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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 |
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Stress Corrosion Cracking Behavior of Forged 316L Stainless Steel Used for Nuclear Power Plants in Alkaline Solution at 330 ℃ |
Zhiming ZHANG1,Qingjiao PENG1,2,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 |
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
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