...
首页> 外文期刊>Nuclear Engineering and Design >Evaluation method of corrosion lifetime of conventional stainless steel canister under oceanic air environment
【24h】

Evaluation method of corrosion lifetime of conventional stainless steel canister under oceanic air environment

机译:海洋环境下常规不锈钢罐腐蚀寿命的评估方法

获取原文
获取原文并翻译 | 示例
   

获取外文期刊封面封底 >>

       

摘要

Natural exposure and accelerated corrosion tests of conventional stainless steels for canisters of Types 304, 304L, and 316(LN) for concrete casks were conducted using several test specimens and 1/5 scale canister models. The welding residual stress of a full-scale model canister was also measured and the lifetime of sealability of canisters against corrosion evaluated. The maximum pitting rate and crevice corrosion rate of Type 304 were approximately 20 and 30 μm/year. Many SCC in the 4 Point Bending (4PB) test specimens were found to initiate from the bottom of the corrosion area by pitting or crevice corrosion. The SCC propagation rates in Types 304 and 304L under natural conditions were around 1.2E-12 to 1.8E-11 m/s in the K (Stress Intensity Factor) range of 0.6-9.0 MPa m~(1/2), and that of the accelerated test (60℃, 95% RHS, filled with NaCl mist) around 1.0E-10 to 3.5E-9 m/s in the K range of 0.5-30 MPa m~(1/2). The SCC propagation rates under both natural and accelerated conditions were independent of K. The lifetime of sealability estimated from 1/5 scale models was longer than that from the small bending test specimens and has a safety margin as a structure.
机译:使用多个测试样本和1/5比例的罐模型,对用于混凝土桶的304、304L和316(LN)型罐的常规不锈钢进行了自然暴露和加速腐蚀测试。还测量了全尺寸模型罐的焊接残余应力,并评估了罐对腐蚀的密封性寿命。 304型的最大点蚀率和缝隙腐蚀率约为20和30μm/年。发现四点弯曲(4PB)测试样品中的许多SCC通过点蚀或缝隙腐蚀从腐蚀区域的底部开始。 304和304L型在自然条件下的SCC传播速率在0.6-9.0 MPa m〜(1/2)的K(应力强度因子)范围内约为1.2E-12至1.8E-11 m / s,并且在0.5-30 MPa m〜(1/2)的K范围内,加速试验(60℃,95%RHS,充满NaCl雾)的速度约为1.0E-10至3.5E-9 m / s。在自然和加速条件下,SCC的传播速率均与K无关。根据1/5比例模型估算的密封性寿命比根据小弯曲试样的寿命更长,并且在结构上具有安全余量。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2008年第5期|p.1233-1240|共8页
  • 作者

    Akio Kosaki;

  • 作者单位

    Nuclear Fuel Cycle Backend Research Center, Civil Engineering Research Laboratory, Central Research Institute of Electric Power Industry, 1646 Abiko, Abiko-shi, Chiba-ken 270-1194, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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