Creep rupture assessment for Level-2 PSA of a 2-loop PWR: accounting for phenomenological uncertainties
creep rupture、pressurized water reactors、high pressure、nuclear power plant、failure probability、safety assessment、steam generator
28
TG4;TG
2017-08-30(万方平台首次上网日期,不代表论文的发表时间)
共9页
116-124