原子能科学技术2017，Vol.51Issue(6)：994-1001,8.DOI:10.7538/yzk.2017.51.06.0994
基于RELAP5MOD3.2的钠冷快堆热工水力系统分析程序开发及验证
Development and Verification of Thermal-hydraulic System Analysis Code Based on RELAP5 MOD3.2 for SFRs
摘要
Abstract
The general-purpose reactor thermal-hydraulic analysis code RELAP5 MOD3.2 was modified for system analysis of sodium-cooled fast reactor (SFR).The thermodynamic and transport properties of sodium liquid and vapor were implemented into the RELAP5 MOD3.2 code,as well as the specific heat transfer correlations for liquid metal.The methods of code modifications are universal for other working fluids and will not affect the code original performance.The benchmark on loss of flow accident transient of Experimental Breeder Reactor Ⅱ (EBR-Ⅱ) for Argonne National Laboratory (ANL) was analyzed to verify the modified code.The results show that the reactor can shut down automatically relying on inherent negative feedbacks and major thermal-hydraulic parameters are lower than the safe limits.Moreover,the calculation results are consistent with the experimental data and other SFR system analysis code results.The work in the paper can demonstrate the capability and reliability of the modified RELAP5 for the analysis of SFRs further.关键词
RELAP5/钠冷快堆/液态金属物性/热工水力分析/程序开发Key words
RELAP5/sodium-cooled fast reactor/liquid metal physical property/thermal-hydraulic analysis/code development分类
能源科技引用本文复制引用
宋健,谭超,唐思邈,刘利民,田文喜,巫英伟,秋穗正,苏光辉..基于RELAP5MOD3.2的钠冷快堆热工水力系统分析程序开发及验证[J].原子能科学技术,2017,51(6):994-1001,8.基金项目
国家自然科学基金资助项目(11575141) （11575141）
