报告题目：压水堆高温核包壳材料：挑战与机遇
报告人：郑文跃，教授、博导
北京科技大学、国家材料服役安全中心
时间：2019年12月13日(星期五)下午2:30
地点：材料馆A323
报告人简介:
郑文跃，教授、博导。1979-1983北科大金属物理系；1984-88年英国曼彻斯特大学博士；1988年加拿大多伦多大学博士后；1990年加拿大魁北克省电研究院研究员；1993年至2017任加拿大自然资源部材料院能源材料总监及高级研究员；加拿大多个重大研发项目主席；研究领域：①石油、天然气高压管道材料腐蚀及断裂；②先进电站高温材料；③防腐涂料及表面工程技术及石油工程材料。获得NRCan部级奖二次，NRCan-能源部级奖，NRCan-MMS部门奖多次。著书4部，特刊1部，发表SCI及EI论文90余篇。
报告摘要:
Fission reactors are the main energy production form for nuclear energy. The in-core conditions of fission reactors, particularly those of advanced types, can be very severe for common alloys in terms of corrosion, stress corrosion cracking, creep and structural stability. Taking the operating conditions of pressure tube (PT)-supercritical water cooled reactor (SCWR) as an example, the core features of PT-SCWR conceptual design and related materials challenges are discussed in this talk.
Main results from 8 years of a SCWR materials R&D program in terms of alloy selection and assessment for fuel cladding will be presented in details. Opportunities for 1) new alloys and 2) new processing technologies in developing advanced fuels for Gen III (such as ATF fuels) and Gen IV water-cooled reactors will be outlined.
