| 304L不锈钢在核电一回路水中应力腐蚀行为的研究 |
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| 引用本文： | 关矞心,董超芳,李岩,程学群,刘飞华,李晓刚,任爱.304L不锈钢在核电一回路水中应力腐蚀行为的研究[J].科技导报(北京),2011,29(21):17-21. |
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| 作者姓名： | 关矞心 董超芳 李岩 程学群 刘飞华 李晓刚 任爱 |
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| 作者单位： | 1. 苏州热工研究院寿命评估中心,江苏苏州 215004;2. 北京科技大学腐蚀与防护中心,北京 100083 |
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| 基金项目： | 国家自然科学基金项目(50871020) |
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| 摘 要： | 在模拟核电一回路高温高压水环境中,采用慢应变速率拉伸试验方法,研究温度对304L不锈钢应力腐蚀开裂的影响规律。通过扫描电镜观察,对试样断口形貌进行分析。结果表明,在高压水环境中,随着温度的升高,材料有向脆性断裂转变的倾向,抗拉强度等参数变化不大,延伸率和断面收缩率略有降低;在研究温度范围内,304L不锈钢试样断口未发现明显脆性解理特征;温度处于200-345℃区间时,没有发现存在304L不锈钢敏感温度,材料应力腐蚀敏感性较低。
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| 关 键 词： | 304L不锈钢 应力腐蚀开裂 核电 高温水 |
Stress Corrosion Cracking of 304L Stainless Steel in a Simulated PWR Environment |
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| GUAN Yuxin ,DONG Chaofang ,LI Yan ,CHENG Xuequn ,LIU Feihua ,LI Xiaogang ,REN Ai .Life Assessment Center,Suzhou Nuclear Power Research Institute,Suzhou ,Jiangsu Province,China .Corrosion , Protection Center,University of Science , Technology Beijing,Beijing ,China.Stress Corrosion Cracking of 304L Stainless Steel in a Simulated PWR Environment[J].Science & Technology Review,2011,29(21):17-21. |
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| Authors: | GUAN Yuxin DONG Chaofang LI Yan CHENG Xuequn LIU Feihua LI Xiaogang REN Ai Life Assessment Center Suzhou Nuclear Power Research Institute Suzhou Jiangsu Province China Corrosion Protection Center University of Science Technology Beijing Beijing China |
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| Institution: | 1. Life Assessment Center, Suzhou Nuclear Power Research Institute, Suzhou 215004, Jiangsu Province, China;2. Corrosion and Protection Center, University of Science and Technology Beijing, Beijing 100083, China |
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| Abstract: | In a simulated primary circuit of PWR environment,the effect of temperature on Stress Corrosion Cracking(SCC) of 304L stainless steel in high-temperature and high-pressure water was investigated using Slow Strain Rate Tests(SSRT).And the fracture morphology of specimens was analyzed with the aid of Scanning Electron Microscopy(SEM).The results show that 304L stainless steel tends towards a brittle fracture as temperature increasing.Certain parameters,such as tensile strength,almost remain unchanged,while bo... |
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| Keywords: | 304L stainless steel stress corrosion cracking nuclear power high temperature water |
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