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Examination of Cavity Formation in Cold-Worked Alloy 690

机译:690冷加工合金中空洞形成的检验

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Although stress corrosion cracking (SCC) has notbeen reported in Alloy 690 components after more than30 years of pressure water reactor (PWR) service,susceptibility to SCC growth in PWR primary water hasbeen reported by many labs for highly CW Alloy 690along with isolated observations of crack initiation. Posttestexaminations on SCC initiation specimens suggesteda key role of creep by inducing the formation and growthof grain boundary cavities at carbide interfaces leading tointergranular cracking. However, it is clear that highlevels of cold work can produce grain boundary voids andcomplicates the quantitative evaluation of damageevolution during testing in high-temperature water.Therefore, it is crucial to understand how to properlyexamine and classify this type of damage in the pre-testcondition and establish its evolution with time. Thispaper outlines our observational protocols on how to bestprepare sample surfaces to avoid inducing artifacts, andto perform subsequent examinations utilizing scanningelectron microscopy, transmission electron microscopyand focused ion beam milling to assess the formation anddevelopment of grain boundary cavities. Detailedexaminations will be reviewed on several commercialAlloy 690 heats in the pre-test CW condition and afterlong-term initiation testing at constant load in 360°Csimulated PWR primary water to effectively documentgrain boundary cavity formation and growth leading tocrack initiation.
机译:尽管应力腐蚀开裂(SCC)尚未 在超过690个合金后被报道 30年的压力水反应堆(PWR)服务, 压水堆原水对SCC生长的敏感性 许多实验室报道了高度连续的690合金 以及对裂纹萌生的孤立观察。后测 建议对SCC起始标本进行检查 通过诱导形成和生长而蠕变的关键作用 碳化物界面的晶界空洞导致 晶间开裂。但是,很明显 冷加工的水平会产生晶界空隙和 使损害的定量评估复杂化 在高温水中进行测试时会发生变化。 因此,了解如何正确操作至关重要 在预测试中检查并分类此类损坏 条件并确定其随时间的演变。这 论文概述了我们关于如何做到最好的观察方案 准备样品表面以避免引起伪影,以及 利用扫描进行后续检查 电子显微镜,透射电子显微镜 和聚焦离子束铣削以评估形成和 晶界空洞的发展。详细的 考试将在几个商业广告上进行审查 690合金在预测试连续波条件下和之后加热 在360°C恒定负载下进行长期启动测试 模拟压水堆一次水可有效记录 晶界腔的形成和生长导致 裂纹萌生。

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