作者: J. J. Sienicki , A. Moisseytsev , W. S. Yang , D. C. Wade , A. Nikiforova
DOI: 10.2172/932940
关键词: Neutron transport 、 Brayton cycle 、 Lead-cooled fast reactor 、 Load following power plant 、 Coolant 、 Nuclear reactor core 、 Control rod 、 Engineering 、 Nuclear engineering 、 Natural circulation 、 Mechanical engineering
摘要: … Another section of the report details the SSTAR safety design approach … of the plant or which was not forseen at the time that the plant was designed and constructed. The inherent safety …