压水堆核电厂超压分析探讨  

Discussion on the Overpressure Analysis of PWR NPP

作　　者：肖红[1] 郑继业[1] 石俊英[1] 路燕[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082

出　　处：《核安全》2014年第3期50-55,共6页Nuclear Safety

摘　　要：本文介绍了核电厂一回路冷却剂系统、主蒸汽系统及安全壳系统的超压事故分析,涉及内容包括超压验收准则、初始参数和边界条件、分析范围、分析方法等。结合核电厂执照申请文件和最新研究成果,围绕核电行业要求"利益和安全平衡"的特殊原则,本文概述了在审评过程中遇到的问题及其解决方案,旨在探讨如何进一步完善超压分析,推进核电厂的执照申请和审评工作。The article describes the main point about overpressure accident analysis of the primary coolant system, the main steam system, containment system of nuclear power plant, involving the acceptance criteria, the initial boundary conditions and parameters, analysis scope, methodology and so on. It combines with the power plant license files request and the latest research results, the specific principles of the requirements on the balance between interests and security around the nuclear power industry, outlining problems and solutions encountered in the review process. The aim is to explore how to further improve the overpressure analysis, promoting the power plant license requesting and review process.

关 键 词：核电厂 超压 事故分析 

分 类 号：TL31[核科学技术—核技术及应用]