报告题目：核裂变和核聚变反应堆结构材料中气体行为的多尺度研究
报告时间：2016年5月9日 13:30
地点：校本部东区材料学院B楼520 会议室
报告人姓名：Xunxiang Hu, 胡逊祥
报告人单位：美国能源部橡树岭国家实验室
报告人简介：胡逊祥目前就职于美国能源部橡树岭国家实验室，职务为 Eugene P. Wigner Fellow。 2007年本科毕业于上海交通大学， 2009年在清华大学获得硕士学位， 2013年在加州大学伯克利分校获得博士学位，师从Brian D. Wirth教授。他的主要研究内容为材料的辐照损伤，聚变和裂变反应堆中结构材料中的气体行为研究。
报告内容简介：The behavior of gaseous foreign species (e.g, helium, tritium, and hydrogen) that are generated, adsorbed, or implanted within structural materials exposed to irradiation environments is a critical, yet largely unresolved, issue in nuclear materials science. The coexistence of gaseous foreign species and radiation damage is a major driver of a multitude of performance degradation mechanisms that limit the lifetime of structural materials in fusion and fission reactors. Extensive research has been performed on helium and hydrogen isotope effects on structural materials. However, the overall picture of gas behavior in nuclear materials still remains disconnected, incomplete, and far from self-consistent. In this seminar, a brief introduction of irradiation effects on structural materials used in nuclear energy will be given first. Microstructural evolution in single crystalline tungsten and iron following low dose and low temperature neutron irradiation will be presented along with the resulting mechanical property changes, which will help to reveal the relationship between microstructure and mechanical property by applying a coordinated modeling and experimental approach. Subsequently, two case studies, hydrogen permeation in FeCrAl alloys for accident-tolerant fuel cladding application in fission reactors and helium-point defect interaction in iron for fusion application, will be shown to demonstrate the importance of applying a coupled modeling and experiment research method to expanding the current understanding of gas behavior in structural materials. In the end, some ongoing research activities at Oak Ridge National Laboratory related to fusion materials research will briefly be introduced.
