预形变及模拟压水堆一回路水中预浸泡对690合金拉伸性能的影响

腐蚀与防护, 2015, 36(2): 170-176.

预形变及模拟压水堆一回路水中预浸泡对690合金拉伸性能的影响

夏小峰 ^1, , 吕战鹏 ^2, , 陈俊劼 ^3, , 肖茜 ^4, , 茹祥坤 ^5, , 周邦新 ^6, , 熊茹 ^7,

1.上海大学材料科学与工程学院材料研究所,上海,200072

2.上海大学材料科学与工程学院材料研究所,上海,200072

3.上海大学材料科学与工程学院材料研究所,上海,200072

4.上海大学材料科学与工程学院材料研究所,上海,200072

5.上海大学材料科学与工程学院材料研究所,上海,200072

6.上海大学材料科学与工程学院材料研究所,上海,200072

7.中国核动力研究设计院反应堆燃料及材料重点实验室,成都,610041

基金项目: 上海市浦江人才计划(12PJ1403600) 教育部博士点基金博导类项目(20123108110021) 核燃料与材料重点实验室基金

关键词： 690镍基合金 , 压水堆核电站 , 冷加工 , 拉伸试验 , 氢

Effects of Prior Deformation and Prior Immersion in Simulated Pressurized Water Reactor Primary Water on Tensile Properties of Alloy 690

Keywords： nickel-based alloy 690 , pressurized water reactor , cold work , tensile test , hydrogen

研究了预充氢和模拟压水堆核电站一回路水中预浸泡对有、无经过2o％轧制冷加工690合金拉伸性能的影响.室温下空气中拉伸试验结果表明,冷加工显著提升690合金的抗拉强度并降低延伸率和断面收缩率;预充氢显著降低有、无冷加工690合金的延伸率和断面收缩率,并且降低冷加工690合金的抗拉强度;高温水中预浸泡对未冷加工690合金的拉伸性能有一定影响.320℃高温水中测得的抗拉强度、延伸率和断面收缩率均低于室温时的值;高温水中预浸泡对抗拉强度和延伸率的影响不大,使断面收缩率略有增大.

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