期刊文献+

核电站核岛筒体类锻件锻造工艺参数的分析与确定 被引量:2

Analysis and Determination of Forging Process Parameters of Cylinder Shell Forgings for Nuclear Power Plant Nuclear Island
下载PDF
导出
摘要 以核岛反应堆压力容器堆芯筒体锻件为例,通过分析和探讨核岛筒体类锻件材料特点、标准规范、采购要求以及制造工艺特点,研究了筒类锻件的锻造主工艺参数,明确了变形目的,制定出合理的筒类件的锻造工艺。 Taking nuclear island(NI) reactor pressure vessel(RPV) core shell as example,through analyzing and discussing characteristics of materials,standard or norm,purchase requirements and characteristics of manufacturing process of NI cylinder shell forgings,the main forging process parameters are researched,the deformation purpose is made clear,and then the reasonable forging process is constituted.
出处 《热加工工艺》 CSCD 北大核心 2011年第17期106-108,共3页 Hot Working Technology
关键词 堆芯筒体锻件 锻造工艺 标准规范 国产化 core shell forging forging process standard or norm localization
  • 相关文献

参考文献6

二级参考文献9

  • 1法国阿海珐公司.EPR—先进核电技术[J].核电,2005,(0):1-88.
  • 2INEEL/EXT-03-01210 Supercritical water reactor (SCWR) [ R ].Progress Report for the FY-03 Generation-IV R&D Activities for the Development of the SCWR in the U.S.,Jacopo Bunongiorno,U.S.SCWR Product Manager,INEEL,& Philip E,MacDonald,INEEL,2003-09-30:1-38.
  • 3MALCOLM P,LABAR.GA-A23952 The gas turbine-modular helium reactor:A promising option for near term deployment [J ].General Atomics,2002 (4):1-8.
  • 4美国西屋公司.AP1000—先进核电技术[J].核电,2005,(0):1-84.
  • 5上海发电设备成套设计研究院.压水堆核电站核岛主设备材料和焊接[M].上海:上海科学技术文献出版社,2008.
  • 6RCC-M 2000,Design and Construction Rules for Mechanical Components of PWR Nuclear Power Plants[S].
  • 7RCC-M-2000. Design and construction rules for mechanical components of PWR nuclear islands[S].
  • 8Nuclear News . 2 0 0 0
  • 9阚玉琦,陈晓青,梁书华.反应堆压力容器大型锻件热加工质量控制研究[J].热加工工艺,2009,38(23):138-141. 被引量:17

共引文献68

同被引文献14

引证文献2

二级引证文献9

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部