A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design
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Douglas E. Burkes | M. K. Meyer | Randall Fielding | Douglas C. Crawford | Douglas L. Porter | M. Meyer | D. Burkes | R. Fielding | D. Crawford | D. Porter
[1] N. J. Olson,et al. Statistical and Metallurgical Analyses of Experimental Mark-IA Driver Fuel Element Cladding Failures in the Experimental Breeder Reactor II , 1976 .
[2] W. R. McDonell,et al. An X-RAY method for predicting anisotropic irradiation growth in Uranium , 1962 .
[3] D. C. Crawford,et al. Performance of U-Pu-Zr fuel cast into zirconium molds☆ , 1993 .
[4] G. D. Hudman,et al. Analysis of the leak-detection system for top welds of EBR-II fuel elements , 1973 .
[5] G. L. Hofman,et al. Irradiation Behavior of Experimental Mark-II Experimental Breeder Reactor II Driver Fuel , 1980 .
[6] Arthur D. Pelton,et al. Solidus and liquidus temperatures in the uranium-plutonium-zirconium system , 1988 .
[7] H. F. Jelinek,et al. EQUIPMENT FOR REMOTE INJECTION CASTING OF EBR-II FUEL , 1962 .
[8] C. H. Bachman,et al. Flow through Capillary Tubing with Eccentric Annular Sections , 1959 .
[9] B. R. Seidel,et al. In-reactor cladding breach of EBR-II driver-fuel elements , 1977 .
[10] L. C. Walters,et al. Status of LMR fuel development in the United States of America , 1993 .
[11] H. P. Planchon,et al. Loss-of-primary-flow-without-scram tests: Pretest predictions and preliminary results☆ , 1987 .
[12] A. P. Grunwald,et al. LEAK TESTING OF EBR-II FUEL RODS , 1962 .
[13] Douglas C. Crawford,et al. Fuels for sodium-cooled fast reactors , 2006 .
[14] L. C. Walters,et al. Development and Performance of Metal Fuel Elements for Fast Breeder Reactors , 1979 .
[15] Fh Huang. Fracture Toughness and Tensile Properties of Alloy HT9 in Thin Sections under High Neutron Fluences , 1992 .
[16] S. P. Henslee,et al. Sodium bond defect investigations , 1990 .
[17] M Haas,et al. Fabrication of driver-fuel elements for EBR-II , 1979 .
[18] Gerard L. Hofman,et al. Swelling behavior of U-Pu-Zr fuel , 1990 .
[19] A. L. Pitner,et al. Metal fuel test program in the FFTF , 1993 .
[20] J. J. Laidler,et al. Development of pyroprocessing technology , 1997 .
[21] E. S. Sowa,et al. DEVELOPMENT OF A PROCESS FOR SODIUM BONDING OF EBR-II FUEL AND BLANKET ELEMENTS , 1961 .
[22] G. Hofman,et al. Metallic Fast Reactor Fuels , 2006 .
[23] S. T. Zegler,et al. Transformation temperatures and structures in uranium-fissium alloys , 1959 .
[24] J. F. Koenig,et al. Experience with advanced driver fuels in EBR-II☆ , 1993 .
[25] Robert E. Einziger,et al. Irradiation performance of metallic driver fuel in Experimental Breeder Reactor II to high burnup , 1980 .
[26] Robert W. Cahn,et al. Materials science and technology : a comprehensive treatment , 2000 .
[27] B. R. Seidel,et al. Performance of metallic fuels and blankets in liquid-metal fast breeder reactors , 1984 .
[28] G. H. Golden,et al. U-Pu-Zr Metal Alloy: a Potential Fuel for LMFBR's , 1975 .
[29] Y. I. Chang. The Integral Fast Reactor , 1989 .
[30] Gerard L. Hofman,et al. Experimental studies of U-Pu-Zr fast reactor fuel pins in the experimental breeder reactor-ll , 1990 .
[31] J. H. Kittel,et al. PRELIMINARY ANALYSIS OF FISSION-INDUCED DIMENSIONAL CHANGES IN SINGLE CRYSTALS OF URANIUM , 1958 .
[32] J. P. Bacca,et al. Anisotropic irradiation growth of EBR-II driver fuel pins☆ , 1971 .
[33] L. C. Walters,et al. Irradiation behavior of metallic fast reactor fuels , 1992 .
[34] J. Kittel,et al. History of Fast-reactor Fuel Development , 1993 .
[35] Charles E. Stevenson. The Ebr-II Fuel Cycle Story , 1987 .