Metallic fast reactor fuels

Barnes, 1958, Swelling and Inert Gas Diffusion in Irradiated Uranium Barnes, 1964, A Theory of Swelling and Gas Release for Reactor Materials, Journal of Nuclear Materials, 11, 135, 10.1016/0022-3115(64)90002-9 Batté, 1990, Run-Beyond-Cladding Breach (RBCB) Test Results for the Integral Fast Reactor (IFR) Metallic Fuels Program, 207 Bauer, 1992, Integral Fast Reactor Metallic Fuel Program in Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel, Transactions of the American Nuclear Society, 65, 278 Bauer, 1990, Behavior of Modern Metallic Fuel in TREAT Transient Power Tests, Nuclear Technology, 92, 325, 10.13182/NT92-325 Bauer, 1995, In-Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel, Nuclear Technology, 110, 407, 10.13182/NSE110-407 Beck, 1968, The Irradiation Behavior of High-Burnup Uranium-Plutonium Alloy Prototype Fuel Elements, Argonne National Laboratory Report ANL-7388 Beck, 1969, Fission Gas Release and Thermal Conductivity Measurements on U-5 Wt % Fs Irradiated in CP-5, Transactions of the American Nuclear Society, 12, 78 Bellamy, 1962, The Swelling of Alpha-Uranium under Neutron Irradiation with 0.7% Burn-up Betten, 1985, In-Core Measurements of Uranium - 5 wt.% Fissium Alloy Thermal Conductivity, Transactions of the American Nuclear Society, 50, 239 Blake, 1961, Achieving High Burn-up in Fast Reactors, Reactor Science and Technology, 14, 31 Campbell, 1969, Thermomigration and Electromigration in Zirconium, Physical Review, 179, 601, 10.1103/PhysRev.179.601 Chang, 1989, The Integral Fast Reactor, Nuclear Technology, 88, 129, 10.13182/NT88-129 Claudson, 1959 D'Amico, 1969, Electromigration and Thermomigration in Gamma Irradiation, Journal of Physics and Chemistry of Solids, 30, 1607, 10.1016/0022-3697(69)90269-8 DiNovi, 1972, Effect of Burnup, Swelling and Irradiation Temperature on Thermal Diffusivity and Conductivity of Uranium-Fissium Alloy, Argonne National Laboratory Report ANL-7889 DeVolpi, 1982, Fast-Neutron Hodoscope at TREAT: Methods for Quantitative Determination of Fuel Dispersal, Nuclear Technology, 56, 141, 10.13182/NT82-1 Enderby, 1956, Plastic Flow and Swelling of Gas Bubbles in Uranium, U.K. Atomic Energy Authority Report ICR-R/R.198 Frost, 1962, Research on the Fabrication, Properties, and Irradiation Behavior of Plutonium Fuels for the U.K. Reactor Programme, 4.1 Greenwood, 1962, The Effects of Neutron Irradiation on λ-Uranium and Some Fissile Alloys of Cubic Crystal Structure, Journal of Nuclear Materials, 6-1, 26, 10.1016/0022-3115(62)90213-1 Hehenkamp, 1977, 68 Hofman, 1980, Irradiation Behavior of Experimental Mark-II EBR-II Driver Fuel, Nuclear Technology, 47, 7, 10.13182/NT80-A32408 Hofman, 1986, Chemical Interaction of Metallic Fuel with Austenitic and Ferritic Stainless Steel Cladding, 12 Hofman, 1990, Swelling Behavior of U-Pu-Zr Fuel, Metallurgical Transactions A, 21A, 517, 10.1007/BF02671924 Horak, 1962, The Effects of Irradiation on Uranium-Plutonium-Fissium Fuel Alloys, Argonne National Laboratory Report ANL-6429 Kittel, 1949, Layer Formation by Interdiffusion Between Some Reactor Construction Metals, Argonne National Laboratory Report ANL-4937 Kobayashi, 1990, Development of the SESAMI Metallic Fuel Performance Code, Nuclear Technology, 89, 183, 10.13182/NT90-A34345 Kulcinski, 1969, Fission Gas Induced Swelling in Uranium at High Temperatures and Pressures, Journal of Nuclear Materials, 30, 3, 10.1016/0022-3115(69)90246-3 Lambert, 1990, EBR-II Test Programs, 181 Leggett, 1966, Swelling of Irradiated Fissionable Materials, Battelle Northwest Report BNWL-207 Leggett, 1967, Basic Swelling Studies, Radiation Effects, 303 Lehmann, 1968, Etude du Gonflenent d'Alliages d'Uranium Sous Irradiation, Journal of Nuclear Materials, 27, 285, 10.1016/0022-3115(68)90088-3 Makin, 1962, The Study of Irradiation Damage in Uranium by Electron Microscopy Merten, 1963, Thermal Migration of Hydrogen in Zirconium-Uranium-Hydrogen Alloys, Journal of Nuclear Materials, 10-3, 201, 10.1016/0022-3115(63)90055-2 Mikailoff, 1964, Quelques Aspects du Gonflement en Pile des Materieux Fissiles, 1601 Murphy, 1969, Post Irradiation Examination of U-Pu-Zr Fuel Elements Irradiated in EBR-II to 4.5 at % Burnup, Argonne National Laboratory Report ANL-7602 Mustelier, 1962, Quelques Resultes d'Irradiation Sur les Combustibles Evisages par Rapsodie, 163 O'Boyle, 1970, The Uranium-Plutonium-Zirconium Ternary Alloy System, 17 Pahl, 1990, Experimental Studies of U-Pu-Zr Fast Reactor Fuel Pins in EBR-II, Metallurgical Transactions A, 21A, 1863, 10.1007/BF02647233 Pahl, 1990, Steady-State Irradiation Testing of U-Pu-Zr Fuel to > 18 at% Burnup, 129 Porter, 1990, Fuel Constituent Redistribution During the Early Stages of U-Pu-Zr Irradiation, Metallurgical Transactions A, 21A, 1871, 10.1007/BF02647234 Pugh, 1961, Swelling in Alpha Uranium Due to Irradiation Rhodes, 1992, Fuel Motion in Over-Power Tests of Metallic Integral Fast Reactor Fuel, Nuclear Technology, 98, 91, 10.13182/NT92-A34653 Sackett, 1990, The Role of EBR-II and Treat in Establishing Liquid Metal Reactor Safety, 61 Seidel, 1977, In-Reactor Cladding Breach of EBR-II Driver Fuel Elements Seidel, 1986, Experience with EBR-II Driver Fuel, 2 Seidel, 1986, Off-Normal Performance of EBR-II Driver Fuel, 6 Shewmon, 1958, Vol. 212, 642 Till, 1988, The Integral Fast Reactor, Advances in Nuclear Science and Technology, 20, 127, 10.1007/978-1-4613-9925-4_3 Tracy, 1989, Improvements in the Fabrication of Metallic Fuels, Transactions of the American Nuclear Society, 60, 314 Tsai, 1990, Fuel/Cladding Compatibility in Irradiated Metallic Fuel Pins at Elevated Temperatures, 257 Tsai, 1991, Behavior of Low-Burnup Metallic Fuels for the Integral Fast Reactor at Elevated Temperatures in Ex-Reactor Tests, 1.18-1 Van Loo, 1984 Walter, 1973, EBR-II Driver Fuel Qualification and Performance, Nuclear Metallurgy, 19, 181 Walter, 1975, U-Pu-Zr Metal Alloy: A Potential Fuel for LMFBRs, Argonne National Laboratory Report ANL-76-28 Walters, 1984, Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors, Nuclear Technology, 65, 179, 10.13182/NT84-A33408 Zegler, 1967, Compatibility Between Metallic U-Pu-Base Fuels and Potential Cladding Materials, 13, 335