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采用高温高压水慢应变速率拉伸测试(SSRT)及断口形貌观察研究了pH值和辐照对国产核反应堆堆内构件用不锈钢的应力腐蚀开裂(SCC)行为的影响。结果表明,不锈钢的SCC敏感性在pH值为7.0溶液中较小,在pH值为6.4与7.5水溶液条件下SCC敏感性显著增加。带电粒子辐照后出现辐照加速SCC(IASCC)现象,主要是由于辐照缺陷与局域形变对裂纹起裂的影响导致的,但由于离子辐照损伤深度的限制,不能从SSRT试样断口形貌观察到离子辐照对SCC的影响。
The effects of pH value and irradiation on the stress corrosion cracking (SCC) behavior of stainless steel used in the domestic nuclear reactors were studied by using the test of high temperature and high pressure water slow strain rate (SSRT) and fracture morphology. The results showed that the SCC sensitivity of stainless steel was smaller in the solution of pH 7.0, and the sensitivity of SCC increased significantly under the condition of pH 6.4 and 7.5. The accelerated accelerated SCC (IASCC) phenomenon after charged particle irradiation is mainly due to the influence of irradiation defects and local deformation on crack initiation. However, due to the limitation of ion irradiation damage depth, it can not be detected from the SSRT specimen fracture The effect of ionizing irradiation on SCC was observed.