Determination of Residual Stress in Nuclear Class Heat Exchange Tubes Based on Standard RCC-M
摘 要
为保证核电站的安全运行, 降低核级换热器传热管的环境敏感开裂风险, 核级传热管的采购标准《压水堆核岛机械设备设计和建造规则》(RCC-M)中规定了残余应力的检验要求。重点介绍了残余应力检验采用的C型环试验和沸腾氯化镁试验方法及需要注意的问题。其中C型环试验可以定量检验出残余应力值; 沸腾氯化镁试验可用于证明传热管的表面残余应力是否小于某个要求值。这两种方法便于实施, 可满足工业化的核电用不锈钢传热管采购的检验需要。
Abstract
To keep the operation safety of nuclear power station and reduce the risk of environment sensitive cracking of nuclear class heat-exchange tubes, RCC-M specified the requirement of residual stress test. It was mainly introduced including the C-ring and boiling magnesium chloride residual stress test and the problems that needed attention. C-ring test can give the residual stress quantitative, and boiling magnesium chloride test can prove whether the residual stress less than a given required value. These two methods are easy to implement, which can satisfy the test requirement of nuclear class heat exchange tubes in industrialization production.
中图分类号 TM623.7
所属栏目 试验技术与方法
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收稿日期 2013/5/13
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备注黄大鹏(1980-), 男, 工程师。
引用该论文: HUANG Da-peng,LIU Hong-wei,KAN Yu-qi. Determination of Residual Stress in Nuclear Class Heat Exchange Tubes Based on Standard RCC-M[J]. Physical Testing and Chemical Analysis part A:Physical Testing, 2014, 50(3): 191~193
黄大鹏,刘红伟,阚玉琦. 基于RCC-M标准的核级换热器传热管残余应力的检验[J]. 理化检验-物理分册, 2014, 50(3): 191~193
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参考文献
【1】郑文龙, 施伟力.残余应力测定的基本知识 第六讲 残余应力与环境敏感开裂[J].理化检验-物理分册, 2007, 43(11):587-593.
【2】RCC-M 2000Design and Construction Rules for Mechanical Components of PWR Nuclear Power Plants[S].
【3】李志华.X80级JCOE直缝埋弧焊管残余应力估算与分析[J].焊管, 2008, 31(6):32-38.
【4】陆世英, 王欣增, 李丕种, 等.不锈钢应力腐蚀事故分析与耐应力腐蚀不锈钢[M].北京: 原子能出版社, 1985:1-38.
【5】MCLLREE A R. Alloy 690 for steam generator tubing applications[R].Pittsburgh, Pennsylvania: Westinghouse Electric Corporation, 1990.
【2】RCC-M 2000Design and Construction Rules for Mechanical Components of PWR Nuclear Power Plants[S].
【3】李志华.X80级JCOE直缝埋弧焊管残余应力估算与分析[J].焊管, 2008, 31(6):32-38.
【4】陆世英, 王欣增, 李丕种, 等.不锈钢应力腐蚀事故分析与耐应力腐蚀不锈钢[M].北京: 原子能出版社, 1985:1-38.
【5】MCLLREE A R. Alloy 690 for steam generator tubing applications[R].Pittsburgh, Pennsylvania: Westinghouse Electric Corporation, 1990.
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