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1 某沸水堆碳钢给水管的安全端疲劳损伤评价 [29~31]

Table 1 Fatigue damage evaluation for safe end of a boiling water reactor feedwater pipe[29~31]

Salt / MPa T / ℃ ε ˙ / %s-1 Design cycle / cyc NASME Uair Nenv Uenv 567.2 200 0.028 120 1024 0.1172 92 1.304 500.6 0.026 1429 0.0630 142 0.634 444.1 200 0.026 142 1967 0.0722 231 0.615 268.8 200 0.002 555 9272 0.0599 2191 0.253 201.9 200 0.001 10 23830 0.0004 7149 1.40×10-3 143.8 200 0.001 120 81350 0.0015 88833 1.35×10-3 132.4 200 0.001 98 115630 0.0008 231742 4.23×10-4 121.1 200 0.001 10 159810 0.0001 703538 1.42×10-5 120.2 288 0.001 10 163810 0.0001 777252 1.29×10-5 95.5 288 0.001 222 444850 0.0005 1000000 2.22×10-4 92.6 200 0.001 666 523970 0.0013 1000000 6.66×10-4 91.9 288 0.001 120 560450 0.0002 1000000 1.20×10-4 Total 0.317 Total 2.81