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3 某压水堆进水管嘴的疲劳延寿评估[31]

Table 3 Life extension of a pressurized water reactor inlet nozzle[31]

Load pair Salt Nenv 40 a 60 a N40 U40 N60 U60 Cooldown/plant load 416.6 1458 90 0.062 135 0.093 Leak test/plant unload 330.8 1534 200 0.130 300 0.196 Heatup/plant load 270.4 4263 90 0.021 135 0.032 Plant load/unload 143.6 58406 14620 0.250 21930 0.375 Plant unload/upset 136.6 73899 480 0.007 720 0.010 Plant undload/OBE 98.7 265677 200 0.001 300 0.001 Plant unload/step load 87.6 729360 520 0.001 780 0.001 Total 0.472 Total 0.708