核级低合金钢高温水腐蚀疲劳机制及环境疲劳设计模型

吴欣强, 谭季波, 徐松, 韩恩厚, 柯伟

CORROSION FATIGUE MECHANISM OF NUCLEAR-GRADE LOW ALLOY STEEL IN HIGH TEMPERATURE PRESSURIZED WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL

WU Xinqiang, TAN Jibo, XU Song, HAN En-Hou, KE Wei

表2 典型运行瞬态的总设计周次、40 a和60 a的周次 [31]

Table 2 Typical design basis cycles, anticipated cycles for 40 a and 60 a[31]

Transient Design basis cycle Anticipated cycle for 40 a Anticipated cycle for 60 a Heatup 500 90 135 Cooldown 500 90 135 Reactor trip 480 150 225 Loss of letdown 100 40 60 Loss of charging 100 12 18 Safety injection test 260 100 150 Leak test 260 115 173