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秦山一厂严重事故管理导则典型事故缓解对策有效性验证

王勇 魏严凇 史晓磊 张应超

原子能科学技术2017,Vol.51Issue(4):666-670,5.
原子能科学技术2017,Vol.51Issue(4):666-670,5.DOI:10.7538/yzk.2017.51.04.0666

秦山一厂严重事故管理导则典型事故缓解对策有效性验证

Strategy Validation of Severe Accident Management Guidance for Qinshan-Ⅰ NPP under Typical Severe Accident Sequence

王勇 1魏严凇 2史晓磊 2张应超2

作者信息

  • 1. 中核霞浦核电有限公司,福建 宁德 355100
  • 2. 中国原子能科学研究院 反应堆工程技术研究部,北京 102413
  • 折叠

摘要

Abstract

National Nuclear Safety Administration (NNSA) requires nuclear power plants (NPPs) to improve their abilities to deal with severe accident after Japanese Fukushima nuclear accident.The severe accident management guidance (SAMG) was developed for Qinshan-Ⅰ NPP in response to NNSA.Typical severe accident sequences were simulated by using MELCOR code,according to strategy used in SAMG,to validate the effectiveness of the strategy on plant main parameters during the progress of severe accident.The results show that the progress of core damage will be terminated or delayed if actions are taken in time.

关键词

严重事故管理导则/MELCOR程序/严重事故/缓解对策有效性

Key words

SAMG/MELCOR code/severe accident/strategy validation

分类

能源科技

引用本文复制引用

王勇,魏严凇,史晓磊,张应超..秦山一厂严重事故管理导则典型事故缓解对策有效性验证[J].原子能科学技术,2017,51(4):666-670,5.

原子能科学技术

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