-15% 0.0 0.48255E-03
BR 7o 0.22490E-10 0,43241E~-39 0.10500E-07 Cel G0 0.0 0a1B622E-C4
AS 80 0aB34T1E-12 0,16049E-11 0.0 0.2%5488E 0T 0.15430FE~-02 0.32403E=-02 0.997¢9E-03
5F 80 0.18912F-172 Ve36362FE-11 0.15893E-11 C.0 0.0 0.0 0.18503E-01
BR a(QOM Oe23219E-12 0.864543E-11 G.0 Q. 68786E 04 0.84750E-C7 0.0 0.19225E-0¢
BR &0 0.15533-13 C.29961EF-12 0.0 C.68G28E 04 0.86406E-06 0.11233€-06 0,12902E-07
KR 80 Ns4TOLIE=-15 0.90445E=~14 0. 6356GE=-09 d.0 0.0 0.0 0.33653E-04
AS A1 0.15775=~-13 0.3903316-12 0.0 0.22331F 0% 0.88932E-04 0.0 Je34090E-03
SE 81M 0. 186401€-172 0,31535¢-12 0.3 C.22401E 04 0e15i195E-06 0.0 0.19182E-02
SE 71 0.52204£-12 C. 10037510 C.0 C.21881E 06 0.79358E-04 0.25982E~-C4 0434398E-01
BR 81 C.a2TB4E~-CH G.82260E-07 G.74144E-06 Ce0 G.0 0,0 0.35425€E~02
KR #1M Oe 24475FE-27 C.2T058E-21 0.0 Ce8T94¢E-03 0,91882£-13 0.0 0e2258BE=-11
KR 81 0+ 33600E-19 DeC4TTHE-18 U. 0 C.0 0.0 0.0 C.&483261E-08
St 82 0.93834F-12 0.18041E-10 0. 195982€-1¢ £.0 0.0 0.0 0.5T128E~01
BR 32M Del€348E-13 0.31432E=-12 0.0 0.20B&4E 05 0.13750E-C6 Q.0 0.13536E-07
B” 82 D.54834€~11 0.10543E-09 0.0 G, 20133E 05 {.80388E=-05 Q. 163869E-~05 0.45402E-0D5
KR B2 0.146936E-14 Qe287TtRE-LD 0.53701E-D9 C.0 0.0 0.0 0.106685E-03
SE P3N De&5840E-12 0.8B1365-11 C.0 Q.3059CE 07 0.15116E-02 0.0 0.156%6E-01
SE 83 0.49629€=-12 0.95423¢€-11 0.0 0.1%455E 06 0.182R29E-03 0.13716E-03 0.33787TE-D1
BR 23 Ge 1251 6F=09 C. 24065E-03 C.0 C.67388E 07 0e37362E-03 Oe 0. 10343E-03
KR R3M O.4T453F-12 0.91230E=11 Ge%S324E-08 C.323104F 05 0.83250E-C6 Gl De335467E-0C1
KR R3 0e42220€-12 0.B1Y77E=-11 D.425800E-04% C.0 0.0 G0 0.30586E~-01
SE B4 0. 20783€-11 0439959E£-10 G.0 L.49030F 07 Qe.23272E-C2 0.0 Qe 10724E 00
8R B4m 0.52426E~12 0.10080£~10 0.0 0.68024E Gb 0.25669£-03 0.28178E-03 0.43409E~06
arR A4 0, 51B05F-10 0.99608%E-09 0.0 Ce12683E 08 CeB214TE-C2 0.2560T4E-02 Da42894E-04
KR B4 0a11538E-11 0.2218B4E-10 0,550C2F-08 0«0 D0 0.0 0.82563E-01
SE 85 0.15519E-11 0.29838E-10 0.C C.18582F 08 0,148B56E~-01 0.0 0, 37569E~01
BR 8”5 0+ 1249%£-10 C.26023E-09 0.0 Ce32424¢ 0B 0.48T7TT5E-02 0.0 0. 103486E-04
KR 35M 0.26623E-11 0.51188F=-10 Ca22T46F-07 J.78512F 05 0.148616E-04 0425140E~QS 0.18983€ ©Q
STEADY STATE

NUCLIDE

KR
RB
B8R
KR
R3
RR
SR
BR
KR
RB
SR
SR
ar
KR
rE
SR
BR
KR
RB
SR

¥
KR
Ra
5R

Y

Y
IR
¥R
Ry
Sk

¥

Y
IR
KR
RE
SR

v
IR
¥R
rRY
SR

Y
IR
NE
NB
KR
PR
2R

¥
ir
RB
5K

¥
R
NE

85
g5
858
86
REM
RG
85
at
87
B?
RTM
87
88
ag
23
88
89
89
29
B9
29
30
20
a0
I0M
90
20
91
91
91
1M
a1
31
92
Qg
92
92
22
93
g2
93
a3
g1
33M
23
94
34
94
94
94
95
9%
95
95
N

CONCENTRATION

GM-ATOM/CC

0,17772E-12
0. TASELE-0T
0.69995E=11
044923511
0. 56550E~15
0. 19982F-10
0.22082£-C8
0. 3B8T90E-11
0.5984T7E=11
0.72279E=06
C.86229E-15
0.15065€~1C
Dy 34113611
0.70371E-11
D, 22796E~11
0, L0044 E=DE
0. 10124E-11
D.62202E-11
G.78312E-10
0y 413B4E-04
0.27576E-08
D.37452E~11
N.32872E-1D
C.32472E-04
. 21408E-15
G.TBRE4E=08
3.4 0895E-06
3,10472E-11
0.15040F=70
0. T8654FE-01%
0.35$58F=09
0. L2543 E~06
0,1 3900F-0F
De2296GE-12
G, 12486E~11
0.23064E~08
54 34008F=08
0. 32074E=05
0, 39760E-12
e 14044F~11
0. LZBLTE-QS
0, 96R56E-08
Ja 33303E~05
0,25393E~17
0. 19690E=24
0. 547T39E=14
D, 20632F-12
0.1 7853E=-10
02785 1E-C9
0.32574E-05
0. 15209F=12
3. 8TDTIE-11
Os1E130E=-0Y
5,942978-06
0. 11627E=12

Ga34170E-1)
D.14345F-0%
G.L345BE=C9
C.BR63TIE-1D
Q. 10872E-13%
0.383481E~0D9
B.18%G4%-09
C.11318FE=09
Cal4289004
G.156%99E~-113
G.28965E~09
Gy 55902-190
C.13530E-09
J3.45752E-10
0. 745963E~05
Ce19802E=10
GC.15057E-08
CsT956QE~05
053021 E-05
C. 7T2010E=10
G, 632046£~09
BL62RYIVE-C3
B.41328E~14
7.15163E-06
G.TR8822F=0%
0, 20135€-10
C.28318E-09
0.15125E~05
C. T6827E-03
0.81798E=(5
0.267T25F-04
Get4162E-11
0. 24007F~10
Da.44345E-07
D.EH38BE=0GT
0.618T70E=04
G.TE467E~12
0,28734E-10
C, 24643E-08
0.18623E=04%
C.6403LE=0%
D.468B2E=16
0.37853F~23
D.1488525%€-12
J+59010E~11
0434308509
0.5354%E-08
0.42630E=04
0,2941586E~11
0.16742E-09
Ca31012E-08
0.18131E-C4
0.22375E=11

VALUES FCOR THE FISSTCN PREEBUCTS
MOLE FRACTION

PCISCNING

ABS/ABS(FUEL)

e 73%41E~08
0.B82616E-06
0.0
Ga123310E-08
0.0

O« 0
G.1R808E-07
C'.O

0. 52112806
Gal2228E=05
G. 0
De64l64E-10
0.0

Te G
G.2533&8F~10
(. 25582E~07
Ge G

Ce

Cu G

C. 23935E=-05
e %2510E-05
0.0

0. C

C. 48213E-03
0.0
Gu21329E-06
C.47421E-06
Cu 2

0.0
O
G, 0

0. 5257TEE-Q5
Ce 51484E-04
Ny

Q

2595804

. ®
S D QOO0

>

PO OQO OO0

3. 23062E-23
0.0
OIO
0.0
Ca 2
Je 4C99&E-05
0. G
Je &
0.0
0.3
0.0

ACTIVITY
CURIES

0.24445E 00
4.0

0. 6054GE C8
C.0

C.42332E 04
C.578B0SE 0%
GIO

C.83905€ 08
C.80302E G4
C.216556~03
0.3G582E 02
G.C

C.9%556E 08
C.32611E G6
C.104C7E 7
C. 0

C+1052CE 09
G.1537¢E 08
C.29589E Q8
Cu.&4202E8E G8
CaC

G.53015F 08
G.B8247E {8
C.17211E 08
C.B89971F Ot
L. 15989 OB
C.0

C.4EBS18E OB
G 97577E 08
0.1055£4E 09
C.6221€E OB
C.39117E 08
G. 0

0.35764E 08
C.11GC3E 09
Cull0432E (9
0.125C1E 29
Ce0

0.928¢5E 07
0. 1246£E 09
C.12472E 0%
0.12321¢ 09
C+32BELSE Q2
,265408~0%
G.0

C.1B2H4E 07
C.%45440FE 08
C.I06B%E N9
0.10681E 9
C.G

C.,2E587% 08
0. 84741 08
0.11520F 09
0.78435E 08
Q0. 167TTEE 03

POWER DENSITY

KH/LITER

0.30721E-10
0.0

0.2%019E-01
O'O

0433962E-C6
D.65759E-06
0.0

0.67917E-01
0,664 1BE=03
0.341B9E~14
0.22003E-C8
040

0.57788E-01
0.30193E~03
0.40109E-03
0.0

G.49325E-01
0.15541E-01
0.16953€=-C1
0.3741BE~C2
0.0

0.39315E-01
0.59421E-0C1
0.54247E~C3
0.88295E~09
0.22105E-02
0.0

0.13810E-01
0.41233€-01
0.26313E-01
0.49113E-02
04359 78E-C2
0.0

0.12489E-01
0.55024E-01
0.23099E~01
0.31879€-01
0.0

5.51713E-02
0.49113E-¢1
0.57537E-01
0.24360E-01
0.94168E-10
0.365016-16
Cu0

0.79165€-03
0.29536E-C1
8.36444E-01
0.41621E~01
0.0

0. 14007E-01
0.30351E-C1
0.33339E-01
0.99223E-02
0.18073E-07

GAMMA HEAT
KH/LITER

4577E=-12

2

0

o

o

3

T

o
45504E-01
29224E~03
o
2
¢
0
2
8
0
0

5060E-03
422BE-04

T3IBLBE-02
0.1356TE-0L
0.0
0.0
0.26344E-C1
0.61000E-01
6.0
0.88295E-09
0.9
0.0
0.0
0.12578E-01
C.16314E~01
CetS113E-02
0.215687E~04
0.0
0.0
8.0
.19403E-01
D.66946E~02
0.0
0.0
Q.0
0.35673E-01
0.48720E-C2

*

1639E-C1
4151E-01

SOOI OONO0

L I T S S R I )

DT DO OR

0.70012E-02
0.,81462E-G2
0.18073E-C7

PROCESS RATES

MOLES/DAY

0.12924E-01
0.,10152E-02
3.57955E-05
0.22137€ 00
0.7B0O3QE~11
3.27533E-06
0.30473E~-04
0. 81798E-05
J.41421€ 0OG
Ce10112E~01
G.11913E~10
0,207SCE=-06
0,28246E~05
Ja49965E 0C
0.32838E=-07
Gu85261E=-02
3. B298B8E-06
0. 32363E GO
5. 1080TE~QS
0.57T110E~-02
0.22833& GO
3.80933E-01
O.45384E-08
0. 45087E 0O
J.1TTSBE~OS
O &5299E-02
0.84861E=-01
0.868&2E-02
0. 207546E-0¢
0.10856E-03
0.32085E-03
0.3522%E 00
G.287T73E 00
Ca&22G4E-03
0.17231E-07
G.31828E-04
U, 2B159E-G2
U.663%4E GC
0. T2703E-04
3,20623€-07
C.1T768T7E~0S
G.B0197E~-Q2
Gy 58937TE 00
Go LT444E=-04
0,450T6E~113
G, 1060TE-05
0.42386E-(8
0.26823E-06
3+ 230&0E-03
J.6742BE 0C
0.21113E~08
0.12C17E-Q6
0, 13355E~03
0,1951%E 0C
0.83233E=02

¢l
STEANY STATE VALUFES FOR THE FISSICN PRCDUCTS

NUCLIDE CONCENTRATICN MOLE FRACTION POISCNING ACTIVITY POWER OENSTITY GAMMA HEAT PRCCESS RATES
GM—-ATGM/CT ABS/ABSTFUEL) CURIES KW/LITER KW/LITER MOLES/ZDAY
NB 95 0.57023E-11 0.1C965E~-09 0.390361F-09 C.H580CS5E 03 0«32673E-C6 0,3087&E~-C5 0. 407587 0C
M es D.B88733F=13 0.16484F-11 0.33151E-10 Je9 0.0 0.0 Cueb1435E~-02
Y 96 Js 216456F=10 0.60846E-093 0.0 0.10712% 09 0.77037E-01 0.52926E-01 Ce262C2E~-04
F A Je 27464E-05 0.52006E-04 0,19G20E-05 0.0 0.0 0.0 C.56851Ff 0C
NB 96 0.8FG02F~-14 D.1653%4F-12 0.0 C.48513E 02 0.58013E-07 Ca52211E-07 0.61462E-03
MO 96 0.36045F-17 De69304F-16 0.26159€-15 C.0 0.0 0.0 O.82465E~06
Y =7 Ne12890E=11 0.24784E-1G 0.0 0., 1003¢E 09 D.32350E-CL 0.0 0.10&673E~05
IR a7 0.13082%=-07 0,25152€-0¢ 0. C 0.39852E 0% 0.17231E~-C1 0.99071£~-C3 0.27080E-02
MR 9TM N.45080E-11 0,86676E-10 0.0 0.3509¢ckE 08 0.73945E-02 0.73969E-(2 0.142038 00
NB 97 0,28771c-11 0.55318F~10 Q.0 J«31109E 0% ND.26147TE-C2 0.15165E-02 e 37950 00
MO 27 0,225235-12 D.43313€=-21 0.13587€-1C 3.0 0.0 0.0 0e22816E~01
IR 98 0s3122319E~-10 0.23£93E-09 0.0 C.35126¢ 08 0.74955E-C2 0.0 Te2%5293E-05
NB 98Mm NeS4T6LE-T1 0.105295-09 0.0 0.21316E 03 0.,14611E-C1 0.0 C.23955E Q0
NB 98 De26605E~12 0.51154E=-11 0. C.4l€13E 05 0.51811FE-04 0.27460E-04 G« 18570801
40 98 3.18845E-11 D.304K6F-10 Qe 2694 7E-1C C.0 0.0 0.0 0.266C2E 00
NB 99 0.565%9E-11 0.,10682E-09 2.0 C.18022E 08 0.72403£-02 C.0 0425987 OC
2 99 0. 12369FE-11 0.257C5F-10 0.0 C.25892F Q4% 0.17892E=-0% C.51886E~05 0.23316E 00
TC 99M 0.16686E-15 0.22082F-14 0.0 0.3408B5F 01 0.110866E-C8B 0.0 D.T75793E~-04
TC 99 D.282&41E-16 0.4853nE~15 J.11252E-12 «1T624E-08 D.43752E-18 0.0 Js11655E~04
Ry 99 0.13074£-27 D.251415-256 0.153]18F-25 0.0 0.9 0.0 O 14218E-15
NB100 0.53716E~71 0.1032BE-09 0. T.13G39E 08 0.15199£~01 0.273585-C2 0.26993E o¢
M3100 0.10342E-11 G.15884E-10 0.1837¢E-10C Ca0 Ja.0 0.0 0.18832E O¢C
TC100 0.578B23E-24 0.,1111RE=-27 Ded Ca15889E-04 O.82373E~13 C.0 Ge3329%E-1¢
RUIODOQ 0.117R82-23 0.22665E-22 0a14862E-21 00 0.0 C.0 0.16777¢-11
NBIOY Ne273445-31 0.5257T4E~-190 0.0 f.21288: 08 0e69082E-C2 2.0 O.86146E-91
Mglnt Cus15192E-11 0.29211E-10 0.0 0.81012F 06 0.121462E-02 0.97296E-03 C. 200698 0C
TCiol 0.57722E-73 N.11098E=-11 0.0 C.22099E 05 D.42644E-04 Ua17684E=-08 0.16759E=-01}
RULOY 0.22815F-14 C.457P7GE~-113 0. 50876E=-12 Ca0 0.0 0.0 0., 19675€E-02
MOIn2 0.21607E-11 0.6077LFE-10 0.0 0.22370E 07 0.46864E-03 0.0 0.2027CE 0G
TClo02M 0.73543E-12 Os141402-11 0.0 «12723E 08 0.35498E-C3 D.25551E~02 0.13232€-01
TCia2 0.10462E-172 3.20116E~-12 0.9 0.37746E 06 0.87463F-03 0.0 Ge TE65TE-03
PUl02 0,81960E-12 0.15758E-1% 0,32301€E~11 C.0 0.0 c.0 0.21250E-01
MO103 0. 17140FE-11 J.32954F-10 Ja0 C.12914EF 08 O,44105£-02 Q.0 0.54990E-C1
TC103 0.565856F=12 0WYQRROE-10 J.0 C.5286€E€ 07 0.267C9E-02 0.0 0.42816E-01
RUTO? 0.29222€-12 0.75612e-11 0.0 C«535%0E 02 0+351€6E-07 0.30946€~-07 0.93348E~C]
RH1Q3M De39332E-17 NeTT623E-14 0.0 0.53720F 00 0.5868%E=-10 0.C Oal2310LE-0S
RHE1012 0,39856E~19 0,75631E-18 0.160826-15 C.0 0.0 0.0 0e54382E-07
MO1n4 Ne3G4A/KF-12 C.19128E-10 0.0 C.59577F 07 0.32709E-02 (.31400€-02 V. 3599LE-C1
TC10e Ne&2827F=-12 0.R”2345E-11 Dal) C.18522E 06 0.64946E-03 Ce50008E-03 0.61478E-CL
rUto4 0u13743F-13 0.26%423°-12 0.214168-12 0.0 Q.0 0.0 De53232E-02
RHLO4M J.162CRF=26 0.21162E-25 0.0 L.28612E-08 0.44266E-17 0.0 De42592E-14
RH104 N 1300566-25 0.25007E-24 Ga G 0.16129£-06 0.,:2721E-14 J.15265E=16 0.25971E-13
PO 04 0. 10431E-25 0.20055E-24 Celi221E-23 Ce0 0.9 J.0 Q46566813
¥OiI05 0.40019E-32 C.76946E-11 Ce ) Ce4ueT35E 07 0.25881E~C2 D0 0.,98512€-92
TC10%5 0.65027E-13 0.12503E-11 0.9 C.3797CE 07 0.15517E-02 Cs 0 0.22249£-02
RUT OGS 0.23110F=12 0.540%7F=-11 0. 6E5032E-12 C.82151F 04 0, 73772:-C5 Jets7214E-05 D.411319E-01
RHIO5M Qe 34432F=-15 Debb2T2E-14 0.0 0.38742EF 04 0.54948E-06 0.0 0. 81939E-04
RH105 0. 26509E-45 D.50068E-14 0.1%14CE~09 C.95813E 00 D.601125-09 0.21039E-09 Ga.15767E=-013
P31 05 0. TIORKE-19 0.13668E-17 0.20751E-1¢& G.0 G0 0.0 C.98106E~07
TCL06 0.19596F~12 0,3767TTE-11 Us0 0.24740E 07 0.15230E=-02 C.30460E-03 U.45801E-02
RULOS 0.1R355E-12 0.3529%LE~-11 0.1129€E~11 C.27040F 0% 0.18523E-10 0.0 G.22859E-C1
RH10AM 0.72458F-20 0.1%026E-12 0.0 Cat3691E-03 0.86006E-11 CeTH26BE-11 Ja 10CL4E-0T
aHIns N.100€65F-18 0.19252¢€-17 0.0 Ce15673E 01 0.29808E8-C8 0.35769E-09 D.22384E-07
PLIOG 0.,116%1E5-18 0.223263F~17 0,19556E-17 0,0 0.0 0.G D.67T8B50E-07
RUIOT 0.21991€E-32 0.42262E~11 0.3 Ce&40T63E Jb 0.2339BE~-C3 042135353804 D.12075E-01
STEAQY STATE VALUES FOR THE FISSICK PRCDUCTS

NUCLIDE

RH107
fOIOTM
pPDIOT
rRUIO8
RH108
PI108
RH1QO
pPRIOSM
pR10S
AG1D9M
AGLOS
41D
pCiic
AGLIOM
AGLID
colsg
PDI1ILIM
P11
AGTTIM
AG111
CD1llm
cDlly
epLIY 2
AGll2
cnlvz
PL11R
AGLLIZM
AG113
cCo1lam
(e B
N1 3
PD1 4
AGI14
(D114
TNYIT4M
IN11&
ANt S
PC1L5
AGLYSHM
AG1YIS
CO115M
£o1ls
INT1SM
IN115
SN11s
AGlla
CoLls
IN11GM
IN11§
5N114
AG1L7
COLLITNM
o117
IR1IITM
INIYLY

CONCENTRATION

CM~-ATOM/CC

0e29469E-13
0.560085E~-16
0.71361E-15
0u.101248-12
0. 4276£2E~14
0.87178E-12
G.32353FE-13
0.12350€-22
De37349E-13
J.14302E-16
0.12392F-16
G.56217E~-14
0.38957E-13
0.31473F-24
0s32919FE-23
3+ 33510E-16
0.34809E-15
0.33STBE-13
0.60765E~15
0.28457E=-15
Ge¥0018E-23
0.57152E-12
0.22859E=13
G.10448F-16
0.BT3DSE-13
5.19170E-13
Ju53390E=15
0.710508-14
0. 12960E~15
¢.295388-10
0233026F=17
D.21373E-13
G.64B5TE-15
0,44920F=08
0.87315E~19
0. 21367E-23
0.34868E-18
0.146380E-13
0.12925F~14
G.88231E-14
3,93703€-11
0.3£634F~10
Y. AQT?T2E-11
0,14265F8-08
0. 11378E-09
0.20056E-13
(s 39353£-09
Coel6245%=-12
0. 18TT§E~1F
Q. T£355E=09
0.15403F-13
0,1B1528~-14
3.407415-11
0.22750E-11
0.58497€-12

MOLE FRACTION

0.565660F=12
0,11553¢F-14
(. 13721F-13
Vs12465E=-11
0.8221%F=13
0. 167T62E-12
0.562205E-12
0,2374568~21
G.7181lE~-12
0.27498E~15
0.23825€~15%
G.108098-12
Ga74021E-12
0.,60512E-23
Os63203€-22
Cab4&20E-15
G.6EF2FE-14
D.65331E~12
0.,116832F=-13
C.56TIEE~1S
O,192¢1e-22
Gal201vE-11
Su%3951E-12
C,20038E~15
0.167858-11
0.25857E-12
0.10268E-13
0., 12561F-12
0,2664%E=~14
0.5&TG3E-09
G.635C08~16
G.411028=12
Q.12672FE=23
0.,883275-07
0,1678BB8E-17
0.41082€-22
C.67040E-17
Q.314%4E=12
G.24851E~13
0,15974E-12
0.18016E-09
Q. T0436E-09
0.538155E8~-10
C.27428¢€-07
G.21872€-C8
0.38634F-12
8.,75T41 E-07
0.31427F-11
C.356105E~14%
0.14681£=-07
0.298158-12
D.24302E~13
0.78334E£-10
0.562968E-10

POISONING

ABS/ABS(FUEL}

4163€-12

<

2 @ & ¢ & 0 ¢ & W & A

22946-11

3045E-13

WO OO MO IO

SO OG D

0o 595 0E-12
O, 0

.
g% ]
i
o
W
>
m
i
P
i

54608E-11
£3B1E-11
3344E-05
36226~14
4670E-05

T125E-1E

HOOOOOOWOSONODDRGEODIOONMDOONDSDOO0D

41776-04

OO OGO OOODAC OO0 DEO 0D O

¢ # 4 & B B e ® ¥ ¥ % B O F 4 B ¢ B @ e & & @ @ F F H B B

‘=

0.C
Os 3BFBHE-CT
Ga O
Oa O
0. 24£32E=-07
0.0
.0
0.0
D, 34E7CE-CS
0.52284E~-10

ACTIVITY
CURLES

C.10428F 05
C.12758E 04
0.0

C.1T514E 06
Q.117S0E Q6
0.0

0.50377E Q6
C.2045TE-04
C.35978E O3
C.167C2€ 02
0.0

0.52521F 06
.0

0,67258F-11
0.563022E-04
.0

C.B2123E€ 01
C.12024E QS
0,38358% 04
£.20515¢€ 00
C.16047E-06
G.0

C.14124F 03
C.43364E 0O
.0

0.106&CE 06
0a34837E 04
0.17395E 03
C.l4655E-03
G.0

Ce O

£.6G53458 D5
C.50602€ 05
0.0

0,244 &E-05
Uue12BE63E-00
G‘O

C,17C04E G5
0.3C189E 05
0s34364E 04
G 117B2E 0%
t.83B50E 05
L.8B72CE 05
.0

0:0

C,625T73E 0B
0.0

C.23565%E 05
0.626%7E 04
C.0

0.1C901F 06
£.632778 D2
0.22027E 06
C.22018E D6
C.1035CE 06

POWER DENSITY

KW/LITER

0. 795CCE=-GS
0.336413E-C6
0.C

0.34137E~-C4
0.12639E-03
0.0

0.181368E=03
U.97365E-14
0.97L16E-07
C.14297E-C7
0.0

0.1%220E-03
0.0

0294517E-19
0.23005-12
0.0

0.14006E-C8
0.44991E=05
0,20745E-C6
0.15273E~CS
0.9103%E-17
0,0

0e56211GE-G8
0.11245E~-C8
0.0

0.,41105E-Ca
0.16038E~05
0.19254E~(56
0.46B8156~14%
C.0

G.0

D.30281E-Ca
0:53052E~-L4
G0

0.324£4E-15
0.15769E-14
0.0

0.88502E-04
Oel105T1E~Ca
0.4TO83E-CS
0.11596E~C6
0.T1538E-05
D.%2585E~(C5
J.0

OO0

0
» B9505E-C4
+0

0.95541E=05%
0.12567TE-C5
0.0

0.39450E-C%
0216475€-C7
0,56172E~04
0.16813E-04
0.16472E-04

GAMMA HEAT
KHALITER

0.31005E-C5
0.33413E-0b
0.0
0.0
0.20222E-04

5120E=-04

7568E-05

0T16E=-19
2114E-14%

6809E-17

a & & @ 8 3 & b » o 8 @ ¥ v @&

QOO JOr-OOOCPr~000Lr00VToRo0 O PRQOO0 00

T454 =07

L4748E~06
6B19E-17

3263E=-04%

SidE=16
T69E-17

COoODOCOLOOHOLCOVOODOoOOOODOOOOOCOULODLODO
o=y

¥ & 4 v % 6w w s ¥ & & b g oy

268541E~05
0.17046E-07
0.24609E=-05
L.404938E-05
0.0

5605€E~05
1310E-07

DO OOo
QOre®mOOQ

2
a
2
*

»

®
-

0.93910E~-0B
0e40444E-04
C.aTQTTE-D5
0s82492E~05

PROCESS RATES

MCLES/DAY

04544 T7E-02
0+ 15055E-04
Q. 354G£E~03
Co 564 TSE-D2
04 346526~03
0.21778E-02
0.65353E-03
0. 86950E-11
0.43261E~02
0226926505
0.60190E-05
0424 T5CE~Ch
0e31651E-02
0.35884E-12
0s21213E-11
0.69365E~11
0. 24807E-04
0.22981E-02
0. B6BO0E~-C4
0, 10978E=-03
3.20736E-18
0.13900E~C7
0.163368-02
0+23793E~(5
0.18072E-07
0., 71888E-03
0.50242E-04
0a109126-02
J.28690E~10
0,61144E~05
04868364E-12
5.99%92E-03
0.35437E-04
£.930056-02
0. 1BO0T4E~-13
0.44229E-18
0uT2176E-13
0.43491E-03
0.62090E=-04
0.10927€-02
0.19356E-05
0uT75832E-05
G.B36IBE-06
0.29529E~03
0235475~ 04
0,35306E=03
0+ B1544E-03
0+ 32834E-07
0. 38B71E~10
0.15805E-03
0.51128£=-03
0.375375E=-05
0.84335E-06
0.67732E-06
0.12109€-C6

Gl
STEADY STATE VALUES FGR THE FISSICN PRCOUCTS

NULCLIZE

SKh117#m
SNIL1TY
CD11R
TN11BM™
TN1LE
SN ig
CD11gm
cDlle
TNILGM
TM119
SNI1OM
SNile
cpi20
INT20M
IN120
SN120
cD12%
INIZ2'M
iN121
SN121M
SN121
sSg12?
iNi22
SN122
SB1Z2M
SRiI22
TEYI22
TNYL23M
INi23
SN323M
IN123
$8123
TE123M
TE123
iM124
3MN124
Salz2am
Salz2s
TE124
SN125w
SN125
58125
TELZ2GM
TE12%
SN126
SPR12¢em
sB12¢
TE126
SNi27M
SN127
$B127
TE127H
TE'27
1127
SNl2@

CONCENTRATION

GM-ATOM/CC

0.12193E-12
0.5627T2E=04
0.15927F-11
De 254441518
0. 33888F=-14
0., 8137TE=-0R
0551654813
D, 2042T7E-12
0.7352Ye-12
0.62R02F -1 4
De131445-110
0.B1230E=-CF
0.422A3E=-117
0. 1153¢&E-14
0. 16%583F-173
C.8&527F-08
0.15275FE-12
0.12529%~12
0. 33080F-24
0.10G4%1E=-12
0. 70139F-10
C.B4611E-C8
0,9427T4F=-14
0.,1&119:-07
Ne32241E-15%
N,2159R84%=-11
0. 4699525-18
N.62512€-13
C.1C179F-14
De LOBYZ2C-08
N.41T7T38BE-~-11
C.?1816E-07
NeB29863FE-24
0.166%18F=23
0.107T7T3E-12
0,32255F-07
0.52629F=-1¢
D0.82692F-10
De5856THE-1 5
0.71457F-12
O 153T7YE-QR
De3269T7TE-07
N.B51870E-14
0.811i3Nc~14
0.454891E=-07
Dy &3503E-11
0. 3T4L3E=-]R
G.12148F=12
D.8%610E=-1¢6
0.17252E-09
D.T4&325E~0R
Os 16925E=12
Qs SQ99S0E-12
D.168426-09
O« L 4963E-09

MOLE FRACTINN

0.234037-11
D.10820E-06
0.38313E-10
.46994E-17
D.£5186E-13
D.15646FE-05
C.105604F~11
0.39274F-11
0.141325-19
C.R266£9F-173
C.252725=-09
G.15618E-06
C.83191E-12
0.2218YE-13
0.218858-12
0.16637E-36
0,2936RE-11
C.26012E-11
0.63503E-23
0.21036E-12
0.134R6E-08
0.15268E-06
0.19126E-12
0.27146E-06
0.,73827¢c-14
Q.65187E-10
CeIENL45T~14
C.1203A£-11
Ja368765-113
0.209425-07
0.8025CE-10
D.L13685-06
O.,1589518=~22
0.31951E-22
0.20712F~12
0.6201~E=-06
0.10119E-14
0.15899F-08
D.107T0SE-13
0,137395-10
0.29170E-07
0.62868E-06
0.99730E-113
0.1559%¢€-12
0.87851 E-06
U.83655E~10
De71992E-07
0.23357E-11
0.18660E~14
0.32170E-08
Je14290E-06&
0.32544F-11
0,11527€e~10
0.22382E-08
0,2RTTOE~08

POISCNING

ARS/ABSEFUELY

0.C
0. 26885E-06
C.212177E=1C
C.0
0.0
Q. B6E4E6E=-0C
0.0
0.0
De 782Q2E-11
O.45¢7TCE=-112
0.0
0.22652E-0¢
D.0
Os15919E-15
0,22883E-14
0.2510%E~Q7
Oa 0
0.0
C. 0
0. C
0.0
0, 336836-0%
0.0
0., 27059¢F-07
0.0
C.0
Oe 15956E-12
0.7
0.0
Ne 0
Ca 0
C.9662%E-05
Ce0
0.70774€E-2C
0.0
C. 4BCBLE-07
0.0
Js45643E-05
Os41496E=-12
0.0
Oe?
0.586T72F~-08&
0.0
0.582578E-12
O. 15838E-C&
Gae 0
e
0. 36330E-11
Ga.0
U.0
J. 0
GeO
U0
0. 7667TE-Q7
PR

ACTIvVITY
CURIES

Ce4TCBTE D2
0.0

0.31£€6CF 06
Coel4324€E Q0
Q.3166CF 0%
Q.0

C.1%5903E 06
C.15902% (6
C.31803F 06
0.1E9C1F 0Ff
C.2842&F% 03
C.0

0.33621L 06
Cs1£840E 06
0.16840E D&
Cetd

C.239T€E D5
0.33975F 0%
C.51509E-05
0.21310E-D2
C.237CBE 056
Cs0

0.55048E 06
£.0

C.7C8RSE 03
C.66483F D4
Qe

D.81245E 06
C.BSS5SLE 085
0.47112% 05
C.B1234E 06
0.0

C.38328£-10
c.0

Cl.1258CE 07
UsQ

C.26435E 03
J.74514EF 04
U.C

Je«5T351F 06
D.87260F Gb
0.1792¢&E 06
C.4B8352E 00
.0

0.5763¢€E 01
C.17828EF 07
0.18165%F 07
0.0

C.l8862E (3
C.10660F 08
Cel037CE 08
G.8395BE 0Ot
0.82755¢€ 04
0.0

C.1G744Et 08

POWER QENSITY

Kn/LITER

0.21384E-(8
0.0

0.12065E~-C4
0.20322E-09
D 870ATE-Q4
0.0

Oe24175E-C4
04341 74E-C%
0.51020E=C4
N.33488E-C5
O.36245E-C8
g.0

0.60316E-04
0.51522E-04
0.87006E~-C4
0.7

0.26377F-C4
0., T4dT12E-C4
CelS202E-14
C.54028E-13
0.54086E-CE

o

«32492E~03
-0

+16452E-07
C.10651E-C5
0.0

0.37247€=-03
0.41073E-C4
0.,38R09E-0%
CG.T93TIE-C4
Gae0

C.10951E~19
Qa0

0. 79844E~-C3
0.0

0.15664E~C7
D.24339E-55
0.0

0.97528E-04
0.12764E-03
0.,14536E-04
0.32141E~10
0.0

0.87208E-10
0.25030F-C4
U.42924E-03
OIO

Ce2B8910E-CT
Ce27642E~-02
C.13772E~C2
Ce35T95E~G9
0.10417E-CS
0.0

J.23933E-02

GAMMA HEAT
KW/ LITER

6450E-09
3603F-05

133E-06
T53E-0%

w o

2450£-05
B354E-04

22B3E-C4

8407E-15

68946E-03

5801E-06

6445E-03
9lb62E-04

7846£-03

164E-~07
IBBE-05

COoO00OCOGOOUOUO0O00OCO0000O0COOIDON0COOOONDOOD
O

4 & & 5 8 & 9 & 4 % & % 8 B * & P B E 8 & W A K B A e BRSO A Ao

SCrHOWOQOQLOMMNOPFTOHOOQTOYOWMPOOTmANOOGTHOOO

Ge29063E-04
CallblSE-CH
0.79949E-C5
0.0
G0
0.0
0.95114E-05
0.24896E-03
00
Dei2C62E~07
0e14650E-32
0.69825£-03
0.0
0.15526E-07
0.0
0.1555%£-02

PROCESS RAVES

MOLES/OAY

0.25239E-07
0.11649€6-02
0.41248E-06
0.50594£-13
04 70147E-D6
0.16845€-02
0.11417€-07
0.42283E-07
0.152216-06
0.88787E-09
e 2T208E-05
0a16815E=02
0.89554E-08
0.23880€-09
0.34327E-08
0.17911E-02
031618607
0.28004E-07
0. 654 75E=19
D.22648E-08
0.1451GE-04
0.17515E-02
0.195156-08
0429226£-02
0e79160E~10
0. 764 8TE-0¢
C.35726E-04
0.129615-07
0.3$7C0E-09
0.22547E-03
0.863%7E-06
De44537E-02
0.189G2E-12
0.380642E~12
0.22299€-08
0.6ETETE-02
0.10894E-10
0.17117E-04
0429830504
Je147S1E-06
0. 31404E-02
0.6 T6E84E=02
0.37106E-03

« 58040E-03
0.94581E~02
C.90064E-0¢
0.77507E=D3
J.86905E-02
0.17721E-10
0.357131E-04
0.15385€-02
0.12109E~01
0.42792€-01
0.1%945E-03
0. 30974E-04

9L
STEADY STATE VALUES FOR THE
CONCENTRATICHN

NUCLIDE

ssiz2aM
spi22
TELZE
1128
Xgize
SN129M
sRa129
TEIZ29M
TEl12%
1:2%
XEL29M
XEL28
SN13D
581i30M
58130
TE130
11304
11390
XE12D0
SN131
58131
TELALM
TE12L
1121
XE121M
XE131
SN122
58132
TE132
1132
XEL122
$B132
TE133M
TELI33
1133
XE133M
XE133
£5133
SBi%4
TE134
1134
XEL34
£3134#
L5134
BAl134
TEL35
11358
XEI25M
XET2S
C51365M
Cs135
BAI3SH
SA12%
136
XE136

GM-ATOM/CLC

0,27059€=-10
0. 17776Z-09
G.16110F-11
0.57228E~14%
0.1238GF=-15
0,27791E-09
0,11935-03
D.96192£-12
0.16959€~-11
0.38539E~083
D.23992E~-21
O, 3&695E=15
0.160566E~10
G.21626E~10
0. 10164809
0.356RTE~11
Cs259%4F~14
Ds13662E-11
0, 10607E~14
N, 23885E~-10
C.17538BE=CS
3.607T60E-12
0s33655E~11
Gy 3G26TE-O8
0,1 5433E~-14
0.329506-12
0. 232347E-10
0.22285E-10
0.6128TE=11
G &TLI68E-10
D.19T7T81€E-12
0e346656F~10
D.612%95~11
5.12847E~11
(e 21001E-GA
G.23200E-13
C.91809E-42
D.56453E=-C9
0.31527E-12
C.7ta58E-11
Dal5259E8~-11
De 30354E~1%
Q.1Z148F-09
0. 33501E-09
0.32586E-11
0. 43184E-C8
0. 18953E=-11
Da521558-11
0, 13737E-14%
0. T4SE1E-CT
0. 26851E=15
2. 29034E6~11
0, 62234611
G6.98524E-11

Na52027E-D9
De24] 798=-03
0.,30975E-10
CaliO03E~-12
0.23820F-14
0.53435€£-08
0.22947E-07F
0,184%5E-10
C.3260TE~L T
Ca74137E-07
0uas6129E-20
CalB207E-12
0.30890€E=Nn9
0.41581E-09
0.19500€~03
D:6R616E-10
0.E1902E8~13
0.,2682576-10
0,20394£-13
D.45866E-09
0.33721€-08
Qe11682E-10
0.64727E=-10
D.TELSRE-DT
0254673112
0.15949£~-10
0.4%883E-09
0.4284BE-0%
0. 11TB4E=DI
Q. 806°0E-09
0,330328-11
0.66852E-09
0.117T73E~Q9
Qe 24701 E=LO
0.,40651£-07
D.845607E-12
0.176528-190
O.10470E-07
Q.60612E-11%
0.13815E~09
J.220322E-03
0, 2933CE-1 0D
B.58382E-113
0.23386E-08
Oub4412E-33
D6 2653E~10
0. 83030E8=07
0.20578E~10
G.1C025E-~-09%
Da26411E-113
0.14340E-05
0.51049%=-14
0.55823F~-10
0. 12158E-09
0. 18942E~09

FISSICN PRCOUCTS
MCLE FRACTION

POISCNING

ABS/ABS (FUEL)

0.0
3.0
0 35567E-1C
0«0
Oa 3B8121E-11
Qald
GO
0e0
D O
Da1ESHEE-D5
0. 91792E~-17
0. 203895E~-05
0.0
0.0
0,0
D.115216-1C
OIC
O, 2E1R3E=05
0. 224638E-1C
0.0
Oe )
Ce O
0.0
0, 10151E=0¢
0. 5749%E-05
0.24161E-05%
0.0
Ce O
Ga 0
0.3
Os 14867E-08
Ce 0
Cs O
0.0
Gs 0
O'a
C.14853E-05
0. T5528E=-0¢8
3.0
G, TE508F-~11
a0
0w 98143E-08
Ce B4031E-13
0,191 76E=-06
Ca358TCE=CB
Qs O
0.9
CalllBEE-02
C.39G958FE-C2
q. 0
Ou2CT16E-04
0.0
Ce 15457E-0%
o
Uq 28393E~07

ACTIVITY
CURIES

Cel9151f 08
C.2562%E Q7
0.0

0.17321E 04
0.0

0.36062EF 08
0.36015E 38
C.152%¢€ 03
C.1G138F Q6
C.33575E-02
C.16214E-06
0.0

Ce%8106F 08B
0.24052F 08
C.24043E 08
0.0

0.22843E 04
C.1429¢E 05
0.0

Cue54£22£ 08
D.54615E 08
0. 26280E 0%
C.1C4B3EF OY
0. 26373E 07
C.7CT11E QO
C.0

C.82€17E 08
0.82614E C8
0,10195€ 0%
C.26610¢ Q7
C.0

QV.64258E 0B
C.95383EF Ga
C.BCO14E 06
C.13032E 08
Ce55502E D2
0.94189E 03
0.0

C-98182¢ 08
0.13319E 07
O.168S¢6E 05
0.0

Cel33828 03
Q.BTTLITE 03
GC.0

D.B248%E C8
C.83834E 048
D.75354E 06
Ce.7354CE O35
0,2C178F 032
C.3580CE OO0
0.,120C4E N
G.O

0.,35580€ 08
OO

POWER OENSITY

KW/LITER

0.75808E-C2
0.1306GE=-02
0.0
0.24485E-C6
0.0
0.99711E-02
D.70172E=-02
0,23422E-07
0.53019E-0%
0a35114E~13
0.1T576E-16
0.0
0.0
0.1144CE-CL
0.11439E-01
0.0
0.327256E-07
0.306312E-05
0.0
0.156516~C1
214475E-C1
D.19725E-(5
0.53433E~C3
0.26221€=02
0.53162E~10
0.0
0.23872E-C1
0.3S769E-01
0.10748E=-05
0.10293E-02
0.0
0.25408E-C1
D.10101E=02
0.6663TE~03
0.20537€~62
0.55271£-C8
0.78580E-07
0.0
0.517863E-01
0.167£2E=02
0.75154E-02
0.0
0.297TCE-CB
De22243E-06
0.0
0. 3L T66E-01
0.27318E-C1
De18182E=-C3
3.19261€-04
G,46853E-(7
0.43232E-11
0. 46089E=10
0.0
0.21670E-C1
040

GAMMA HEAT
K/ LITER

0a45257E-Q2
0.11206E=02
0.0

Ue®235%E~07
J.0

C.56835€6~C2
C.320876E-02
0.28106E-08
C.7G529E~05

GT3E-0C2
(63E=Q2

M

3644E-C5

3823E-02
5879E-C5
3358E-C3
5051€=-03

B44E-06
288E=-03

Q@

1616E~G3
5313E-03
0474E-02

o B ¢ & ® & 3 & & & 9 2 v 3 e € P b p b W ¥ & &

COFMRCPFOOCOUmS OO POOODHEFOONOON-DOE0

64431 E-02

175E-09
TYOE-0O

COOOOLODLO0O0ADCOOH0RODADOOCEDOOIOOIOO0
O D

e ® & 3 & € « b6 2 b @

0.2294BE~01L
0s18182E8=03
QeBREIRE=CE
0.46853E6~07
D.0
D.45089E~10
00
Qe11268E~01
Qa0

PRCCESS RATES

MOLES/DAY

0.56013E~05
0, 3678TE~D4
0.,11525E 00
G.4T3B5E~0D8
0,88429E-05

« ETH2BE~04
O« 24TC5E-03
0.68813E~C1
0.11912E 0C
0.31626E-02
0.17216E-10
Ge6TTHHE-C4
0.33256E-05
Ve 44 THEE-GS
0.21101E-04
0.28530E 00
D.22351E-08
0.11212E-0E
0, 158B0E=C4
0,49379E~-05
0. 36304E-04
Ua43437E-C1
0. 22%19E GO
0,32513E-02
O.11040E-02
0,59342E-01
Q. 48328E-05
0.46130E~03
0.4%3833E 00
1. 39055E-04
0.,14151E-01
0s71785%E~(5
D.42T38E 0O
0. 84T08BE~0O1
0. 174563E~-02
0.16591E=02
0.656568E-01
0. TE14BE-05
0.65261E=07
0. 4%9895E GC
054 8B1E~0Q4
0. 10%17E OO
0. 41883E-10
0. }ETHLE~GB
Qatb231E~05
Qubas33E-01
Da35756E~-02
Q. 10520 CC
0.2TTGTE GO
0.18955E~10
G.102%2E=-02
O.36640E~11
0. 40088E=07
0o 52359E=05
0.72108€ 00

L
STEADY STATE VALUES FCR

NULLTDE CONCENTRATINN

Cs126
BA126
1137
XE1L3Y
C5137
BAL3TM
PAYI2T
1132
XEi38
£S13e
AT R
129
XE129
5129
BA129
LAlze
XEL40
£sSi4n
BALALD
LAL4D
TEL140
XEL1GY
CSlal
BALI4T
LAIal
CF14Y
PRY 4T
XFl42
S142
BAl42
iAl42
CEla2
PR1G2
NO14&2
XEl142
5142
BAl43
LA143
CEl43
PR143
ND143
Lalsas
LEt4sa
PR144
NDisa
CELLS
PRI&GS
ND14S
CEl46
PRIALS
ND14S
Ceray
PR147T
NDYT AT
PM14T

GM-ATOM/CL

J0.51674F~-08
0.F0339F-06
N, 590255F=-11
0,60424F-11
0.129F7F-04
N.19453F=-11
0.23519%-08%8
D, 14919E-11
0, 75000E£-11
0,42545F=-1C
D.,41422F-0C%
0.42922F-12
0.,38207E5-11
0.1149RFE~-0%
0.10185E-0¢
ND.HI21RE-06
D.128p2F-11
0,12913E=-10
0,.,22RR725-056
0.332467=07
0.70728E-26
0.110475-12
D.434781F=-11
0.,27724£=0%
N.36489E-0A
0.37522c-04
0.40058%-06
0.22960£-17
0.36107E-12
0.17008F-00
0.18%5044F-0R
0.817495-05
0. 19405E-10
0.82R828C5-D9
N, 1QGRIE=-1 4
Ge 14B4GE~12
0,22940F-11
0.20214F-00
0.,27502£=07
N0. 1983606
0.470805=-06
Q. 7546752~

0.50343E~06
0.22557F=10
0.BAZSTE-N}T
0.25450==-10
0.30223E~08
O 41534E~048
3.90148E=10
0,1544TE-09
N.32556F-06
0.52610FE-~11
N.58264E-10
Je E29R4E-07
J3.1E724E-06

D.,9923RE-NT
0.15447E~-04
0.113¢3£-09
0,132435-09
0.,24673¢E-01
Ne37403E-10
0e8452215~04
C.28884E-10
Oel4438FE-09
0.3372%E-09
0.79642E-04
D.82525F-11
Je73481E-10
0,22107E-08
0.19582E~-07
Q. 1 3,7'-"OE-04
0.26575E-10
N.2482RE-09
0.4397T6HE-05
C.62927FE-06
e 13599E-04
J.2123%8-11
0.BR3500%-10
0.533055-058
0.7Ci1ERE~D7?
0.,72157E~-05
U.770205-05
Ou4B145E~12
0.59422F-11
0.32874E-08
J.289246E-07
J«1571RE-0S
0.3730%E-09
O.1611RE-OT
0.38350F~12
0.28551€F~-17
0.44106E~10
C.38EE6E-08
0.52877F-0%
0.37560E-35
C.90521£-0%
C.14512F=10
0.965%055=0%
0. 43370E-069
0. 16588E-05
J.499325-09
0.58103E-07
0.79858F-05
NDeI7333E-08
0.29699E-08
(0. 6259%E-0%
0.,10115E-09
0.,11202€E-08
Je11335F-05
0.30252E-05

THE FISSICN PROCUCTS
MOLE FRACTION

POISONING

AgS/ABS{FUEL?

T442F =04

IS4 EE-04

3853E-03

49£3E-04

BS3TF-C4

DoV O0O0O0DDT 20O OO
.
DO DTOMNIDIOT=IOINOONO

0.0
C.1158BF=-03
O, 63756E-04
0.0
0.0
Je0
Ds
Q. 1AT13E-04
O.40358E-018
D. 174635E~064
Ol()
0.0
0.0
0,0
0.,15087&£-35
0.27068E-073
0. 17234F-02
Ua 0
Coe 535947205
Ca 0
C.T71424E-05%
0.0
0.0
Cue 27T7OTE=03
0.0
O.

]

<

I2B2E-02

0
D4 B
De 0
0.0
0.0
0.1

558GE~02

ACTIVITY
CURTES

Co21486E
G,0

G.12035¢
t.1385¢8¢
CL634689F
£,59361¢E
5.0

CellB12E
Ge36388E
C,105Z8F
Ce0

C.10C25F
D.41506F
C.94225F
C.95646F
C.0

0.40354E
C.,91395F
0.98661CE
0.1072¢¢
C.0

C.25801F
D.8463CE
D.119G1E
0,12140¢
C.62625E
060

D.7T15032E
C.T3333E

D.11241€
£.10814F
2.77093¢
£.0

0488143
0.95885¢
9, 10151E
.0

0. 56044E
0.65572¢
9.0

C.50130E
0.50106%
0. 0

C.37809E
0.37800¢
0.28715E
£.88897¢

c7

09
08
o7
Qv

09
08

Q9
08
08
08

08
08
08
0%

08
o8
09
G9
08

o7
o8
o=
09

06

0%
08
o8
09
09
oeg

o8
o7
a8

03
08

08
o8

cs8
08
08
0é

POWER DENS({TY

KW/LITER

C.R202&6E-C3
C.0

0«30345E-02
N.10877E-C1
0e.24R31E-C3
Q0+56327E-03
0.0

C.57874E-C1
NaZ21316E-02
0.54601E-C2
0.0

0.28725€E-01
0.21327E-01
0.32263E-01
D.12326E-C1
Celd

0.13499E~-C1
0.45697E-01
0.78754€E~-02
Da%30326E-01
0.0

0.,10424E-C1
0.24T34E~01
0.23535E-0
0.17567E-01
D.297T87TE~C2
0.0

0.322C36E-0C2
Ca31519E-01
0.,16071E=C1
0.60352€-C1
0.9

0.45465E-04
0.0

De42431E~T3
0.14260E-01
0.23924E-C1
0.25123£-01
0.11R67E-0L
Qo4& 24E~C2
0.0

0,3295GE-C]
0.20323E-03
C.18251E-02
Ve

0.1G124E-01
G.6857BE-C2
0.0

0.34042E-C2
0.19454F-~C1
O.01

0.,10833E-01
0.,57402E-02
Ue19418E-C2
0.110B0E-C4

GAMMA HEAT
KW/LITER

0.75450E=-03

0.0

G.0

C.16%158~-02

0.0
5632TE-03

0.0

0.0

0e%53948E-C2

Qe3TETSE-C2

0.0

0.0

J.0

0.17099E~01

0.897B1F~-04%

0.0

0.0

0.21021E-01

0.3T014E~02

0,33130E-01

T430E-0Q3

£

i52=-01

94E2E-04

9965£-02

-t"Ol"‘OONO-POGOOO-“DOGD

o

T33E=02
9G4E=-02

48T3E-Q4
22802E-04
4289E-03

5319E-02
2061E-CY

® & & 8 5 & 2 2 ® 8 8 I ® m s & & &4 ¢ 3 & & R * e 8 " g4 8 8 &

2065&-(2

&4
0
o
0
5
4
0
0
3
0
1
1
0
Q
ol
B3496E~04

OOQQOOOQQOOOUOOOOOOGOOOOOOOQGOOOOOQ

-
-0

PROCESS RATES

MCLES/DAY

0s71227E~04
0.11087E-01
C.49083E-05
0.374460F OC
0.,17756E OC
C.26845E-07
De326457£-01
0s12353E-05
G.49983: 00
0. E0052E=-06
0a571¢2€-01
0.35539E-06
0.98562E-01
0.1%867E-05
0. 14055€E-04
0.504689E CO
0.17151E-01
0.178208-056
Ce31563E-02
0.27528E-01
G.58562¢ 00
0.201899E-02
0. 50003E-07
Qe 3BZ25GE~- 08
0.30213E-02
0.31074E 00
0.3314#8E 0C
D.31651E-04
0.49827E-08
04 23595E-05
0,31245TE-02
0.6TERBE 0C
0.,1¢067E-04
06594 10E-03
De 1847T5E-05
Q0,20492£-08
0.31657€-07
0,16738E-03
0¢22771E-01
0,16175€ 00
0.38982F 0C
0,624%945-0¢
0.41689E 00
D.18677E-04

‘O, 72160£-01

0.21072E-04
(}25022E-02
3.34390% 00
Q. T4643E-04
J+127T90E-03
J.256956E 00
O«%3561€E-C5
0.48242E-C4
0.483814E-01
0.,13028E CO

3.
STEADY STATE VALUES FOR THE FISSICN PRCDUCTS

NUCLIEE

SM147
CEl48
PR1I4S
NDL148
PM148M
PMILA
SMlas
PR14S
NDY149
PHM14G
$M149
ND1ISO
PM15G
SM150
NE15)Y
pr1Isl
SMisl
Euls1
pMiIsS2
SM152
EUlISZM
EuUls?
Ghls2
PMIS3
SuMi53
EULS3
GD1I53
PM1 54
iMI54
EULE&
GO154
SM1SS
EL11 595
60155
$M1Ss
EYl1Ee
GDisS
SM1IST
EULST
60157
E¢158
G158
EUIS9
G159
TB1SS
EUL&0
GU160
TB160
oYi1a0
60141
TRISY
pYletl
GD1s2
TBleZM
0Yle2

CONCENTRATION

GM=-2TOM/CC

0. 55086E=03
0, 23858E-11
O« 66022E-11
O.16458E-06
D.14027F=03%
0.12165E-08
Q. 904R0E~C8B
Ce43738F=11
0. 2052EE~09
0.61737E-C3
0. T2127E-08
0. 68583807
Q. 48TTRE~11
0.99843E-11
0,13522E-n%
0.21828E-07
0,105816E-10
0.32706FE-11
Vea22325-07

«S1T7386-13
0.49200E-1]
U.3432BE-11
D.15108E-11
0,11413E-018
0.18358E-07
0. TRTSLE~13
0.29109E-12
U.58016E-CR
0.14868E~08
0.85520E-11
0.13699€E~-11
G, 10262F-058
D.40RBTE-11
D.15685F-10
D.1095GE-08
0.25739€-08
D.61139E-14%
0.109%15-15
Ga16140E-10
De18975E-12
O 7RI94E=-09
0. 39564F=13
0. 23471E~-11
0. 1087T0E-09
0.15142%-14
0.302226-10
D.18628E-71
Q.557685~-12
0, TORG2E=15
D,15764E-11
0.569908E~11
D.57911E~14
0,119%0F-11

MOLE FRACTICN

D.10591F-06
D.454B8E~10
0.12696E=09
0431644E=05
C.26970E-07
0.22389E-07
0.173675=06
0.24095E-10
04354 70E=08
0.11870E-0%
C.140£2E-056
0.13181€-05
0.9378SE-10
0.1T110E=-05
0.16197E=09
Ty 26000E~07
0.4197CE~CS
5.20218E~09
D,62BR0E~-10
0.81200E-06
0.95471E=12
G.25943E-10
0.66984E-10
0. 29045E=10
D,21944E-07
0.35298E-06
0. 15149611
0,55968E~11
0.11155€=06
3,2 8580E=07
04 16443E-09
9.26339E~10
0.19731E~07
0.11707E-09
0.30187E-09
0.210708-07
0. 49485E-07
0.117556-12
€.21056E-09
0.31832E-09
0a366483E=11
G.15266E-07
C.T60TOE~12
0.45127E-10
0.,20323E=08
0.291138~13
0.58108E=09
0.35812E-10
0.16491E-10
Os 13534E-13

G,30309E=-10

0a134418=09
Qe TBOGZE-1D
0,111368€=~14
T.23083E=-10

PCISONING

ABS/ABSIFUEL)

0. 14072E=-04
0.0
0.0
Ue 1216 CE-04
0. 546C03E~03
0o 16020E~03
0, 150756-05
0e 0
0.0
0s111T5E-03
04 66282E~02
04 435 71E~C5
O‘O
0.14311E-03
040
9.0
0. 15C0SE=-02
0. FB529E-G6
0. 0
0.38679E-03
3.0
D.26565E-06
0. 66769E-0F
0.0
0, 0
0.13661£-03
0.0
De G
0.67332E-06
0. 25T71E~04
0. 155308-07
8.0 ]
0s 16604E-03
Ce3556CE-05
0.0
0.0
0.45132E=-06
s 0
s 0
. 426717E-04
0.0
0. 82542E-07
040
0.0

0. 2044 3E=-06

0.0
. 257T43E-0%
Q.0
0. 2753 4E-08
0.3
0.0
Oe. 71511E-C7F
Gas 0
G, 0
Q. L1198E=-07

ACTIVITY
CURIES

Ca0
0.25701F
Ce28TOQE
Ca 0
C.l8C57E
O.1218CE
Q.0
Cel4BOSE
J.14798E
G+ 18GB&E
[
C.0
0.23442F
Ce O
0. 647T75E
Ua628€5E
C.3714CE
Ce 0
Cuab2434F
C.0
C.T2183E
Ce51555E
C.0
C.21382E
D, 31509E
0.0
Coal7603E
0. 90646E
C.0
0.13752¢
Ca0
CubBIESE
0.83924F
Cs0
O0.21651E
0.3850CE
Ca0
0.9%195E
C.93487F
J.0
Ce32114€
0.0
O0,17112E
C.1691%E
C-.O
Cs47152E
C,0
Ca13567E
3.0
0.1%811F
Ua12352E
C.0
CobOl22E
Qe 6011 3E
Ce0

08
o8

ab6
07

08
08
08
06
o7
07
04
o7

03
0l

67
a7

o1
0s

04

Q5
3%

36
06

05
05

05

05
05

04
a3

04
o4

a2
02

POWER CENSITY

KW/LITER

0.0
DeT73541E-02
0, 76584E-C2
Ca 0
0.55411E=C%
0+24080E-C3
Q.0
Co42420E-C2
Nal18360E~02
G.90992E~03
Q.0

«0
«T6235E-C4
o0

SCooO

»11322E=-02
0,55123€E~03
D,15843E-0¢8
0.0
0:13739E~02
0.0
C.122048E-CH
0.18166E=-08
0.0
0.25273E-C3
C.14838E-03
0.0
0.861282E-10
0.13117E-03
0.0
0.3L130E=06
0.0
O+45173E-Ca
0170 TAE-Q6
Q.0
0+995T0E-05
0.10073E-03
0.0
Q0.125561E~04
0. 97504505
0.0
0.97537E~-05
00
04330%6E-C5
0,99383E-Ce
Q.3
D 10U65E-05
Q.0
0,28414E=-07
0.0
J.2185e€-Co
0,48664E-07
3.0
0,49441E~-08
Q0.97317€~08
0.0

GAMMA HEAT
KW/LITER

0T22E-02

OO0
Qoo

0.50424E5-04
C«11G77E-03
0.0
C.D
0.T1604E-03
0.1819BE-04

»
o

0315E~-04

3703E-03

5566E=-03

4188E-0%

6149E-C6
1311E=G5
2815E-05
655 5E-0%

BTTE=O5
902E=-05

COoOOLOLoCORDLOCOLQALOLLOOooOROCOSOO
P o~

¥ ¥ & 4 * 9 § % 3 v ¥ ¢ 4 9 s ¢ 9 ¢ & B ¥ 3w g ¥ © W 4 9

QPN ONLF QDA NOLOOTOOTDUNOONOS

O 5462C0E-C5
a0
0.12907E=05
0e11926E=-05
Ge 0
0.0
00
De23300E-07
Cul
Q.82238E£-07
Oei4599E~09
0.0
Q.0
Da0
0.0

PROCESS RATES

“OLES/DAY

0e45611E=02
0.1958%E~05
0. 54667E-05
0.13527E 00
Oell614E=02
0. 10072E-02
0.74917E-02
0.36215E=05
0e16957E-02
0.511186-02
0. £0557E-02
0e56762E-G1
8. 40388E-05
0.73684E-01
0e82670E-05
0.11196£-02
C.18074E-01
0.BT0E9E-05
Ce2T70T9E~T5
0.34968E-01
D.42837E-07
0.413176-05
0.2B846E-05
0.12508E=05
0.94459E-03
0.15201E-01
0.652395-07
G. 24102E~06
0.4803BE-02
0.123C8E=-02
0o 7O811E-05
0.11343E-05
0.84G6GE-03
0.50415E=05
0.12987E=04
0.%0738E-03
0e21312E-02
0.50623E~08
0.90676E-05
04133 64E=04
D.15711E-06
Do 657 40E-03
0432755E-07
0.19434E-05
0. B8BTS 15E~04
0.125376=08
0.25024E=04
De15422E-05
0. TLO1HE-05
0o 582 84E~0F
D.13052E~05
0,57884E-05
0. 33630E=05
DenTY50E-1D
0.95277E-05

Gl
STYEADY STATE VALUES FOR

NUCLIDE CONCENTRATION

TR16DM
TR163
dylio™
TR1AG
oY1 64
DYlesM
DY165
HO168
LYl 6é#
HN166M
®0146
Er166
Exls67

TOTAL POWER DENSITY DUE 7O RADICACTIVE DECAY =

CM-ATOM/CC

N.24348E-15
N.19444F-14
J,16798¢-11
0.,57882&-14
0. 26099LF-12
0,37771E-17
0. T52A9E~16
G.17040E-12
U 33B6NE-14
0,92790F-16
0.12723E-14
Ne38284F-173
0.99323E-15

D.406814F-14
0.37355£-13
0.380655~10
0.11129E-12
0.%0121E~11
0.72622F-16
0.14472E~14
0.32762E-11
0.65102£-112
N.1TE4T1E-14
O. 244855372
0. T3608E-172
0+19108E-13

TAOTAL NEUTRON 2BSORPYINN RATE IS

FEISSILE NEUTRON

BREEDING RATIO IS

POWER GENERATEL RY FISSINN
CHEMICAL PROCESSING RATS,

MOLAR DENSITY,
GAMMA POWER DENSITY,

ARSLCRPTION

MOLES/CC

RATE IS

IN MW TS
EQUIV/SEC =

KW/LITER =

THE FISSICN PRCOLLTS
MDLE FRACTION

POISOGNING

ABS/ABS{FUEL}

ACTIVITY
CURIES

0.0 C.2707GE 03
0.0 C.38215€ Q2
0.1155%8E-07 G.0
0.0 C.32655E 02
0. 77293F-08 C.C
0.0 C.23238F (2
0. 276867F-11 0442C95EF 01
0., 4E968E~-0¢ C.0
0.0 C.5391C¢F 01
G C.6i429t 01
0.8107T¢E~1C Q.0
Qe 74CT3E~11 C.0

0.23328E 01

0.2817GE-L3
0.12528E-013
C.108%29¢t 01
C.22¢14EF Co
J0.21710E-0C1
Us52C1CE-CI
0.62%25F CO

ELEMENTS AND THETR REMOVAL RATFS FROM REACTOR

SYM  MOLE/DAY  SYM

MOLE/DAY  SYM

MOLE/DAY SYM

MCLE/TAY SYM

MOLE/DAY SyM™

POWER NENSITY

KW/LIVER

0.32008E-G7
0.458377E-08
0.0
C.T3917F-08
C.0
D.¥19024E-08
0.32024E-09
0.0
0,11044E-09
0.,29796E-15
0.650337€~-09
0.0

0.0

MOLE/DAY SYM

GAMMA HEAT
KW /LITER

0.99217E-0D8
0.14222E=-02
0.0
C.O
0.0
0.,41854¢£-10
Q.86ah8E-11
0.0
0.0
042943GE-15
G
0

%

QOO
" a0 »
o

PROCESS RATES

MOLES/DAY

0.20160E-0%
3e16100E-038
0.16392E=-05
D.47926E-GB
0.21610E-06
0.212748-11
D.62323E-10
N.14109E-D&
0.28038E~-08
GeV6B30E-10
0.10544E~-08
0.31669E-Q7
Q0.8228SE-09

H
E
{y
My
AS
NB
N
LA
A
TA
L
AT

4,T30E-02 HE T.833F-01 LI 65,14lc 02
1,1320€ 03 NE  1.7758-01 N4 0,90
QuD AR 0.0 K 0.0
0.0 FE  D.0 cn 2.¢
1.738E-02 SE  2,188E-01 BR 3,741F-03
L.R13E 00 MO 1.22YE 00 TC 1.450fF-0Q7
2.970E-04 SN 2.626E-02 SB 1,S567E-02
E.388E-01 L€ 2,013F 00 PR 4,.961F-01
9.037E-05 DY ©S.250F-C5 HI  1.422F-07
0.0 W 0.0 RE 0.0
3.429E-12 PB  5.183E£-07 Bl 1.862F~10
0.0 TH 8.572F 01 Pa S.672E 00

B<
mG
LA
M1
KR
RU
TE
NE
ER
s
PO

X = O W NN DD O

1488 {2 8 3,31%5F-08 C .
0 AL 0.0 51 .
< ¢ 0.0 i .
c U 0.0 IN .
S99kt 00 28 1,113E-N2 SR .
G3%2E-01 RK 6.71i%E-03 PO
4CSE U0 f 1.2085£-02 XE
316E 00 P¥  1,387€-C1l SM
2E2E~-CE  TM 0.0 Y8
0 1 0.0 PT
TFEE-CE AT 0.0 RN
3T8E~CQ1 NP T.443E-03  PY

1. 61 5E-08 N
0.0 P
0.0 v
2.613E~CT GA
4.623E~C1 Y
1.615E-02 AG
2.444E 00 (S
1.506E~01 EU
J.0 Ltu
0.9 AU
S.153E~-07 FR
B.994E-03 AM

MOLEFDAY SYM MOLE/DAY
9.927E~-03 0 5.754E~(2
¢.0 S 0.0
Ca0 CR 0.0
1.7C8E~-0T GE 6.H681&~C4
5.98TE-01 IR 3.1&T7E GO
4.006E-03 CTD 1.763E~-03
1.787E-01 Ba 1.,039E-C1
1aB821E-02 G0 2.84TE=-G3
Je0 HF 0.0
0.0 HG 0.0
0.0 RA  1.4608-09
6.16XE-03 (M 5,8%568-C4

08
Table B-4. Summary of Nuclear and Chemical Properties of the Most Important Isotopes in the
Fuel Salt of a Typical 2250-Mw {thermal) Single-Fluid MSBR

Fe Pu PCISONING Fo Po TOTAL KEAT Fo Fo GANMA HEAT Fe Po CONLENTRATION Fa Po MOLE FRACTION
ABS/IFISSILE ABS) (KW/LITERY (KW/LITERY} (GMICC)
£21490 4. h2BE-D3 290960 Te TCHE-D2Z 3809480 52353E-02 380900 3,26TE-05 330500 6.282E-C4
541350 34909E-03 150870 & T92E-02 35QBT0 4.550E-02 55137C 1.287E-05 551379 224 THE=C4
601430 1.733E-02 571420 6,025E-02 571420 4,315E=-02 561380 4, 142E-06 561380 T+964E-C5
611470 1.555E-03 370900 5. G42E-02 37C9¢CC 4+ 1COE-02 4 {0930 3,330E-06 400930 6.4C3E~-CS
621510 1.501E-03 5231380 T TR7E~-DZ 284930 3.5867E-02 4C0%40C 3.257E-0% 400940 6« 263E-05
541351 1.1159E=-03 150880 Se.779E~02 ST14CO 3.313E-02 400920 3.207E-0¢ 400520 6.167E-G5
511481 5.46CE-04 2895230 5.7%4E-02 3609C0O 2y E4E-02 4 (0960 2. T46E-04 400%80 5.281E-C5
380900 4831E-04 370320 S.5C02F-02 5212¢0 242%5E=-02 5612790 2.382E-0% 561370 4, 522E-08
62152¢ TLBABE-DE 5113245 . 176F-02 28C940 2.170E-02 4C0910 1, 390E~06 400510 2,573E~-C5
601450 3TT1E-D4 250890 4.%33E~02 5514CC 2. 1C2E-02 4 (0950 9,4305-07 400850 1.8138-C5
5912420 2.705E-04 3739130 4.911E=-02 280%20 1.240E-02 58142¢C B.175E-07 581420 1.572E~C5
400930 2.538E-04 551400 4, EI0E-G2 551390 1.,710E-02 561360 8,C034E-07 5861360 1,345E=C5
631550 l.£40GE-04 E71400 4a2CAE-02 280910 1.631E-02 37087¢C T7.3285-07 370870 1,409E-(5
611480 1.502E-04 390940 4, 1672E-02 350940 1.415%E-02 581400 T.0738-07 581400 14360805
621800 1.431E-04 37TL9Y0 4, 124E-02 37CES0 1.257€~-02 57129¢ b, 122E-07 5713596 1,177E-CS
561370 1.3B5E=04 511220 3.9ITE-Q2 270910 1.25BE=~Q2 581440 5. 035E-07 581440 3. 6816~C6
631530 1. 385 6E-D4 360900 3.9228-02 561460 1,2C6E=02 60143¢C 4,708E=07 601430 2,052E-06
5814190 1.159e-04 380540 I,444F-02 5313260 1.127E~02 3s0910 4,2545~07 390510 + 1 30E=C6
611490 1.1176=-04 290950 342334E=-D2 4C0550 B.1456E-03 £014%0 4.153£-07 £D1450 T»9BHE~CH
71220 €.894E-05 871840 2, 296502 £10%71 T.2856-03 3808990 4,13BE~-07 3808990 T.957E~Gé
591410 5,23T4E-DF 390570 3, 2358-02 511210 T.282E~-03 400904 4y JODE=07 4£00%00 7.B882E-L6
8314560 5.338E=0% 551390 3. 228802 3£0A9¢ 7T.382E-03 591410 4, 00&E-0T 591410 T.702E-08
400910 S.148E-0F 399920 2. 18RE-02 5113ct T2 ZCTE-O3 38C88C 4.004E-07 380880 T.6599E-(6
541870 4.35B8E~GF 8213=0 3.177E-02 5113¢0 T+ 2CEE-03 58lalc 3.753E-07 581410 7.,216E=-0¢
5561200 241 7CE-DT 551430 3, 152E=-02 2GC950 7+0CLE-D3 £0146C 3. 256E~07 601460 £6.259E-06
STREAM CCMPCSITIONS FOR MSPER AY STEADY STATE
MOBLE GASFS NOBLE METALS SEMI-NCBLE METALS RARE EARTHS HALOGENS ACTIVE METALS
NUCLIRE GM/DAY NUCLIDE  Gu/laY MUCLICE GM/CAY MUCLTIDE GM/OAY NUCELIDE  GMSTAY NUCLIDE GM/CAY
24613560 S.A07E O 5213240 A.588% €1 SL053C 6.411E Q1 FELA2(0 9.512E Ot 531350 4.827E-0% IBOSCC 4,058 L1}
54Y280 6.PR8E O} 521320 S.78&E 01 4009440 4,338 O 581400 B,199€ 01 531310 4.2355E-01 581370 Z,433& {1
541370 5.132€ Ot 521321 S,6847% 03 4C092¢ 6. 108E 01 S71390 T7.046E 01 531290 4.119%~-01 561380 7.E8BE CQ
561380 5.09CE 0% 410850 Z.876E U1 400560 BL.458E O BE1440 6.C03E 01 350810 2.B6SE-0OL 51370 4,447 CC
I40EB0 4,39TE 01 AT0970 3.682F C1 400910 2.518E £} £01430 5,.574F 01 531330 2,3238-01 561350 1.508BE LU
360870 3.604E §1 3213200 32,3192E {1 400950 1.8%48€ C1 601450 4,987EF 01 531270 1.771E-02 370870 8.758E-01
360890 2.730E 01 E21210 2.0028 {4 400200 7,837 00 551410 4,67TE Q1 531340 1. 271E-02 380890 5,083E-C1
IL0BB0 2. T7H4E 01 411000 2.68GE 01 £0124C 1.1%28 CO 581410 4,381E 01 3506830 8.602E-03 380880 4.883E-C1
3160851 1,614€ O} 470980 2,607F 01 51128¢ 8.46(0E~-01 £01460 3,3836E {1 531320 B5.155£-03 561400 4.419E~C}
51340 1,453E O1 42310990 2.5732F 01 ACL124C B8.2715E-CL 390910 3.2085 ) 350840 3,603E-03 £51330 1.989E~01
541251 1.420E 01 10881 2.348E 01 51123¢ S.478E-01 £61430 2.313E Q1 250790 1.471E-03 ITO835C B.H2IE~Q2
54129C !,3VCE O1L a20990 2,30RE G3 SL1220 3,5%8€E~C} QORGS0 2.032F 1 350850 8,T94E-04 380910 BLBT9E-L3
521330 8,7314¢ 00 4210205 2.0&88F (1 4L0STC 2.627E=01 £C1480 2.017E 01 531380 T.121E-04 551360 9.46B7E-C3
5%131C 7.774F 00 421010 2,027c 01 50288 Z2.145E~01 £1147C 1.915E 01 380870 7,116t-04 380920 T.92B£-03
363900 T.2R4E 20 421000 1.8822& ¢! 5311210 2.11%E=-C1 €21500 1.105F Gl 531270 6.722E-04 3BOBET Z,621E-03
AL0B4AT £.935E 00 521290 1.537¢ ©¢1 S0119C 2.001E-C2 £01440 1,0%4E Q1 350840 4,984E-04 561390 1,954E-43
360831 7,788 GO BZLI2R0 l.47¥5F {1 5CL18C 1.%88E-01 £013500 8.514E 00 350820 3.723E-04% 5531330 5,994E~04
260820 2.5268 00 410971 1.378F 41 51270 1.9%4E-CL £C14T0 T, 1T6E 0O 250880 2.4B6E-04 561340 6.195E=C4
541400 2.401€ 00O 52132G 1,127€ g1 S5CL17¢ 1.363E=01 621820 $.315E Q¢ 5313R0 1.7C5E-04 561417 5,3858-04
541320 1.8&4BE 20 451030 9,515 09 48114C 1.0B0E=CL 571400 3.854E 00 531300 1.4T71E-0Q4 561420 3.351&-04%
380850 1.0%%E DO 2a(84y 3,017 CC 511260 9.7T86E=02 B81&30 3,2%6E GO 350890 T.4T75E-Q5 551340 Z2.,246E-C4
350910 T.904E-C1 %212%1 8.877E (O 48YLEC F,450E=02 621510 2.729E Q0 531390 4.940E-05 551390 2,206F=(4
€41331 2.Z207TE-GY 4311510 8,7C01E 00 5T1250 3.924E-02 521530 2.,326E 0C 250841 3.646E-C% IBEGI3C 1.045E-(%
360920 5.723E-G2 521380 B8.6TLE Q0 325760 3.TFLI9E-C? £21480 1.10%€ 0C 250801 1.538E-05 37CBYC 9.61BE=-(5

541410 2,94 8E-02 431040 443965 03O 45115C 3.386E-02 £214%0 9,023F-01 350821 1.110E-C8 551380 8,292L-0C%5

13
STRFAM HEAT RATES FCR MSER AT STEACY STaATE

NCBLE GASES

NUCLIDE

541380
350880
35C8%0
360870
54137¢C
360900
5413G6¢C
41350
541400
541351
260851
34091¢
541330
3560920
360850
541610
360831
350930
541331
541420
260940
541430
541311

10030
541291

{MW}

2.814% 0OC
2.634E QO
2.29%E 00
1.124E 09
B.620E-01
T.J61E-01
5.864E-01
2.388£-01
1.538E-01
1.28¢E-01
9, 952F-02
T.013E-02
1.335€-02
be2408-03
2,913€-03
1.675E-032
1.575€-03
8,959E-04
T.691E~-04
3.624E-04
2.504E~-05
2,172E-05
2.022F=056
T.5T3E-06
4,537E-12

NOBLE METALS

NUCL IDE

551340
521331
5217220
411000
421020
421010
47 (9s0
410981
340840
410970
521310
521350
4311010
410959
431040
521330
410971
421040
£20990
240853
4£21030
521311
340830
£212%90
431030

(MW}

3.283E 0OC
1.856E 00
1.43%F 0C
9.01¢t-01
.662E-01
G b41E-01
5,500F-01
5.459E-01
4,9T76F-01
4,G19F-01
4.T24E-01
4.043E-C1
3.5T7xE-01
3,68T7E~01
2.1C4E~-01
3,0235E=01
1. 026E-01
2.54TE-01
Z.29RE-01
1.,981F-01
1.7351e-01
1.2332-01
1.1708-01
8.144£-02
7 R9EE-Q2

SEMI-NOBLE METALS

NUCLICE

4CAa%80
4C0%39
SCLzéc
4C0sTC
5112590
51127C
51124¢
5C1256¢C
511250
501291
511310
511280
501231
5Ci230
5C127C
5112¢0
511330
501320
5il24c
511320
5C1310
511281
511301
5013C0
32077C

IMW)

3.7CCE-01
2.310E=-02
2eC3GE-02
B.,2&CE-03
4. TCTE-C3
2.09%E-03
1.602E-03

oESEE'C‘D
205345'04
1.541E-04
1.462E-04
1o 94 8E~04
1.257F-04
1.206E~C4
T«B8Z6E-C5
5.176E-C5
4.4T5F-05
4 36CE~05
34241E-G5
3.195£-05
1.7291‘3"05
1.560E-05
1.233E-058
B.CB1E-06

RARE
NUCL IDE

281440
3¢091¢
581410
571400
£61430
€C1470
581430
£11470
353930
39060¢C
390920
571420
571410
€11431
£11490
831540
591450
€3156C
©11480
61151¢
390940
390950
57143¢C
360911
£21530

EARTHS
{ MW)

€.534E-C1
2.526E-01
1,152E-01
B.610E-02
6.613E-02
3. 0485_02
2. 380E-02
1.268E~02
1.236E-02
7+039E-03
£.599E-33
4.605E-G3
4,52GE~-03
2.904F=-03
2.404E-03
2.172E-03
2.040%-03
1. 804E-03
1.553€=-03
T.6EQE-04
T.007€-04
5.5455=04
5.333E-04
4o 409E-04
3.93T7TE~C4

HALJOGENS

MUCLIDE

531350
53131¢
£31330
531340
350840
£31320
350870
350830
3508380
53135890
350860
350850
260820
531370
531380
350890
531390
531300
350841
350801
35082L
3508090
531280
5313¢1

a

{ MW}

1.200E-02
2' SZSE_GB
2+512E-03
3.4 66E-04
1.375E-04
T.383E-05
4.966F=-05
2.T6TE-05
2.486E-05
2.061E-05
1.756E-05
1.414E-05
1.226%E~-D5
1.,167E-05
G, 013E-06
2.908E=06
1.870t-06
1.7752-0%
2.064E-07
4.284E-08
1.251E-08
5,C78E~0F
3.645E-09%
0.0

ACTIVE METALS

NUCLIDE

380900
551370
561403
2808590
380910
551360
380920
561390
561410
561420
380930
55139¢C
370890
5513490
551380
370900
380940
551400
370910
380950
551410
27086C
37093¢C
561430
370920

{MW)

4. 860E-01
1.228E-01
1.188E-C2
34872E-C3
3.2B3E~C4
2.07TE-C4
1.152E-(4
}.470E-C5
1.159E-(5
1.117E-C5
J.089E-C6
S5.885E-C6
4,342E-06
3.315E~-C%
2+430E~06
2.382E-C6
1.367E-05
1.355€E-04
1.312E=C%
B.345E-C7
3. 1858E-07
2.4425-07
1.5693E-07
1.5613E~GY
1.295E=-C7

<3
Table B-5. Flow Rates and Heat-Generation Rates of the Fission-Product Streams in a
Typical 2250-Mw (thermal) Single-Fluid MSBR

 

 

 

Flow Rates Total Power Gamma Power Poison

Stream g/day moles/day (Mw) (M ) Fraction
1 500 i .388 11.68 5.75 5.02 x 107
D 682.8 6.149 15.96 7.50 6.37 x 1071
3 299.2 %.190 0.43 0.34 3.5% x 107
4 TLT.T 5.242 1.29 o.i5 1.52 x 1072
5 1.884 0.016 0.018 0.012 2.50 x 10'6
6 80.81 0.751 0.62 0.13 7.50 x 10'1+

Totals 2082 19.74 20.00 13.87 2.13 x 1672

 

8
8L
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L

Table B-6. Material Balance for Thorium Consumption in a Typical
2250-Mw (thermal) Single-Fluid MSBR

 

Processing rate of fission products 2282.37 g/day
Processing rate of actinides 201.20 g/day
Deposition rate in graphite 35.65 g/day
Fission rate of miscellaneous actinides 6.01 g/day

Total fission products and actinides removed 2525.23 g/day

Burnup rate of thorium 2529.06 g/day

 
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