S.S. KangDepartment of Nuclear Engineering Korea Advanced Institute of Science and Technology关注立即认领分享关注立即认领分享基本信息浏览量:0职业迁徙个人简介暂无内容研究兴趣论文共 3 篇作者统计合作学者相似作者按年份排序按引用量排序主题筛选期刊级别筛选合作者筛选合作机构筛选时间引用量主题期刊级别合作者合作机构Estimation of fracture toughness transition curves of RPV steels from Charpy impact test dataS.H Kim,Y.W Park,S.S Kang, H.D ChungNuclear Engineering and Design(2002)引用21浏览0EI引用210Dynamic strain aging in SA508-class 3 pressure vessel steelI.S. Kim,S.S. KangInternational Journal of Pressure Vessels and Piping(1995)引用56浏览0EI引用560Temperature And Loading Rate Dependence Of Deformation And Fracture Characteristics Of The Sa508 Pressure-Vessel Steel In The Upper Shelf RegionIs Kim,Ss KangPROCEEDINGS OF THE SIXTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS (1993)引用0浏览0引用00作者统计合作学者合作机构D-Core合作者学生导师暂无相似学者,你可以通过学者研究领域进行搜索筛选数据免责声明页面数据均来自互联网公开来源、合作出版商和通过AI技术自动分析结果,我们不对页面数据的有效性、准确性、正确性、可靠性、完整性和及时性做出任何承诺和保证。若有疑问,可以通过电子邮件方式联系我们:report@aminer.cn