论文摘要
<正>Zirconium alloy has small thermal neutron absorption cross section,good mechanical properties and thermal conductivity,so it is often used as structural materials in reactor core.Be-cause of its severe service conditions and important impact on the safety of the reactor,it is necessary to understand its high temperature mechanical properties in detail when developing anew zirconium alloy for reactor.
论文目录
文章来源
类型: 期刊论文
作者: YU Bintao,ZHAO Yingchao,GU Hongwei
来源: Annual Report of China Institute of Atomic Energy 2019年00期
年度: 2019
分类: 工程科技Ⅱ辑
专业: 核科学技术
单位: Division of Reactor Engineering Technology Research
分类号: TL341
页码: 129-130
总页数: 2
文件大小: 485K