核电站核岛筒体类锻件锻造工艺参数的分析与确定
Analysis and Determination of Forging Process Parameters of Cylinder Shell Forgings for Nuclear Power Plant Nuclear Island
张绍军,阚玉琦
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作者单位:苏州热工研究院有限公司 电站设备监理工程技术研究中心,江苏 苏州 215004
中文关键字:堆芯筒体锻件; 锻造工艺; 标准规范; 国产化
英文关键字: core shell forging; forging process; standard or norm; localization
中文摘要: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。
英文摘要: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.