秦山三期重水堆核电工程安全壳结构强度验证试验和整体密封性试验  

Reactor Building Pressure Proof Test (PPT) & Leak Rate Test (LRT) of Qinshan Phase Ⅲ(CANDU) Project

作　　者：顾军[1] 侍今奇 范福平[1] 

机构地区：[1]秦山第三核电有限公司,浙江海盐314300

出　　处：《中国核科技报告》2004年第2期107-121,共15页China Nuclear Science and Technology Report

摘　　要：作为我国首座无钢衬里安全壳,秦山第三核电有限公司认真研究了其混凝土吸纳/缓释效应强、贯穿件薄弱等特点,精心准备试验方案和应急处理措施,最终取得了安全壳密封性试验结果和试验耗时居世界同类电站领先地位的佳绩。在试验中开创性地使用了安全壳内部压空自供应系统,实现了不停运壳内工艺系统进行试验的目标;集成、开发了专用于安全壳强度验证试验和安全壳整体泄漏率试验的测试系统;在国内安全壳试验领域率先成功组织了高气压环境下的大规模作业。<Author>As the first reactor building (R/B) without stainless steel liner in china, TQNPC studied the containment characteristics, such as strong concrete absorb/release air effect, poor containment penetration.etc. And carefully prepared test scheme and emergency response, creatively introduced the instrument air self-supply system in reactor building, developed the special measurement & analysis system for PPT & LRT, organized work under high-pressure on large-scale in the test. Finally got the containment leak rate result and the test-cost-time value is the best in all same type tests. Key words:CANDU-6, Pressure proof test, Leak rate test, Air absorb/release effect, Instrument air self-supply system

关 键 词：安全壳试验 强度验证 整体密封性 压空白供应系统 

分 类 号：TL364.3[核科学技术—核技术及应用]