SUB-CHANNEL ANALYSIS ON SCWR ASSEMBLY OF DOUBLE-ROW FUEL RODS
In this paper, according to the calculated axial and radial power distribution of core assembly, anumerical analysis of thermal-hydraulic behavior in supercritical water-cooled reactor ofCGNPC(CGN-SCWR) is performed by using sub-channel analysis software ATHAS. The coolant flowin CGN-SCWR reactor core uses double-flow approach. In order to ensure the maximum claddingtemperature (MCT for short) reached the requirements throughout the entire life cycle, the sub-channelanalysis of fuel assembly with the maximum cladding temperature in the BOC, MOC and EOC hadbeen respectively carried out. The temperature and density properties of coolant and moderator in thefuel assembly were investigated. The maximum cladding temperature of the fuel assembly wasobtained. And the selected typical sub-channels were analyzed in detail. The results show that themaximum cladding temperature, coolant outlet temperature and other parameters in CGN-SCWRreactor core through the whole life time meet the thermal design requirements.
Fei WANG Jue YANG Xiangang FU Hongbo LI Yong ZHANG Jianmin ZHANG Jianqiang SHAN Junli GOU Bo ZHANG Chao CHEN
China Nuclear Power Technology Research Institute CNPRI,China Guandong Nuclear Power Corporation CGN Xian Jiaotong University XJTU,Xian ,China
国际会议
3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors(第三届中国-加拿大超临界水堆研讨会 (CCSC-2012)
西安
英文
1-9
2012-04-18（万方平台首次上网日期，不代表论文的发表时间）