The Defect Performance of UO₂-PuO₂ Thermal Reactor Fuel

References

• T. J. PASHOS, H. E. WILLIAMSON, and R. N. DUNCAN, “Fuel Performance in Boiling Water Reactors,” Nucl. Appl., 2, 510 (1966).
   Google Scholar
• G. J. WALKE, R. W. SINDERMAN, and C. E. AXTELL, “The Effects of Failed Fuel on the Operations of a Commerical BWR Plant,” Trans. Am. Nucl. Soc., 13, 165 (1970).
   Google Scholar
• F. W. KRAMER and J. B. ROLL, “Westinghouse Nuclear Fuel Experience,” Trans. Am. Nucl. Soc., 14, 563 (1971).
   Google Scholar
• D. R. McCLINTOCK, “Performance of Zircaloy Clad Fuel Rods in Saxton,” WCAP-3269-43, Westing-house Electric Corporation.
   Google Scholar
• J. PAWLIN, G. H. CHALDER, and R. T. POPPLE, “CANDU Fuel Performance in NPD,” Nucl. Appl., 2, 505 (1966).
   Google Scholar
• S. Y. OGAWA and M. F. LYONS, “Power Reactor High Performance UO2 Program—Final Report,” GEAP-10042, General Electric Company (1969).
   Google Scholar
• M. D. FRESHLEY, “Mixed-Oxide Fuel Irradiations in PRTR,” BNWL-SA-3981, Battelle Northwest Laboratory (1971).
   Google Scholar
• M. D. FRESHLEY and F. E. PANISKO, “The Irradiation Behavior of UO2-PuO2 Fuels in PRTR,” BNWL-366, Battelle Northwest Laboratory (1967).
   Google Scholar
• M. D. FRESHLEY, R. G. WHEELER, J. M. BATCH, and G. M. HESSON, “Investigation of the Combined Failure of a Pressure Tube and Defected Fuel Rod in PRTR,” BNWL-272, Battelle Northwest Laboratory (1966).
   Google Scholar
• Technical Report Series No. 59, “Thermal Conductivity of Uranium Dioxide,” International Atomic Energy Agency (1966).
   Google Scholar
• F. R. ZALOUDEK, Personal Communication, Battelle Northwest Laboratory.
   Google Scholar
• C. L. BENNETT and W. L. PURCELL, “BRT-I: Battelle-Revised-THERMOS,” BNWL-1434, Battelle Northwest Laboratory (1970).
   Google Scholar
• M. F. LYONS, R. F. BOYLE, J. H. DAVIES, V. E. HAZEL, and T. C. ROWLAND, “UO2 Properties Affecting Performance,” in Advanced Course on Limiting Aspects of Fuel Element Performance in Water Cooled Power Reactors, Netherlands-Norwegian Reactor School, Institutt for Atomenergi, Kjeller, Norway, August 1970. To be published in J. Nucl. Eng. Des.
   Google Scholar
• D. R. O’BOYLE, F. L. BROWN, and J. E. SANECKI, “Solid Fission Product Behavior in Uranimn-Plutonium Oxide Fuel Irradiated in a Fast Neutron Flux,” J. Nucl. Mater., 29, 27 (1969).
   Web of Science ®Google Scholar
• B. K. BARNES, D. M. HOLM, W. M. SANDERS, D. D. CLINTON, and J. E. SWANSEN, “Techniques for Two-Dimensional Gamma-Ray Scanning of Reactor Fuel Element Sections,” Nucl. Appl. Technol., 9, 746 (1970).
   Web of Science ®Google Scholar
• M. D. FRESHLEY, “Operation With Fuel Melting,” in Advanced Course on Limiting Aspects of Fuel Element Performance in Water Cooled Power Reactors, Netherlands-Norwegian Reactor School, Institutt for Atomenergi, Kjeller, Norway, August 1970. To be published in J. Nucl. Eng. Des.
   Google Scholar
• W. D. KINGERY, “Thermal Conductivity: XIV, Conductivity of Multicomponent Systems,” J. Am. Ceram. Soc., 42, 617 (1959).
   Web of Science ®Google Scholar
• A. M. ROSS, “The Dependence of Thermal Conductivity of Uranium Dioxide on Density, Microstructure, Stoichiometry, and Thermal Neutron Irradiation,” CRFO-817, Atomic Energy of Canada Limited (1960).
   Google Scholar
• J. A. CHRISTENSEN, “Stoichiometry Effects in Oxide Nuclear Fuels—1. Power Rating Required for Melting and Oxygen Redistribution in Molten Center UO2±xFuels,” BNWL-536, Battelle Northwest Laboratory (1967).
   Google Scholar
• U. RUNFORS, N. SCHONBERG, and R. KIESSLING, “The Sintering of UO2.” in Proc. U. N. Intern. Conf. Peaceful Uses At. Energy, Geneva, 2nd, 1958, 6, 605 (1958).
   Google Scholar
• R. G. WHEELER, “Thermal Contact Conductance of Fuel Element Materials,” HW-60343, General Electric Company (1959).
   Google Scholar
• B. E. SCHAVER, “Metallographic Determination of the UO2-U4O9 Phase Diagram,” J. Nucl. Mater., 2, 110 (1960).
   Web of Science ®Google Scholar
• J. D. EICHENBERG, P. W. FRANK, T. J. KISIEL, B. LUSTMAN, and K. H. VOGEL, “Effects of Irradiation on Bulk Uranium Dioxide,” in Fuel Element Conference, Paris, TID-7546, p. 616–617, U.S. Atomic Energy Commission (1958).
   Google Scholar
• R. C. ASHER and F. W. TROWSE, “The Distribution of Hydrogen in Zirconium Alloy Fuel Cladding: The Effects of Heat Flux,” J. Nucl. Mater., 35, 115 (1970).
   Web of Science ®Google Scholar
• D. W. SHANNON, “Role of Oxidation Rate on the Hydriding of Zirconium Alloys in Gas Atmospheres Containing Hydrogen,” Corrosion, 19, 12 (1963).
   Google Scholar
• R. P. MARSHALL, “Absorption of Gaseous Hydrogen by Zircaloy-2,” J. Less-Common Metal, 13, 45 (1967).
   Google Scholar
• C. CANDELA, C. F. CESARANO, and G. TREZZA, “Effects of Different Fission Products in the Beta-Gamma Autoradiography,” Nucl. Technol., 12, 324 (1971).
   Web of Science ®Google Scholar
• M. BOBER, C. SARI, and G. SCHUMACHER, “Plutonium Migration in a Thermal Gradient in Mixed (U,Pu) Oxide Fuels,” Trans. Am. Nucl. Soc., 12, 603 (1969).
   Google Scholar
• G. M. ALLISON and R. F. S. ROBERTSON, “The Behavior of Fission Products in Pressurized-Water Systems,” AECL-1338, Atomic Energy of Canada Limited (1961).
   Google Scholar
• R. LINDNER and H. J. MATZKE, “Diffusion of Xe-133 in Uranium Oxide of Different Oxygen Contents,” Z. Naturforsch., 14A, 582 (1959).
   Google Scholar
• D. R. McCLINTOCK, “Performance of Zircaloy-Clad Fuel Rods in Saxton,” WCAP-3269-43, Westing-house Electric Corporation (1966).
   Google Scholar
• A. J. MOORADLAN, G. M. ALLISON, and J. F. PALMER, “Chalk River Experience with Fuel Waterlogging,” Nucleonic, 18, 81 (1960).
   Google Scholar
• D. H. LOCKE, “Defected Zircaloy Fuel,” Nucl. Eng. Int., 14, 648 (1969).
   Web of Science ®Google Scholar
• D. H. LOCKE, “The Behavior of Defective Reactor Fuel,” in Advanced Course on Limiting Aspects of Fuel Element Performance in Water Cooled Power Reactors, Netherlands-Norwegian Reactor School, Institutt for Atomenergi, Kjeller, Norway, August 1970. To be published in J. Nucl. Eng. Des., 14, 648.
   Google Scholar