首页> 外文会议>American Nuclear Society;International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors >IASCC INITIATION TEST OF NEUTRON IRRADIATED TYPE 316L STAINLESS STEEL IN SIMULATED BWR CONDITION TO EVALUATE THRESHOLD STRESS
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IASCC INITIATION TEST OF NEUTRON IRRADIATED TYPE 316L STAINLESS STEEL IN SIMULATED BWR CONDITION TO EVALUATE THRESHOLD STRESS

机译:模拟中压水冷条件下中子辐照型316L不锈钢的IASCC初始测试

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Effect of stress on IASCC susceptibility was examinedwith Type 316L SS tube materials neutron irradiated up to1 × 10~(26) n/m2 (E>1 MeV). The constant load test insimulated BWR water was conducted at several stresslevels from 60 to 100% of the irradiated 0.2% proof stress.Under oxidizing conditions (32 ppm DO at the inlet),intergranular fracture was observed on the surface of Cringspecimens at relatively high stress levels. From thetest results, the IASCC threshold stress was estimated fromthe minimum initiation lifetime using an exponentialdistribution model. Based on these results, an apparentstress limit for IASCC of the test material was estimated atabout 80% of the irradiated 0.2% proof stress.
机译:检查了压力对IASCC敏感性的影响 用316L SS管材料中子辐照到 1×10〜(26)n / m2(E> 1 MeV)恒负载测试 模拟BWR水在几个应力下进行 辐照度为0.2%极限屈服应力的60%至100%。 在氧化条件下(入口处的DO为32 ppm), 在Cring表面观察到晶间断裂 标本处于相对较高的应力水平。来自 测试结果,IASCC阈值应力由 使用指数的最小启动寿命 分布模型。根据这些结果, 测试材料的IASCC的应力极限估计为 约有80%的0.2%屈服极限应力。

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