详细信息

Transient analysis and optimization of passive residual heat removal heat exchanger in advanced nuclear power plant  ( SCI-EXPANDED收录 EI收录)  

文献类型:期刊文献

英文题名:Transient analysis and optimization of passive residual heat removal heat exchanger in advanced nuclear power plant

作者:Liu, Yan-Bin[1];Meng, Xiang-Yu[1];Wang, Xue-Sheng[1];Men, Qi-Ming[2];Yuan, Yu-Yang[1];Cao, Jia-Ming[1]

机构:[1]East China Univ Sci & Technol, Key Lab Pressure Syst & Safety, Minist Educ, Shanghai 200237, Peoples R China;[2]State Power Investment Corp, Shanghai Nucl Engn Res & Design Inst, Shanghai 200233, Peoples R China

年份:2022

卷号:33

期号:8

外文期刊名:NUCLEAR SCIENCE AND TECHNIQUES

收录:;EI(收录号:20223612685944);WOS:【SCI-EXPANDED(收录号:WOS:000844264300001)】;

基金:This work was supported by the Shanghai Nuclear Engineering Research and Design Institute, State Power Investment Corporation.

语种:英文

外文关键词:Heat transfer; PRHR HX; Transient analysis; Optimization investigation

摘要:The transient performance and optimization of a passive residual heat removal heat exchanger (PRHR HX) were investigated. First, a calculation method was developed for predicting the heat transfer of the PRHR HX. The calculation results were validated through comparisons with ROSA experimental data. The heat-transfer performance of the AP1000 PRHR HX in the initial period was predicted, and it satisfied the design requirements. Second, the distributions of the heat flux, tube-inside/outside heat-transfer coefficients, and heat load for the AP1000 PRHR HX over 2000 s were examined. Third, an optimization study was conducted by adjusting the horizontal length and tube diameter. Their effects on the four main heat-transfer parameters and the heat-transfer area were analyzed. Furthermore, the influence of the initial in-containment refueling water storage tank (IRWST) temperature was investigated using an established simulation procedure. The results indicated that it significantly affected the trends of the IRWST temperature and reactor outlet temperature. Finally, the minimum required flow rates over time to maintain the reactor outlet temperature at the safety line were determined for different start-up times. The trends of the minimum required flow rate and the peak flow rate were analyzed.

参考文献:

正在载入数据...

版权所有©华东理工大学 重庆维普资讯有限公司 渝B2-20050021-7 
渝公网安备 50019002500408号 违法和不良信息举报中心