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作 者:梅金娜[1] 韩姚磊 彭群家 蔡振 王鹏 遆文新[1] Mei Jinna;Han Yaolei;Peng Qunjia;Cai Zhen;Wang Peng;Ti Wenxin(Suzhou Nuclear Power Research Institute,Suzhou 215004,China)
机构地区:[1]苏州热工研究院有限公司,江苏苏州215004
出 处:《稀有金属材料与工程》2022年第10期3547-3553,共7页Rare Metal Materials and Engineering
基 金:Natural Science Foundation of Jiangsu Province(BK2018117,BK20180210);Scientific Research and Innovation Project of China General Nuclear Power Group(3100129119);National Science and Technology Major Project of China(2019ZX06005003)。
摘 要:传热管是蒸汽发生器(SG)最关键的部件,起到一、二回路换热的作用,是防止放射性泄漏的重要安全屏障。在高温碱性溶液中进行了磨损690合金传热管的慢应变速率拉伸试验(SSRT)。采用扫描电子显微镜、电子背散射衍射和透射电子显微镜分析了690合金传热管的微动磨损和应力腐蚀裂纹(SCC)萌生行为。结果表明,SSRT试样呈现出典型的穿晶SCC特征,且随磨损深度增加,裂纹萌生数量和平均深度均增加,这可能与磨损表面留下的犁沟、剥层、微裂纹以及数十微米厚的残余应变层有关。基于SCC的滑移溶解/氧化机制,对磨损促进SCC裂纹萌生的过程进行了分析。Tube bundles are the most critical components of steam generators in pressurized water plants.They are the heat exchange interface between primary and secondary circuits,acting as an important safety barrier to prevent the radioactive leakage.Stress corrosion cracking(SCC)initiation behavior of the worn alloy 690 tubes was investigated by slow strain rate tests(SSRT)in the hightemperature alkaline solution.The scanning electron microscope,electron backscatter diffraction and transmission electron microscope were used to analyze the fretting wear and SCC initiation behavior of alloy 690 tubes.Results show that SSRT specimens show typical transgranular SCC characteristics.The number of initiated cracks and their average depth are increased with increase in the wear degree,suggesting a wear-induced SCC initiation.This may have a relationship with the grooves,delamination,micro-cracks and residual strain layer with tens of micrometers in thickness left on the worn surface.Furthermore,a preliminary analysis on the possible procedure of wear-induced SCC initiation and further propagation during SSRT tests was carried out based on slipdissolution/oxidation mechanism.
关 键 词:镍基690合金 高温碱性溶液 磨损 应力腐蚀开裂
分 类 号:TG174.3[金属学及工艺—金属表面处理] TM623[金属学及工艺—金属学]
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