ORNL-5388 - the Molten Salt Energy Technologies Web Site

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Fig. 4.5-2. Equilibrium Cycle Net Fissile Production for Possible
Oxide-Fueled 233U Production Reactors. (ORNL Cases 10, 2, and 4 from Table 4.5-1)
References for Section 4.5
D. R. Hoffner, R. W. Hondie, and R. P. Omberg, "Reactor Physics Parameters of
Alternate Fueled LMFBR Core Designs ,I' Hanford EngineerinQ Gevelopment Laboratory,
(June 1977).
Y. I. Chang, C. E. Till, R. R. Rudolph, J. P. Deen, and M. J. Ring, "Alternative
Fuel Cycle Options: Performance Characteristics of and Impact on Nuclear Power
Growth Potential ,'I RSS-TM-4, Araonne National Laboratory, (July 1977).
T. J. Burns and J. R. White, "Preliminary Evaluation of Alternative LMFBR Fuel Cycle
Options," ORNL-5389, (1978).
"The Proliferation-Resistant Preconceptual Core Design Study," J. C. Chandler, D. R.
Marr, D. C. Curry, M. B. Parker, and R. P. Omberg, Hanford Engineering Development
Laboratory; and V. W. Lowery, DOE Division of Reactor Research and Technology (March,
1978).
BNL-17541 (ENDF-201), 2nd Edition, "ENDF/B Summary Documentation," compiled by
D. Garber (October 1975).
R. L. Macklin and J. Halperin, '1232Th(~,v) Cross Section from 2.6 to 800 keV,"
NucZ. SCi. fig. 64, NO. 4, pp. 849-858 (1977).
L. Weston, private communication, March 1971.
B. R. Seghal, J. A. Naser, C. Lin, and W. B. Loewenstein, "Thorium-Based Fuels in
Fast Breeder Reactors," NEZ. Tech. 35, No. 3, p.' 635 (October 1977).