. 196 15.
FEFEENCES
1. C. L. Davis, J. M. Bookston, and B. E. Smith, "GTJU-I1 - A Multigroup One-Dimensional Diff'usion Program f o r t h e IEM-704," USAEC Report GMR-101, General Motors, November 12, 1957. 2. D. J. Hughes and H. B. Schwartz, "Neutron Cross Sections," USAEC Report BNL-325, Second Edition, Brookhaven National Laboratory, J u l y 1958. 3. C. W. Nestor, Jr., "Multigroup Neutron Cross Sections," USAEC Report ORNL CF-60-3-35, Oak Ridge National Laboratory, March 1960. 4. Oak Ridge National Laboratory, "MSW Quart. Progr. Rept. J u l y 31, 1960," USAEC Report ORNL-3014, pp. 41-45. 5. C. W. Nestor, Jr., "A Computational Survey of Some GraphiteModerated Molten S a l t Reactors," USAEC Report ORNL CF-61-3-98, Oak Ridge National Laboratory, March 15, 1961. 6. Oak R i d g e National Laboratory, "MSW Progr. Rept. Aug. 1, 1960 t o Feb. 28, 1961,'' USAEC Report OIWL-3122, p. 70. 7. Oak Ridge National Laboratory, "MSW Progr. Rept. Mar. 1 t o Aug. 31, 1961," USAEC Report Om-3215, pp. 83-49. 8. G. F. Kuncir, "A Program f o r t h e Calculation of Resonance Integrals," USAEC Report GA-2525, General Atomic, August 28, 1961. 9. G. I. &ll, "A Simple Treatment for E f f e c t i v e Resonance Absorpt i o n Cross Sections i n Dense Lattices," Nucl. Sei. E%., 5 ( 2 ) : 138-139 (February 1959). A Consistent PI M u l t i 10. G. D. Joanou and J. S. Dudek, "GAM-1: group Code f o r t h e Calculation of Fast Neutron Spectra and Multigroup Constants," USAEC Report GA-1850, General Atomic, June 28, 1961. 11. H. C. Honeck, "THERMOS: A Thermalization Transport Theory Code f o r Reactor L a t t i c e Calculations," USAEC Report BNL-5826, Brookhaven Nat i o n a l Laboratory, September 1961. 12. D. E. Parks, J. R. Beyster, and N. F. Wikner, "Thermal Neutron Spectra i n Graphite," Nucl. Sei. Eng., 1 3 ( 4 ) : 306-324 (August 1962). 13. James Replogle, "MODRIC: A One Dimensional Neutron Diff'usion Code for t h e I ~ - 7 0 9 0 , " USAEC Report K-1520, Union Carbide Nuclear Company, September 6, 1962. 14. T. B. Fowler and M. L. Tobias, "EQUIPXEE-3: A Two-Dimensional, Two-Group, Neutron Diff'usion Code for t h e IEM-7090 Computer," USAEC Report ORNL-3199, Oak Ridge National Laboratory, February 7, 1962. 15. C. W. Nestor, Jr., "EQUIPOISE 3A," USAEC Report ORNL-3199 Addendum, Oak Ridge National Laboratory, June 6, 1962. 16. B. E. Prince and J. R. Engel, "Temperature and Reactivity Coe f f i c i e n t Averaging i n t h e MSRE," USAEC Report ORNL !IN-379, Oak Ridge N a t i o n a l Laboratory, October 15, 1962. 17. G. H. Kear and M. H. Ruderman, "An Analysis of Methods of Cont r o l Rod Theory and Comparisons with Experiment," USAEC Report GEAP-3937, General E l e c t r i c , May 27, 1962. 18. B. E. Prince, "Control Rod Worth i n t h e MSRE," USAEC Report om m--, Oak Ridge National Laboratory ( i n preparation). 19. R. V. Meghreblian and D. K. Holmes, Reactor Analysis, p. 656, McGraw-Hill, New York, 1960. 20. S. A. Kushneriuk and K. Jirlow, "The Linear Extrapolation Length and Blackness for I n f i n i t e Cylinders," J. Nucl. Energy, Pts. A and B, 16 ( 9 ) : 464-466 (September 1962).
A
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4
Y