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A508-3钢及其焊接材料与工艺研究

INVESTIGATION OF A508-3 STEEL AND ITS WELDING MATERIALS AND PROCESSES

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【作者】 张敬才王文华

【Author】 Zhang Jingcai Wang Wenhua et al. (Nuclear Power Institute of China, Chengdu) (In Chinese)

【机构】 中国核动力研究设计院中国核动力研究设计院 成都成都

【摘要】 介绍了压水堆核电站反应堆压力容器用A508-3钢及其配套焊接材料与工艺的研究情况。首先介绍了研究内容,包括6项母材物理参数测定、10项验收考核性能要求、21项测试及11项研究项目;其次概述了600MWe压水堆核电站反应堆压力容器堆芯简体及蒸汽发生器管板等壁厚模拟产品的制造;第三以八个表格形式给出了母材锻件、焊缝、热影响 区及堆焊层金属的验收要求以及对两个模拟产品的实测性能数据,同时给出了母材、焊缝及热影响区金属的快中子辐照试验结果;最后给出了评价.A508-3锻件的生产、两个模拟产品的制造及实测性能数据表明,我国掌握了压水堆核电厂核岛主设备母材与焊材的生产、焊接、堆焊工艺及无损检测等关键制造技术,核岛主要设备可以实现国产化。

【Abstract】 The investigation on A508-3 steel and its welding materials and processes was conducted. The contents includ 6 items of physical parameter measurement of base metal, 10 items of acceptable property requirement, 21 tests and 11 studies. The manufacture for the simulated products of reactor pressure vessel core sheel and steam generator tube plate for NPP of 600 MWe-PWR is described. The acceptance requirements and actual mechanical properties are given, which obtained from the base metal forgings, weld metal, heat affected zone, and overlaid weld metal of the two simulated products; the results of fast neutron irradiation test are given as well. It is commented that China has grasped the essential technology of producing the base metal and welding materials , welding and clading technology and non-destructive test, based on the productions of A508-3 steel forgings, welding materials, two simulated products, and the actual mechanical properties; the main equipments on nuclear island are able to be manufactured in China.

  • 【文献出处】 中国核科技报告 ,China Nuclear Science and Technology Report , 编辑部邮箱 ,1994年S1期
  • 【分类号】TL341
  • 【被引频次】3
  • 【下载频次】162
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