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ORNL-CF-56-9-32.txt
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ORNL-CF-56-9-32.txt
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X-828
" DATE: - September"_“ 11.; 1956
DAK RIDGE NAT!ONAL LABORM’Q;,;
© .. Operoted By ¥
UNION CARB!DE NUCLEAR COMPANY
_Posf OFFICE BOX P
" OAK RIDGE, TENNESSEE
SUBJECT: FUSED SALT POWER REACTOR STUDY:
- Minutes of Discussian Meeting No. 2
T0: Distribution
FROM: L. G, Alexander- :
5:»; fiu’mm&ty OfF:
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Laboratory Records
G.
BE.
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.SO"
M.
_Alexander
Arnold
Bettis
Billington
~Carrison
Charpie
Qromer
Ergen
Gregg
Gresky
Grimes
Jordan
Kinyon
'MacPherson
Manly
“Mann
Poppendiek
,- Roberts
Swartout
VonderLage
Weinberg
C. R. Library
_ORNL
CENTRAL FILES NUMBER
56-9-Z=
‘This document consists of 3 'puge"s."_.':.
Copy 2 of 24 copies.._S‘efies A
For Internal Use Only =
FUSED SALT 'roWER-'R'EAcTOR STUDY
Minutes of Discussion Meeting No. 2
~ August 22, 1956
Present: L. G. Alexander - - W. H. Jordan
L
W. E. Arnold | " B. WoKinyon
‘E. S. Bettis = H. G. MacPherson
D. A, Carrison o L. A+ Mann
S. J. Cromer | 'H. F. Poppendiek
W. K. Ergen = T, J. Roberts
J. L. Cregg S ‘F. C. VonderLage
A, J. Gresky "A. M. Weinberg
W. R. Grimes -
t”Mr, MaePherson opened. the meeting by summarizing the results of D Ao Carrison 8
y}ceeonomie study. The importance of reducing chemical processing costs was empha-{cfrf’”i'
- .slzed. In re the containment problem, the 1ron=ehromiumimolybdenumnnickel alloy
”={]propoaed by the Metallurgy Division was discussed. It appears to have good: highe-.f-'e~’
- temperature strength, ductility, and corrosion resistance. A test for'this“afloyg'pJ"
in a fused-salt-to-sodium heat ~exchanger hasg ‘been scheduled. - The tubing should
S be available in three or four months,_ “Mr. Gregg ‘noted that although inconel may o
. _prove to be satisfactory at 1200°F, the new alloy should be better. Mr. Bettis
:f;‘inquired concerning the possibility of setting up an inconel loop soon. Mr. . Gregg e
replied that such a 100p is being designed and should be in operation in a matter FENe
'«“-f:-of weeka, _ _ o
._‘-_-_J_.Mr° MaePheraon discussed the possibility of obtaining high conversion ratios in
@& U-233 breeder. On the basis of some preliminary calculations, he felt that one.
- could obtain conversions up to 0.8 in a clean system by keeping the coneentrations
. of thorium and uranium high (4 and 0.2 mol percent; respectively). Under these
"?xeonditions, nearly all absorptions take place at energies above 1.0 ev, in which
'.frange both U-233 and Th compete favorably with Na and Zr for neutrons. Mr. Wein-
‘“if;'berg noted that the recent British data onn in the vieinity of 2 ev clouds the -
'_situation here.
'*7The question of how much ThF) can be incorporated into the melt without raising
' the melting point too high was discussed. Mr. Grimes predicted that the addition:_.'f“'f"-
o of b mol percent of: ThFu would not raise the melting point above 1050CF, and that
1t would be possible to lower the melting point by the addition of KF. Mr. Ergen“:
.~ noted the adverse effect of K on the nuclear economy, But Mr. MacPherson felt -
‘fi]that the effect would not be serious if the neutron spectrum were maintained above
1l ev. Mr. Weinberg inquired if the effeet of fission .product poisons on the neutronf13
"*1eeonomy had been studied. Mr. MaePherson replied that this is being considered and {1"
~that it would probably be- neceasary to process the fuel continuously to remove
o_fiasion products if high conversion ratioa are to be obtained. .
“”7T;ffdf;GA/dé?dd
R
o
efb;Mr, MacPherson summarized the result: of a recent conference with Mr. Culler.
I appears that the cost of U-233 ie 80 high that 1t will ve necessary to start
_f'la Th-U—233 breeder with.U-235.,_ -
re"Mr. Carrison suggested that a loop should be eet up for the study of the effect
~of ThF) on corrosion. Mr. Grimes remarked ‘that there are four thermal loOps now
'[u2;‘;g'7d .
--operating with Li-Be-Th fluoride mixtures., He believee that Th will not increase jf.r
~ the rate of corrosion in the fuel under considera.tionu
r;:Ways and means of producing various tranemutation products other than U~233 were
~discussed at some length. Mr. Bettis remarked that it would be poesible to add
‘a8 much as 20 percent of LiF to the melt without impairing the melting point,,-j”’
_Q”ng,.Weinberg preferred to produce transmutation products in a blanket in order
_fiflto 8implify the separation and. purification processes. Mr. Grimes noted that
- lithium hydride is very stable, having a vapor pressure of only one atmosPhere
- at T50°F. “Mr. Ergen remarked- upon the adverse effect of 1Li on neutron economy
_and noted the advantage of using it in a blanket. Mr,_Weinberg proposed putting .
- Li-Al alloy in tubes just inside the core container to avold losses in the con~
" tainer wall, ‘Mr. Bettis remarked upon the high.melting point of LiF and suggested;i_.;&l
'7fjthat the powder could be used in tubes. . Mr. MacPherson: voiced the philosophy that;f"?°”
;;1the reactor ought to be designed to produce power as cheaply as possible, with
. excess neutrons going to produce U-233 which would in turn be used for fuel; if
~ later it proved more profitable to divert neutrons to some other use, this could T
“ be done. Mr. VonderLage raiged the point that a U-235 burner has the best market Lo
_.cypotential at present if power can be produced at, or. below, 10 mil/kw hr’.'”“
'mJiQqu, Bettis concurred°
'““f,Mra.Jorden inquired if there ie any cle&r choice between one and two region
"1ffimechines,. Mr, Weinberg referred to the Wehmeyer report and remarked that they'
.'fjff;had calculated a breeding ratio of about unity.-v'
. »Mr. Weinberg reported that the (n,p) reaction in Clu36 in the high energy region
"*1-{;i@severely prejudices the fast breeder being etudied by Bulmer et al. -
L. c Alexander