Materials Selection for Supercritical Water Cooled Reactors
Supercritical water cooled reactor (SCWR) is a promising Gen IV concept reactor which can be developed to build large capacity electric power generation plants in the future. The presently well recognized conceptual design of SCWR can promote thermal and nuclear fuel utilization efficiency up to 45％ and 10％, respectively. Compounding its high performance, selection or development of materials for core structures, such as fuel cladding, grid, water rod and core shroud, remains one of the key issues facing the engineering practice of a demo SCWR. For a prototype design with outlet temperature of 510℃, the hot spot temperature on fuel cladding exceeds 600℃ at normal operation conditions, and will be much higher during transients. Selection of fuel cladding material is one of the most urgent issues, while candidate materials for other components are readily available. This paper discusses the technical requirements of the cladding materials and reviews the research works that have been done.
Supercritical water-cooled reactor materials selection fuel cladding corrosion oxide film
Lefu ZHANG Yichen BAO Rui TANG
School of Nuclear Science and Engineering, Shanghai Jiao Tong University No. 800 Dongchuan Road, Sha National Key Laboratory for Nuclear Fuel and Materials, Nuclear Power Institute of China P.O.Box 436
国际会议
上海
英文
2767-2780
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）