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SCC INITIATION OF CW ALLOY TT690 AND ALLOY 600 IN PWR WATER

机译:压水水中CW TT690和600合金的SCC起始

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The purpose of this work is to understand quantitative processes which underlie the initiation of stress corrosion after long term exposures in high temperature water. Long term stress corrosion cracking (SCC) initiation tests up to about 30,000 h were performed using blunt notch compact tension (CT) type specimens and CT specimens with a shallow depth of pre-crack (~0.1 mm) of cold worked (CW) thermally treated alloy 690 (UNS N06690, TT 690), which were exposed in the primary coolant environment in pressurized water reactors (PWR) under static load condition at 320 and 360°C. Further, SCC initiation tests were also performed using blunt notch CT specimens of CW mill annealed Alloy 600 (UNS N06600, MA600) to consider the similarities and dissimilarities with Alloy TT690. Three important patterns were observed: first, intergranular (IG) cracking was observed in 20%CW TT690 from the shallow pre-crack at 360°C in PWR primary water after 20,653 h under static load conditions. Second, clear evidence of cavities were identified in 20%CW TT690 ahead of SCC tip at 360°C in PWR primary water after 20,653 h. The cavities seem to result from the condensation of vacancies and affected the bond strength of grain boundaries. Consequently, the bond strength is assumed to be weakened during the incubation period. Third, SCC initiated in 20%CW MA600 at 360°C in PWR primary water after 1,522 h. The results suggested that the transition of SCC segments from initiation and steady growth seem to be occurred about 0.2 to 0.3 mm depth of intergranular cracking at high stress condition at 360°C in PWR water. As a model for the initiation of SCC after long term operations of CW TT690 in high temperature water, the combination of local corrosion and the formation of cavities from the collapse of vacancies seem to dominate the initiation of SCC after long times in high temperature water.
机译:这项工作的目的是了解定量过程,这些过程是长期暴露于高温水中后引发应力腐蚀的基础。使用钝刻痕紧凑张力(CT)型试样和热加工冷裂(CW)前裂纹深度浅(〜0.1 mm)的CT试样,进行了长达约30,000小时的长期应力腐蚀开裂(SCC)初始测试。经处理的690合金(UNS N06690,TT 690),它们在320和360°C的静态载荷条件下暴露于压水反应堆(PWR)的主冷却剂环境中。此外,还使用CW轧制退火合金600(UNS N06600,MA600)的钝口CT样品进行了SCC初始测试,以考虑与TT690合金的相似性和不相似性。观察到三个重要的模式:首先,在静载荷条件下20653小时后,在20°CW TT690中,在360°C的PWR初级水中,从浅预裂缝观察到了晶间(IG)开裂。其次,在20,653小时后,在压水堆初级水中360°C的SCC尖端之前,在20%CW TT690中发现了明显的空洞证据。空洞似乎是由于空位的凝结而产生的,并且影响了晶界的结合强度。因此,认为在孵育期间粘合强度减弱。第三,在1522小时后,在PWR一级水中于360°C的20%CW MA600中引发SCC。结果表明,在压水堆中,在高应力条件下(360°C),SCC片段从初始生长和稳定生长的转变似乎发生在0.2至0.3 mm的晶间裂纹深度处。作为高温水中CW TT690长期运行后引发SCC的模型,长期腐蚀在高温水中SCC的引发似乎是局部腐蚀和空位坍塌形成空腔的组合。

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