| 注册
首页|期刊导航|核安全|VVER机组事故分析耦合程序开发及应用

VVER机组事故分析耦合程序开发及应用

陈静 陈超 蒋校丰 任一飞 张健夫

核安全2026,Vol.25Issue(1):1-9,9.
核安全2026,Vol.25Issue(1):1-9,9.

VVER机组事故分析耦合程序开发及应用

Development and Application of Accident Analysis Coupled Code for VVER Units

陈静 1陈超 2蒋校丰 2任一飞 3张健夫3

作者信息

  • 1. 江苏核电有限公司,连云港 222042||上海核星核电科技有限公司,上海 201103
  • 2. 上海核星核电科技有限公司,上海 201103
  • 3. 江苏核电有限公司,连云港 222042
  • 折叠

摘要

Abstract

Neutronics/thermal-hydraulic coupled code was developed to model the accidents for VVER units especially in which strong neutronics/thermal coupling effect and obvious change of local power distribution exist.Through dynamic link library technology and building coupling interface model,three-dimensional neutronic kinetics code and thermal-hydraulic code were coupled.Transient simulation on the inadvertent dilution of boric acid accident of VVER-1000 units was carried out based on the coupled code.The sequence of event and parameters in the primary and second circuits were analyzed.Finally,compliance of critical safety-relevant parameters with acceptance criteria was evaluated.Results indicate that simulated values obtained by the coupled code agree well with measured data of the power plant.Variation trends of neutronic and thermal-hydraulic parameters present overall consistence with those of FSAR,and the deviation of the extreme values is small.The computing performance and reliability of the coupled code were proved.Safety acceptance criteria related to maximum fuel temperature,minimum DNBR and other values are satisfied.Neutronics/thermal-hydraulic coupled code could be used as an effective tool for accurate accident modeling of VVER units.

关键词

VVER机组/事故分析/物理热工耦合/硼酸误稀释

Key words

VVER units/accident analysis/neutronics/thermal coupling/inadvertent dilution of boric acid

分类

能源科技

引用本文复制引用

陈静,陈超,蒋校丰,任一飞,张健夫..VVER机组事故分析耦合程序开发及应用[J].核安全,2026,25(1):1-9,9.

基金项目

中核集团"青年英才"项目 ()

核安全

1672-5360

访问量0
|
下载量0
段落导航相关论文