ASME锅炉及压力容器规范中关于核电厂部件安全裕量的控制  

The Control of Safety Allowance for Nuclear Power Plant Components in ASME-BPVC

作　　者：姚伟达[1] 宁冬[1] 杨仁安[1] 贺寅彪[1] 谢永诚[1] 张明[1] 姚彦贵[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《核安全》2011年第1期56-64,共9页Nuclear Safety

摘　　要：针对ASME锅炉及压力容器规范对如何从材料、设计、制作、试验、检测、建造以及役前和在役运行等各个阶段合理地控制其"安全裕量"做初步论述,并对"安全系数"和"验收准则"这两个定量要求也做了初步解剖。对保证"安全裕量"的控制文件和人员的责任做了简述。How to control the＂safety allowance＂reasonably at each phase of materials,design,fabrication, test,examination,building,pre-service and in-service operation and others in ASME-BPVC was preliminarily discussed.The two quantitative requirements of＂safety factor＂and＂acceptance criteria＂were dissected.The responsibilities of controlled documents and personnel to assure＂safety allowance＂were also represented.

关 键 词：ASME规范 核电厂 部件 安全裕量 控制 

分 类 号：TL351.6[核科学技术—核技术及应用]