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首页|期刊导航|原子能科学技术|316 LN 在模拟压水堆一回路异常水化学条件下的应力腐蚀敏感性研究

316 LN 在模拟压水堆一回路异常水化学条件下的应力腐蚀敏感性研究

唐占梅 胡石林 张平柱

原子能科学技术Issue(11):1960-1964,5.
原子能科学技术Issue(11):1960-1964,5.DOI:10.7538/yzk.2014.48.11.1960

316 LN 在模拟压水堆一回路异常水化学条件下的应力腐蚀敏感性研究

Study on Stress Corrosion Cracking Susceptibility of 316LN in Simulated Primary Loop of PWR Under Abnormal Water Chemistry Conditions

唐占梅 1胡石林 1张平柱1

作者信息

  • 1. 中国原子能科学研究院特种材料工程部,北京 102413
  • 折叠

摘要

Abstract

It was studied that the effects of chloride ions and dissolved oxygen on stress corrosion cracking (SCC) behavior of 316LN stainless steel in simulated primary loop of pressure water reactor (PWR) under abnormal water chemistry conditions with slow strain rate test (SSRT ) method .The results show that in saturated oxygen condition , the extension of specimens decreases gradually while the SCC sensitive index increases with the increase of chloride ions concentration .In addition ,the samples will produce SCC in the case that the concentration of chloride ions is more than 1 mg/L .However , cracks are not initiated in de‐aerated solution even if the concentration of chloride ions increases to 10 mg/L .The stress corrosion cracks of 316LN are initiated in defects or Cr‐depleted zones at the surface and transgranularly propagates into the base metal .

关键词

慢应变速率拉伸试验法/应力腐蚀开裂/氯离子/溶解氧

Key words

SSRT method/SCC/chloride ion/dissolved oxygen

分类

矿业与冶金

引用本文复制引用

唐占梅,胡石林,张平柱..316 LN 在模拟压水堆一回路异常水化学条件下的应力腐蚀敏感性研究[J].原子能科学技术,2014,(11):1960-1964,5.

基金项目

大型先进压水堆核电站重大专项资助项目 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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