论文信息 - Core materials development for the fuel cycle R&D program - 字舞流文

Core materials development for the fuel cycle R&D program

T. Byun | S. Maloy | M. Toloczko | J. Cole

[1] F. Garner,et al. Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443 °C , 2009 .

[2] Kenneth J. McClellan,et al. The effects of fast reactor irradiation conditions on the tensile properties of two ferritic/martensitic steels , 2006 .