首页> 外文会议>International conference on environmental degradation of materials in nuclear power systems-water reactors >Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment
【24h】

Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment

机译:低溶解氧环境下辐照316 SS的裂纹扩展行为

获取原文

摘要

Cracking susceptibility of austenitic stainless steels is known to be affected by dissolved oxygen (DO) or corrosion potential. In low-DO environments, crack growth rate (CGR) is significantly lower than that in high-DO environments. A strong dependence of CGR on corrosion potential has also been seen in irradiated stainless steels. While it has been shown that reducing the potential can reduce the CGRs of irradiated SSs, some high-dose specimens have shown elevated CGRs even in low potential environments. Thus, it is not clear how irradiation affects the dependence of CGR on corrosion potential. In the present study, a disk-shaped compact tension specimen of Type 316 SS was tested in low-DO environment. The specimen had been irradiated in the BOR-60 reactor to 5 dpa at 320°C. Post-irradiation CGR tests were performed in a low-DO environment. The effect of unloading on crack growth behavior in low-DO environment is discussed.
机译:已知奥氏体不锈钢的开裂敏感性受溶解氧(DO)或腐蚀电位的影响。在低DO环境中,裂纹扩展速率(CGR)明显低于高DO环境中的裂纹扩展速率。在辐照过的不锈钢中也发现了CGR对腐蚀潜能的强烈依赖性。虽然已经表明降低电势可以降低被辐照SS的CGR,但即使在低电势环境下,一些高剂量标本也显示出较高的CGR。因此,尚不清楚辐射如何影响CGR对腐蚀电位的依赖性。在本研究中,在低溶解氧环境中测试了316 SS型盘状紧凑拉伸试样。样品已在BOR-60反应器中于320°C辐照至5 dpa。辐照后CGR测试是在低DO环境下进行的。讨论了卸荷对低DO环境下裂纹扩展行为的影响。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号