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核压力容器钢和焊缝的力学性能研究

MECHANICAL PROPERTIES OF NUCLEAR PRESSURE VESSEL STEEL AND IT’S WELDS

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【作者】 邰江崔岚张庄史巨元

【Author】 TAI Jiang CUI Lan ZHANG Zhuang SHI Juyuan (Beijing Institute of Nuclear Engineering)(Central Iron & Steel Research Institute)

【机构】 核工业第二研究设计院钢铁研究总院钢铁研究总院

【摘要】 研究了核一二级压力容器焊缝的拉伸、冲击性能及低周疲劳性能与母材的匹配性 ,同时制定了设计疲劳曲线 ,按照 ASME和 RCC- M规范进行了评价。结果表明 ,焊接接头的低周疲劳性能与母材匹配较好 ,一级容器钢 (A5 0 8- 3)疲劳寿命 Nf≥ 10 3时其设计疲劳曲线与 ASME和 RCC- M的基准曲线相当 ;Nf≤ 10 3时则比基准曲线稍低。二级容器用 2 0 HR钢及接头的设计疲劳曲线 (因试验温度高 2 0℃ )则略低于基准曲线

【Abstract】 The tensile properties,impact toughness, low cycle fatigue and matchable properties with base material of steel welds,which will be used for nuclear pressure vessel, have been studied. At same time, the design fatigue curves of steel have been established.The research and curves have been evaluated according to ASME and RCC M code. The result show, the low cycle fatigue properties of steel welds are matchable with base material, the design fatigue curves of class 1 nuclear pressure vessel steel (A508 3) are equivalent with design basis curves defined in ASME and RCC M code when fatigue life is N f ≥10 3 and a little lower than design basis curves when fatigue life is N f ≤10 3, the design fatigue curves of class 2 nuclear pressure vessel steel (20HR) are lower than design basis curves .

  • 【文献出处】 钢铁 ,Iron and Steel , 编辑部邮箱 ,2003年09期
  • 【分类号】TG407
  • 【被引频次】12
  • 【下载频次】469
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