Fuel Pin and Assembly Design
暂无分享,去创建一个
[1] R. W. Weeks,et al. LIFE-II: A COMPUTER ANALYSIS OF FAST-REACTOR FUEL-ELEMENT BEHAVIOR AS A FUNCTION OF REACTOR OPERATING HISTORY. , 1972 .
[2] W. H. Sutherland,et al. AXICRP — Finite element computer code for creep analysis of plane stress, plane strain and axisymmetric bodies , 1970 .
[3] R. A. Markley,et al. Thermal analysis of liquid--metal fast breeder reactors , 1978 .
[4] A. Mendelson. Plasticity: Theory and Application , 1968 .
[5] S. A. Chastain,et al. Modeling of the fuel cladding postirradiation gap in mixed-oxide fuel pins , 1973 .
[6] J. Straalsund,et al. A new approach to stress-rupture data correlation , 1977 .
[7] Peter L. Balise,et al. Elements of Materials Science , 1959 .
[8] D. Mohr,et al. BOW-V: A CDC-3600 PROGRAM TO CALCULATE THE EQUILIBRIUM CONFIGURATIONS OF A THERMALLY BOWED REACTOR CORE. EBR-II Project. , 1970 .
[9] Joseph Edward Shigley,et al. Mechanical engineering design , 1972 .
[10] Donald R. Olander,et al. Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .
[11] J. Bates,et al. Dependence of irradiation creep on temperature and atom displacements in 20% cold worked type 316 stainless steel , 1977 .
[12] F. L. Brown,et al. Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron flux , 1969 .
[13] E. R. Gilbert,et al. Creep Deformation of 20 Percent Cold Worked Type 316 Stainless Steel , 1977 .
[14] Donald R. Olander,et al. Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .