核级低合金钢高温水腐蚀疲劳机制及环境疲劳设计模型  

CORROSION FATIGUE MECHANISM OF NUCLEARGRADE LOW ALLOY STEEL IN HIGH TEMPERATURE PRESSURIZED WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL

作　　者：吴欣强[1,2] 谭季波[1,2] 徐松[1,2] 韩恩厚[1,2] 柯伟[1,2] 

机构地区：[1]中国科学院金属研究所核用材料与安全评价重点实验室,沈阳110016 [2]中国科学院金属研究所辽宁省核电材料安全与评价技术重点实验室,沈阳110819

出　　处：《金属学报》2015年第3期298-306,共9页Acta Metallurgica Sinica

基　　金：国家重点基础研究发展计划项目2011CB610506;国家科技重大专项项目2011ZX06004-009资助~~

摘　　要：通过模拟核电高温高压循环水腐蚀疲劳实验,研究了核级低合金钢环境疲劳损伤规律与控制机理,构建了一个植入环境效应的疲劳设计模型,给出了便于工程应用的环境疲劳设计曲线,并建立了核电站实际构件的环境疲劳安全评估流程,给出了尝试实施例.The service degradation and life assessment of key components in light water reactor nuclear power plants（NPPs） mainly depend on the accumulation of service property data of component materials, understanding of environmental degradation mechanism, and construction of evaluation models or methods. The current ASME design fatigue code does not take full account of the interactions of environmental, loading and material’s factors. In the present work, based on the corrosion fatigue tests in simulated NPPs’ high temperature pressurized water, the environmental fatigue behavior and dominant mechanism of nuclear-grade low alloy steel have been investigated. A design fatigue model was constructed by taking environmentally assisted fatigue effects into account and the corresponding design curves were given for the convenience of engineering applications. The process for environmental fatigue safety assessment of NPPs’ components was proposed, based on which some tentative assessment cases have been given.

关 键 词：核级低合金钢 高温高压水 腐蚀疲劳 设计模型 环境疲劳安全评估 

分 类 号：TG172[金属学及工艺—金属表面处理]