MATERIALS RESEARCH IN SUPPORT OF SCWR EVELOPMENT: CURRENT AREAS, GAPS AND NEEDS
International efforts on materials selection and development related to supercritical water-cooled reactors (SCWRs) have produced a considerable amount of data in the open literature 1. The majority of these data are on aspects of materials properties such as corrosion, stress corrosion cracking, creep, irradiation damage as well as microstrucrural degradation under various exposure conditions. These prior efforts are helping guide the current selection of candidate alloys for further, longer-term evaluation. As continuing research on the SCWR advances, gaps and limitations in the published data are being identified. In terms of corrosion properties, these gaps can be seen in several areas, including: 1) the test environment, 2) the physical and chemical severity of the tests conducted as compared with likely reactor service/operating condition, and 3) test methods used. While some of these gaps can be filled readily by the current research projects, in particular those occurring in Generation IV International Forum (GIF) member countries, others require further advances in our understanding of material-environment interactions involving supercritical water. Gaps in advanced test facilities for future research are also becoming evident. Future needs for materials development and suggestions for expanded international collaborations to link with groups working on materials for advanced fossil-fired supercritical water power plants, as well as other GEN IV and fusion reactor designs are summarized.
Wenyue Zheng Dave Guzonas D.Brady W.Cook J.Luo
NRCan-MTL Ottawa, Ontario, Canada Atomic Energy of Canada Limited, Chalk River Laboratories, Ontario, Canada NRCan-OERD Ottawa, Ontario, Canada University of New Brunswick Fredericton, New Brunswick,Canada University of Alberta Edmonton, Alberta, Canada
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-7
2010-05-17（万方平台首次上网日期，不代表论文的发表时间）