摘要
10 MW高温气冷实验堆(简称HTR-10)是我国第一座模块式高温气冷堆,由清华大学核能与新能源技术研究院(核研院)设计。按照我国核安全法规的要求,并经过国家核安全局的批准,核研院于2012年开始对10 MW高温气冷实验堆进行定期安全审查(简称PSR),安全分析是本次审查的重点安全要素之一。本文对安全分析要素审查的主要内容作了概述,并给出了核研院对本次审查的内部评价。
Designed by the Institute of Nuclear and New Energy Technology（INET）of Tsinghua University,the 10 MW High Temperature Gas-cooled Reactor-Test Module（HTR-10）is the first modular High Temperature Gas-cooled Reactor（HTGR）in China. According to the nuclear safety regulations of China,the periodic safety review（PSR）of the HTR-10 was initiated by INET after approved by the National Nuclear Safety Administration（NNSA）of China. Safety analysis of the HTR-10 is one of the key safety factors of the PSR. In this paper,the main contents in the review of safety analysis are summarized;meanwhile,the internal evaluation on the review results is presented by INET.
出处
《核安全》
2015年第1期19-24,共6页
Nuclear Safety
基金
国家重大科技专项经费资助项目
课题编号ZX069
