DEVELOPMENT OF A MECHANICAL PROPERTY DATABASE FOR GENERATION IV SUPERCRITICAL WATER REACTOR MATERIALS

摘要：

As a contribution to the development and selection of appropriate reactor materials for theGeneration IV Supercritical Water-Cooled Reactors (Gen IV SCWR), a mechanical propertydatabase is being developed, including nominal compositions, tensile properties, typicalmicrostructures, minimum creep rates, and times to rupture. The mechanical property database hasbeen developed with reference to ASME Section III Subsection NH code and the preliminary fuelcladding requirements in Canadian and Japanese conceptual SCWR designs. The materials reportedbase alloys, Ni-base alloys, and oxide dispersion strengthened (ODS) alloys. Traditionalcreep prediction models (i.e., Monkman-Grant model and Larson-Miller parameter) and the recentWilshire-Scharning model are assessed and applied to the creep database. The predicted averagemaximum allowable stresses at the conceptual design temperatures in the Canadian and the Japanesedesign are presented.

关键词： SCWR Gen IV mechanical properties creep prediction model Monkman-Grant model Larson-Miller parameter Wilshire-Scharning model

作者: P.Le Dreff-Kerwin S.Xu

作者单位: Department of Materials Science and Engineering,McMaster University 1280 Main St W,Hamilton,Ontario, CANMET-Materials Technology Laboratory Natural Resources Canada,183 Longwood Rd S,Hamilton,Ontario,C

会议类型: 国际会议

会议名称: 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors(第三届中国-加拿大超临界水堆研讨会 (CCSC-2012)

会议地点: 西安

会议语种:英文

页码: 1-15

在线出版日期: 2012-04-18（万方平台首次上网日期，不代表论文的发表时间）