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Transient analysis and optimization of passive residual heat removal heat exchanger in advanced nuclear power plant

Transient analysis and optimization of passive residual heat removal heat exchanger in advanced nuclear power plant

作     者:Yan-Bin Liu Xiang-Yu Meng Xue-Sheng Wang Qi-Ming Men Yu-Yang Yuan Jia-Ming Cao Yan-Bin Liu;-Xiang-Yu Meng;Xue-Sheng Wang;Qi-Ming Men;Yu-Yang Yuan;Jia-Ming Cao

作者机构:Key Laboratory of Pressure Systems and SafetyMinistry of EducationEast China University of Science and TechnologyShanghai 200237China Shanghai Nuclear Engineering Research and Design InstituteState Power Investment CorporationShanghai 200233China 

出 版 物:《Nuclear Science and Techniques》 (核技术(英文))

年 卷 期:2022年第33卷第8期

页      面:147-162页

核心收录:

学科分类:080702[工学-热能工程] 080802[工学-电力系统及其自动化] 0808[工学-电气工程] 08[工学] 0807[工学-动力工程及工程热物理] 

基  金:supported by the Shanghai Nuclear Engineering Research and Design Institute State Power Investment Corporation 

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

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