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.
出处
《辐射防护通讯》
2011年第6期1-5,共5页
Radiation Protection Bulletin
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
Steam generator tube rupture accident
Design basis accidentsRadiological consequence
Acceptance criteria
