Review of Molten Salt Reactor Physics Calculations [Disc 2]

22
on an average fuel salt temperature of 922°K and an average blanket salt
temperature of 895°K. The previous calculations were done with the kernels
for fluorine, lithium and beryllium cquted ,at W°K and for the
heavy metals and carbon at 1000'K.
c
References
-1. J. R. Stehn et al., Neutron Cross Sections, USAeC Report BIG-325,
2nd Ed., Supplement No. 2, February 1965.
2. H. Brown and D. St. John, Neutron Ehergy Spectrum in D20, USAEC
Report DO-33 (1954).
3. D. E. Parks, The Calculation of Thermal Neutron Scattering ICernels
in Graphite, USAM: Report GA-2438 (October 1961).
4. F. D. Brooks et d., Eta and Neutron Cross Sections of from
, 0.04 to 200 ev, AWE-M-1670, Harwell, November 1965.
5. Personal Communication L. Weston and G. DeSaussure to E. H, Gift,
March 1966;.
6. R. L. Machin et al., Manganese Bath Measurements of Eta of 833
and l?35, Nucl. Sci. &g ., 8(3): 210-220 (September 1960). .
7.
R. Gwin and D. W. M~gnuson, The Measurement of Eta and Other Nuclear
Properties of $33 and $35 in Critical Aqueous Solution, Nucl. Sci.
-0, E(3): 364-380 (March 1962).
8. M. S. Moore and C. W. Retch, Multilevel Analysis of tb Slow Neutron
Cross Sectivns of l?33, m. Review, U8(3): 714-718 (May 1960).
9.
10.
D. Hughes et al., Neutron Cross Sections, USAEC Report -325,
2nd M. , July 1958 and Supplement no. 1 dated January 1960.
R. C. Block et al., Thermal Neutron Cross Section Measurements of
.U-233, U-235, Pu-240, U-234 and 1-129 with the ORNL Fast Chopper
Time of Flight Neutron Spectrometer, Nucl. Sci. Eng., 8(2):
112-121
11. S. Oleksa, Meutron Scattering Cross Section of U-233, Phys. Review,
lOg(5): 1645 (March 1958).
12. F. B. Simpson et al., The Resolved Resonance Parameters of Pa-233,
Bull. of Am. Phys. Soc., 9, page 433 (1964).
13. L. Nordheim, Resonance Absorption, USAEC Report GA-3973, Feb. 12, 1963.
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