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Environmental effect of PWR primary water on fatigue life of stainless steel (influence of loading rate on fatigue life reduction)
Fatigue & Fracture of Engineering Materials & Structures ( IF 3.1 ) Pub Date : 2020-06-08 , DOI: 10.1111/ffe.13277
Masayuki Kamaya 1
Affiliation  

Fatigue tests on Type 316 stainless steel specimens were conducted for various combinations of rise time and strain range in simulated pressurized water reactor (PWR) water. It was demonstrated that crack growth rate estimated from test results correlated well with the strain intensity factor range. An equation for predicting Fen was obtained as a function of rise time and strain range. It was found that, although Fen depends on strain range, the magnitude of the change in Fen due to the strain range is negligibly small compared with the scatter in the test results.

中文翻译:

压水堆原水对不锈钢疲劳寿命的环境影响(负荷率对降低疲劳寿命的影响)

在模拟压水反应堆(PWR)水中对上升时间和应变范围的各种组合进行了316型不锈钢试样的疲劳试验。结果表明,根据测试结果估算的裂纹扩展速率与应变强度因子范围相关。获得了用于预测F en的方程,该方程是上升时间和应变范围的函数。已经发现,尽管F en取决于应变范围,但是与测试结果中的散布相比,由于应变范围引起的F en变化的幅度可以忽略不计。
更新日期:2020-06-08
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