核设备建造中的成形工艺评定试验——ASME与RCC-M相应规定的对比分析  

Procedure Qualification of Forming of Nuclear Equipment——Comparison of Corresponding Items of ASME with RCC-M

作　　者：邓丰[1] 黄燕[1] 李焕鸣[1] 张敏杰[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《东方电气评论》2014年第1期51-54,59,共5页Dongfang Electric Review

摘　　要：成形操作会对金属材料的性能造成不利影响,故在设备建造规范中通常要求在某些条件下的成形操作需进行成形工艺评定,以确定成形操作对材料性能的影响。本文主要对ASME第Ⅲ卷和RCC-M中有关核设备成形工艺评定的相关规定进行了对比分析。ASME和RCC-M的成形工艺评定采用了完全不同的试验方法,但两个规范在技术要求上是相似的。而RCC-M规范中对于评定的相关规定较ASME更为详细具体,但其评定试验和检验项目更多。RCC-M对于低合金钢和碳钢临界应变率的规定偏高,且未考虑后续制造工艺对成形材料的影响,较ASME要求偏松。The forming procedure usually degrades the character of metal materials. In order to determine the influence over the material caused by the forming operation, the instruction rules for equipment usually require qualification assessment of the forming procedure under some conditions. This paper describes the comparison of items for forming procedure qualification between ASME section III and RCC-M, which are the two most widely used construction standards for the nuclear vessel. During the forming procedure qualification, ASME and RCC-M used completely different test methods, but the two standards were similar about technical requirements. Compare with ASME, the description of corresponding items of RCC-M were more specific and detailed, but the qualification test items and examination items is much more than ASME. The critical elongation of RCC-M for carbon steel and low alloy steel was too great, and RCC-M wasn＇t taking into account the influence over the material caused by subsequent processes, so these requirements of RCC-M were less rigorous compare with ASME.

关 键 词：核设备 成形工艺评定 ASME RCC-M 对比分析 

分 类 号：TM623[电气工程—电力系统及自动化]