原子能科学技术2018，Vol.52Issue(2)：320-325,6.DOI:10.7538/yzk.2017.youxian.0114
钠冷快堆棒状燃料堆芯子通道分析程序开发及验证
Development and Verification of Sub-channel Analysis Code for Solid Fuel Core of Sodium Cooling Fast Reactor
张松梅 1张东辉2
作者信息
- 1. 核工业研究生部,北京 102413
- 2. 中国原子能科学研究院,北京 102413
- 折叠
摘要
Abstract
The verification of thermal-hydraulic code is a focus of safety review .In order to verify the correctness of the analysis code through the comparison of different code calculation results,a detailed sub-channel calculation code SSCFR with independent intellectual property rights was developed for solid fuel core of sodium cooling fast reactor .Whole core steady analysis ,sub-channel steady analysis and whole core transient analysis for China Experimental Fast Reactor (CEFR) were performed by using SSCFR .The results of SSCFR were compared with the operation and design values of CEFR ,respectively .The results show that the calculation values of SSCFR agree well with the operation values and the calculation values of safety analysis report ,and SSCFR can be used to the design of the Chinese Demonstration Fast Reactor (CDFR).关键词
钠冷快堆/棒状燃料堆芯/子通道分析Key words
sodium cooling fast reactor/solid fuel core/sub-channel analysis分类
能源科技引用本文复制引用
张松梅,张东辉..钠冷快堆棒状燃料堆芯子通道分析程序开发及验证[J].原子能科学技术,2018,52(2):320-325,6.
