References
- C. V. CHESTER and R. O. CHESTER, “Civil Defense Implications of a Pressurized Water Reactor in a Thermonuclear Target Area,” Nucl. Appl. Technol., 9, 786 (1970).
- R. O. CHESTER and C. V. CHESTER, “Power Reactor Vulnerability,” Civil Defense Research Project Annual Progress Report, March 1971-1972, ORNL-4784, Oak Ridge National Laboratory (1972).
- N. M. NEWMARK and J. D. HALTIWANGER, “Air Force Design Manual—Principles and Practices for Design of Hardened Structures,” AFSWC-TDR-62-138, Air Force Special Weapons Center, Kirtland Air Force Base, New Mexico (1962).
- SAMUAL GLASSTONE, Ed., The Effects of Nuclear Weapons, U.S. Department of Defense, U.S. Atomic Energy Commission (1962).
- General Electric Task II Report: Conceptual Plant Design, Systems Descriptions, and Costs for a 1000-MW(e) Sodium Cooled Fast Reactor, complied by W. R. GEE, Jr., GEAP-5678, General Electric Co. (1968).
- B. WOLFE, General Electric Co., Sunnyvale, California, Personal Communication (1970).
- R. W. HILLENDAHL, “Theoretical Models for Nuclear Fireballs (U),” LMSC-B00670, Lockheed Missiles and Space Co. (1962).
- HYMAN SERBIN, “The High Speed Flow of Gas Around Blunt Bodies,” The Aeronautical Quarterly, 9, 313 (1958).
- Civil Defense Research Project Annual Progress Report, March 1970-March 1971, ORNL-4679, Chap. 22, p. 123, Oak Ridge National Laboratory (1972).
- J. F. BYRON, “Yield and Flow of Polycrystalline Uranium Dioxide,” J. Nucl. Mater., 27, 48 (1968).
- C. S. MORGAN, “Deformation of UO2,” Fuels and Materials Development Program Quarterly Progress Report, D. J. RUCKER, Ed., ORNL-4480, p. 22, Oak Ridge National Laboratory (1969).
- M. O. MARLOWE, “High Temperature Isothermal Elastic Moduli of UO2,” J. Nucl. Mater., 33, 242 (1969).
- T. B. Fowler, Reactor Analysis Department, kindly supplied the nuclear reactor core analysis code CITATION (described in ORNL-TM-2496) and the changes necessary to introduce a volume decrease. L. L. Bennett, Reactor Analysis Department, provided the results of calculation of the effective multiplication factor for the uncompressed core that was used as a starting point for the compressed core cases.
- D. E. SIMPSON, J. W. HAGAN, A. E. WALTAR, R. A. HARRIS, A. PADILLA, and G. L. FOX, Preliminary Analysis of Postulated Maximum Accidents for the FFTF, BNWL-760, Suppl. 1, Additional Calculations for Sodium-In Conditions, by R. A. HARRIS, Battelle-North-west (1968).
- ANDREW PADILLA, Jr., “Transient Analysis of Fuel-Sodium Interaction,” Trans. Am. Nucl. Soc., 13, 375 (1970).
- R. A. MEYER and B. WOLFE, “Fast Reactor Meltdown Accidents Using BETHE-TAIT Analysis,” Advances in Nuclear Science and Technology, Vol. 4, pp. 197–250, Academic Press, New York (1968).