压水堆核电厂蒸汽发生器传热管破裂事故后果分析中若干问题的讨论  

Analysis of Radiological Consequence of SGTR Accident at PWRs

作　　者：陈莹莹[1] 李冰[1] 陈晓秋[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082

出　　处：《辐射防护通讯》2011年第6期1-5,共5页Radiation Protection Bulletin

摘　　要：压水堆核电厂蒸汽发生器传热管破裂事故是核电厂安全分析报告需要评价的一个重要的设计基准事故,随着该事故的工况分类由极限事故变更为稀有事故,其放射性后果不能满足我国放射性后果验收准则的要求。本文从SGTR事故放射性后果评价的计算假设、事故源项、验收准则及国内外的实践情况等几方面进行讨论,认为应对SGTR事故作进一步的研究,寻求从设计上的解决方案,同时还应结合SGTR的事故特征给出更为合理的验收准则。The steam generator tube rupture accident at PWRs is an important design basis accident to be evaluated in nuclear power plant safety analysis report. With the classification of this accident condition being changed from limiting accident to infrequent accident, the radiological consequence can not meet our country＇ s acceptance criteria. The calculation assumption, source term of SGTR, acceptance criteria and practices in China and abroad are discussed, the conclusion is that the SGTR accident should be studied further to seek so- lutions from design, and a more reasonable acceptance criteria should be given.

关 键 词：蒸汽发生器传热管破裂事故 设计基准事故 放射性后果 验收准则 

分 类 号：TM623.8[电气工程—电力系统及自动化]