核用锻造态316L不锈钢在330 ℃碱溶液中应力腐蚀开裂行为研究

doi:10.11902/1005.4537.2014.073

中国腐蚀与防护学报

2015, Vol. 35

Issue (3): 205-212 DOI: 10.11902/1005.4537.2014.073

研究报告

本期目录 | 过刊浏览

核用锻造态316L不锈钢在330 ℃碱溶液中应力腐蚀开裂行为研究

张志明¹,彭青娇^1,²,王俭秋¹(

),韩恩厚¹,柯伟¹

2. 中联重工科技发展股份有限公司长沙 410007

Stress Corrosion Cracking Behavior of Forged 316L Stainless Steel Used for Nuclear Power Plants in Alkaline Solution at 330 ℃

Zhiming ZHANG¹,Qingjiao PENG^1,²,Jianqiu WANG¹(

),En-Hou HAN¹,Wei KE¹

1. Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research,Chinese Academy of Sciences, Shenyang 110016, China
2. Zoomlion Heavy Industry Science &Technology Development Co., Ltd., Changsha 410007, China

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摘要:

利用U弯样品研究了国产压水堆核电站主管道用锻造态316L不锈钢在330 ℃ NaOH溶液中的应力腐蚀开裂行为。结果表明,浸泡720 h后在样品表面观察到明显的应力腐蚀裂纹,裂纹扩展完全穿透样品厚度。样品表面生长的氧化膜内层富Fe,中间层富Ni,外层是富含Ni和Fe的分散的颗粒状氧化物,氧化膜缺乏保护性。EBSD和断口观察发现样品主要是沿晶型开裂,断口主要体现冰糖状花样,局部还分布有河流花样和准解理台阶。在应力的作用下,晶界富含Fe和Ni的氧化物的脆性断裂导致应力腐蚀裂纹的扩展。316L不锈钢的脆性断裂机制属于阳极溶解型-应力使晶界氧化膜破裂机制。

关键词 ： 316L不锈钢, 高温高压, NaOH, 应力腐蚀开裂

Abstract：

The stress corrosion cracking behavior of forged 316L stainless steel used for the main pipe of pressured water reactors was investigated in sodium hydroxide solution at 330 ^oC using U-bent samples. The results showed that, after immersion for 720 h, obvious stress corrosion cracks were found on the sample surfaces. The formed surface oxide film consisted of an inner layer rich in Fe, a middle layer rich in Ni and an outmost layer of oxide particles rich in Fe and Ni, which could not protect the base metal from further corrosion. EBSD and fracture morphology observation showed that the steel suffered mainly from intergranular cracking and the fractured surface exhibitedmainly rock candy-like patternwith partly river-like pattern and quasi-cleavage steps. The cracks were propagated by the brittle fracture of grain boundary oxides rich in Fe and Ni under the external stress. The stress corrosion cracking mechanism was ascribed to anodic dissolution-brittle fracture of grain boundary oxides by the applied stress.

Key words： 316L stainless steel high temperature and high pressure NaOH stress corrosion cracking

基金资助:国家重点基础研究发展计划项目 (2011CB610502),国家科技重大专项项目(2011ZX06004-002和2011ZX06004-009)和国家自然科学基金项目 (51301183) 资助

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引用本文:

张志明,彭青娇,王俭秋,韩恩厚,柯伟. 核用锻造态316L不锈钢在330 ℃碱溶液中应力腐蚀开裂行为研究[J]. 中国腐蚀与防护学报, 2015, 35(3): 205-212.
Zhiming ZHANG, Qingjiao PENG, Jianqiu WANG, En-Hou HAN, Wei KE. Stress Corrosion Cracking Behavior of Forged 316L Stainless Steel Used for Nuclear Power Plants in Alkaline Solution at 330 ℃. Journal of Chinese Society for Corrosion and protection, 2015, 35(3): 205-212.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2014.073 或 https://www.jcscp.org/CN/Y2015/V35/I3/205

图1 316L不锈钢主管道及U弯样品取样位置示意图

图2 316L不锈钢3个方向金相组织

图3 应力腐蚀实验U型弯曲试样尺寸

图4 316L不锈钢U型弯曲样品浸泡后表面形貌的SEM像

图5 316L不锈钢U弯样品表面氧化膜截面形貌及化学组成分析

图6 316L不锈钢U型弯曲样品浸泡后截面的裂纹形貌

图7 316L不锈钢U型弯曲样品裂纹与晶界分析

图8 在高温碱性溶液浸泡后316L不锈钢U型弯曲样品断口形貌观察

图9 316L不锈钢U型弯曲样品裂纹路径腐蚀产物分析

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