主要技术内容
在本部分编写过程中，参考了金属所企业标准《Q/KJ.08.09—2017核电结构材料轻水堆环境疲劳设计模型》、《ASMEBoilerandPressureVesselCodeSectionIII-2004》、《NUREG/CR-6909,EffectofLWRcoolantenvironmentsonthefatiguelifeofreactormaterials》和《JNES-SS-1005,Environmentalfatigueevaluationmethodfornuclearpowerplants》关于核电结构材料平均曲线的拟合方法、设计曲线的建立方法以及环境疲劳设计模型的构件流程。结合中国科学院金属研究所积累的核电结构材料环境疲劳数据而制定。具体技术内容说明见表1。材料包括19MnNiMo反应堆压力容器低合金钢锻件，化学成分为：0.2C,1.41Mn,<0.005P,0.002S,0.16Si,0.78Ni,0.13Cr,0.49Mo,<0.002V,BalFe，热处理状态为供货状态。022Cr17Ni12Mo2N主管道奥氏体不锈钢锻件，第一种材料化学成分为：0.026C,0.36Si,1.41Mn,0.016P,0.004S,17.05Cr,12.45Ni,2.25Mo,0.02Co,0.0009B,0.072N,BalFe，第二种材料化学成分为：16.96Cr,13.07Ni,2.23Mo,0.014C,0.29Si,1.4Mn,0.003S,0.015P,0.12N,BalFe，热处理状态均为供货状态。022Cr19Ni10堆内构件奥氏体不锈钢锻件，材料化学成分为：0.029C,18.89Cr,9.65Ni,1.72Mn,0.38Si,0.23P,0.005S,BalFe，热处理状态为供货状态。NS3105蒸汽发生器传热管及管坯，第一种传热管化学成分为：59.3Ni,29.89Cr,9.2Fe,0.26Mn,0.018C,0.13Al,0.26Ti,0.029Cu,0.31Si,0.0067N，第二种传热管化学成分为：60.2Ni,29.47Cr,9.8Fe,0.018Mn,0.02C,0.11Al,0.14Ti,0.01Cu,0.04Si,0.01N，第三种传热管化学成分为：59.4Ni,29.47Cr,9.9Fe,0.079Mn,0.019C,0.12Al,0.27Ti,0.016Cu,0.2Si,0.028N，管坯化学成分为：57.7Ni,29.73Cr,10.5Fe,0.2Ti,0.2Al,0.001S,0.29Si,0.007P,0.29Mn,0.013N,0.03C。低合金钢高温高压水腐蚀疲劳数据点总计103个；奥氏体不锈钢高温高压水腐蚀疲劳数据点总计156个；镍基合金高温高压水腐蚀疲劳数据点总计87个。