| 核电工程材料的应力腐蚀破裂研究 |
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| 引用本文： | 杨武. 核电工程材料的应力腐蚀破裂研究[J]. 腐蚀科学与防护技术, 1995, 7(2): 87-92 |
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| 作者姓名： | 杨武 |
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| 作者单位： | 机械工业部上海材料研究所 |
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| 摘 要： | 采用慢应变速率试验(SSRT)和U型弯曲试验技术研究了水中杂质离子、溶解氧(DO)、外加电位以及温度等对核电工程材料304不锈钢(SS)、316SS以及A533B压力容器用钢在高温水中应力腐蚀破裂(SCC)的影响,并结合电化学测试和表面膜分析结果进行了讨论,还根据304SS的U型弯曲和SSRT结果的差异提出了SCC加速试验的选择原则建议。
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| 关 键 词： | 核电工程材料 应力腐蚀破裂 高温水 慢应变速率试验 U型弯曲试验 表面膜 |
| 收稿时间： | 1995-03-25 |
| 修稿时间： | 1995-03-25 |
STRESS CORROSION CRACKING OF ENGINEERING MATERIALS USED IN NUCLEAR POWER PLANTS |
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| YANG Wu. STRESS CORROSION CRACKING OF ENGINEERING MATERIALS USED IN NUCLEAR POWER PLANTS[J]. Corrosion Science and Protection Technology, 1995, 7(2): 87-92 |
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| Authors: | YANG Wu |
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| Abstract: | The effects of impurity ions, dissolved oxygen, applied potential and temperature onstress corrosion cracking (SCC) of engineering materials used in nuclear power plants, including304 stainless steel (SS), 316 SS and A533B pressure vessel steel, in high temperature water havebeen investigated using slow strain rate testing (SSRT) and U--bend testing techniques, comple'mented by electrochemical measurements and Auger electron spectroscopy (AES) analyses of thesurface films formed on specimens. A suggestion for choosing the accelerating testing methods isproposed based on the comparison of the results of SSRT and U--bends. This paper briefly introduces some most important results. |
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| Keywords: | engineering materials nuclear power plant stress corrosion cracking high temperature water slow strain rate test U--bend surface film |
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