Assessment of Creep in Reactor-Irradiated CuCrZr Alloy Intended for the ITER First Wall Panels
Fusion Engineering and Design(2018)
关键词
ITER,CuCrZr alloy,Tensile strength,Creep relaxation,Reactor irradiation
AI 理解论文
溯源树
样例

生成溯源树,研究论文发展脉络
Chat Paper
正在生成论文摘要