Uranium-Plutonium Carbide Fuel for Fast Breeder Reactors

References

• H. A. BETHE, “Advanced Nuclear Power,” Report of the Cornell Workshops on the Major Issues of a National Energy Research and Development Program, Cornell University, Ithaca, New York, September 14-October 17, 1973, p. 169.
   Google Scholar
• J. M. SIMMONS, J. A. LEARY, J. H. KITTEL and C. M. COX, “The U.S. Advanced LMFBR Fuels Development Program,” Proc. Topi. Mt. Advanced LMFBR Fuels, Tucson, Arizona, October 10–13, 1977, p. 2.
   Google Scholar
• J. A. VITTI, P. K. DOHERTY, G. F. di LAURO, J. C. GILBERTSON and D. W. STUTEVILLE, “Design of Prototype Carbide Subassemblies and an Evaluation of Proof-Testing Plans in the Fast Flux Test Reactor,” Nucl. Technol., 26, 442 (1975).
   Web of Science ®Google Scholar
• R. C. NOYES, P. K. DOHERTY, S. A. CASPERSSON, N. HANUS and D. W. STUTEVILLE, “Optimum Pin Diameter for Liquid-Metal Fast Breeder Reactor Carbide Fuels,” Nucl. Technol., 26, 460 (1975).
   Web of Science ®Google Scholar
• S. A. CASPERSSON, R. C. NOYES, M. R. KULW1CH, G. F. di LAURO and R. H. KLINETOB, “Optimization System Design Studies of Advanced Carbide Fuel,” Proc. Topl. Mtg. Advanced LMFBR Fuels, Tucson, Arizona, October 10–13, 1977, p. 614.
   Google Scholar
• R. C. NOYES, R. H. KLINETOB and M. R. KULWICH, “Design of Carbide Fueled LMFBR Cores,” Proc. Int. Conf. Fast Breeder Reactor Fuel Performance, Monterey, California, March 5–8, 1979, p. 897.
   Google Scholar
• E. C. WEBER, V. W. LOWERY, A. BIANCHERIA and R. P. OMBERG, “The Performance of FBR Core Designs with Alternative Fuel,” Proc. Int. Conf. Fast Breeder Reactor Fuel Performance, Monterey, California, March 5–6, 1979, p. 879.
   Google Scholar
• L. D. FELTON and L. B. LEVITT, Eds., “Liquid Metal Fast Breeder Reactor Conceptual Design Study, Phase I, Driver and Blanket Fuel Section,” FBR-79-3, U.S. Department of Energy (1979).
   Google Scholar
• H. D. LEWIS and J. F. KERRISK, “Electrical and Thermal Transport Properties of Uranium and Plutonium Carbides, A Review of the Literature,” LA-6096, Los Alamos National Laboratory (1976).
   Google Scholar
• Hanford Engineering Development Laboratory Compilation, “Nuclear Systems Materials Handbook,” TIP-26666, Vol. 1, Part IV (1977).
   Google Scholar
• L. A. NEIMARK, Compiler, “Advanced Fuels Development Program Quality Progress Report for the Period July-September 1980,” ANL-AFP-94, p. 41, Argonne National Laboratory (1980).
   Google Scholar
• J. O. BARNER, T. W. LATIMER, J. F. KERRISK, R. L. PETTY and J. L. GREEN, “Advanced Carbide Fuels–U.S. Experience,” Proc. Topi. Advanced LMFBR Fuels, Tucson, Arizona, October 10–13, 1977, p. 268.
   Google Scholar
• R. L. GUTIERREZ and R. J. HERBST, “Preparation of Carbide-Type, Advanced LMFBR Fuel Pellets for Irradiation Testing,” LA-8304-MS, Los Alamos National Laboratory (1980).
   Google Scholar
• P. D. SHALEK and R. B. MATTHEWS, “Progress in Processing Carbide Fuels for the LMFBR,” Trans. Am. Nucl. Soc., 39, 410 (1981).
   Google Scholar
• D. H. NYMAN, E. M. BENSON, J. M. YATABE and T. T. NAGAMOTO, “Remote Fabrication of Nuclear Fuel: A Secure Automated Fabrication Overview,” Trans. Am. Nucl. Soc., 39, 982 (1981).
   Google Scholar
• T. W. LATIMER, R. L. PETTY, J. F. KERRISK, N. S. DeMUTH, P. J. LEVINE and A. BOLTAX, “Irradiation Performance of Helium-Bonded Uranium-Plutonium Carbide Fuel Elements,” Proc. Int. Conf. Fast Breeder Reactor Fuel Performance, Monterey, California, March 5–8, 1979, p. 816.
   Google Scholar
• J. F. KERRISK, N. S. DeMUTH, R. L. PETTY, T. W. LATIMER, J. A. VITTI and L. J. JONES, “Design and Performance of Sodium-Bonded Uranium-Plutonium Carbide Fuels,” Proc. Int. Conf. Fast Breeder Reactor Fuel Performance, Monterey, California, March 5–8, 1979, p. 804.
   Google Scholar
• R. L. PETTY and T. W. LATIMER, “The Behavior of Sodium-Bonded Carbide Fuel Elements Irradiated to Goal Burnup,” Trans. Am. Nucl. Soc., 39, 418 (1981).
   Google Scholar
• U. P. NAYAK, P. J. LEVINE and A. BOLTAX, “Irradiation Behavior of Helium-Bonded Mixed-Carbide Fuel Pins,” Trans. Am. Nucl. Soc., 39, 412 (1981).
   Google Scholar
• R. L. PETTY and T. W. LATIMER, “The Behavior of Helium-Bonded Carbide Fuel Elements Irradiated to Goal Burnup,” Trans. Am. Nucl. Soc., 39, 413 (1981).
   Google Scholar
• T. W. LATIMER and R. L. PETTY, “The K6 Test: Helium-Bonded Uranium-Plutonium Carbide Fuel Pins Irradiated to 12 at.% Burnup in EBR-II,” LA-8688, Los Alamos National Laboratory (1981).
   Google Scholar
• T. W. LATIMER and G. R. HARRY, “Irradiation Performance of Uranium-Plutonium Carbide Fuel Pins in EBR-II,” Trans. Am. Nucl. Soc., 39, 411 (1981).
   Google Scholar
• R. W. STRATTON, “Development of Advanced Fuels in Switzerland,” Trans. Am. Nucl. Soc., 39, 421 (1981).
   Google Scholar
• J. F. KERRISK, “Experience Related to the Safety of Advanced LMFBR Fuel Elements,” LA-6028, Los Alamos National Laboratory (1975).
   Google Scholar
• H. C. TSAI, L. A. NEIMARK and D. L. JOHNSON, “Behavior of Advanced Carbide Fuel During Transient Overpower Operations,” Proc. Int. Conf. Fast Breeder Reactor Fuel Performance, Monterey, California, March 5-8, 1979, p. 853.
   Google Scholar
• L. A. NEIMARK, Compiler, “Advanced Fuels Development Program Quarterly Progress Report for the Period April-June, 1981,” ANL-AFP-105, p. 52, Argonne National Laboratory (1981).
   Google Scholar
• H. C. TSAI, S. M. GEHL and L. A. NEIMARK, “Transient Performance of Helium-Bonded Carbide Fuel Pins,” Trans. Am. Nucl. Soc., 39, 415 (1981).
   Google Scholar
• R. L. PETTY and T. W. LATIMER, “The Loss-of-Bond Test of Sodium-Bonded LMFBR (U, Pu)-Carbide Fuel Elements,” Proc. Int. Topl. Mtg. Reactor Safety Aspects of Fuel Behavior, Sun Valley, Idaho, August 2–6, 1981.
   Google Scholar
• H. K. FAUSKE, “Assessment of Accident Energetics in LMFBR Core-Disruptive Accidents,” Nucl. Eng. Design, 42, 19 (1977).
   Google Scholar
• J. J. BOARD and R. W. HALL, “Retardation of Fuel-Coolant Explosions,” Nature, 254, 319 (1975).
   Web of Science ®Google Scholar
• D. R. ARMSTRONG, G. T. GOLDFUSS and R. H. GEBNER, “Explosive Interaction of Molten UO2 and Liquid Sodium,” ANL-76-24, Argonne National Laboratory (1976).
   Google Scholar
• D. R. ARMSTRONG and L. BOVER, “Fuel Coolant Interactions,” U.S. Department of Energy Fast Reactor Safety Program Progress Report, April-June 1981, ANL/TMC81-3, p. 122, Argonne National Laboratory (1981).
   Google Scholar
• K. O. REIL and M. F. YOUNG, “Prompt Burst Energetics Experiment–Uranium Carbide Series,” Trans. Am. Nucl. Soc., 28, 487 (1978).
   Google Scholar
• T. P. HENRY, E. R. SIEGMANN and M. F. KENNEDY, “Analysis of In-Pile MFCI Experiments with Carbide Fuel,” Trans. Am. Nucl. Soc., 28, 452 (1978).
   Google Scholar
• H. JACOBS, M. F. YOUNG and K. O. REIL, “Fuel-Coolant Interaction-Phenomena Under Prompt Burst Condition,” Proc. Int. Mtg. Fast Reactor Safety Technology, Vol. Ill, Seattle, Washington, August 19–23, 1979.
   Google Scholar
• R. C. DOENER, T. H. BAUER, C. L. FINK, W. F. MURPHY and A. E. WRIGHT, “In-Pile Molten Fuel-Coolant Interaction Test of Carbide Fuel: TREAT Test AX1,” Nucl. Technol., 58, 465 (1982).
   Google Scholar