池式非能动余热排出系统热工水力分析的系统程序改进及验证  

Improvement and Validation of System Code for Thermal-hydraulic Analysis of In-pool Passive Residual Heat Removal System

作　　者：连强 朱隆祥 唐思邈 黄涛 张勇[4] 潘良明[1,2] LIAN Qiang;ZHU Longxiang;TANG Simiao;HUANG Tao;ZHANG Yong;PAN Liangming(Key Laboratory of Low-grade Energy Utilization Technologies and Systems,Ministry of Education,Chongqing University,Chongqing 400044,China;Department of Nuclear Engineering and Technology,Chongqing University,Chongqing 400044,China;Postdoctoral Station of Power Engineering and Engineering Thermophysics,Chongqing University,Chongqing 400044,China;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]重庆大学低品位能源利用技术及系统教育部重点实验室,重庆400044 [2]重庆大学核工程与核技术系,重庆400044 [3]重庆大学动力工程及工程热物理博士后科研流动站,重庆400044 [4]中国核动力研究设计院核反应堆系统设计技术重点实验室,四川成都610213

出　　处：《原子能科学技术》2025年第4期858-866,共9页Atomic Energy Science and Technology

基　　金：国家自然科学基金(U23B2068)。

摘　　要：福岛核事故后非能动理念被广泛应用于先进反应堆的热工安全设计,而池式非能动余热排出系统(PRHRS)也在国产华龙一号中提供了不依赖外部能源驱动的安全保障。尽管RELAP5程序在反应堆瞬态热工水力特性分析方面开展了大量验证工作,但由于缺乏针对性的池式热交换器模型,RELAP5程序低估了池式PRHRS的换热功率及系统流量。因此本文根据池式热交换器工作条件选用棒束池式沸腾换热模型及大管径管内冷凝换热模型,在RELAP5程序中植入了池式热交换器模型,针对两种换热模型分别进行了分离效应验证。基于应急工况池式能量排出系统(PERSTO)实验台架分析了节点划分方式对池式PRHRS热工水力行为的影响,对比了改进程序及原始程序对整体性实验台架系统瞬态参数的模拟能力。经过分离效应验证和整体效应验证,确认了改进程序在池式PRHRS热工水力分析中的有效性。After Fukushima nuclear accident,the passive concept is widely adopted in the thermal safety design of advanced nuclear reactors.The in-pool passive residual heat removal system(PRHRS)can also provide security guarantee for the domestic reactor HPR1000 without driving of the external power.Although RELAP5 code has been extensively validated for thermal-hydraulic transients in nuclear reactor,it underestimates the heat exchanging power and the system flow rate in the in-pool PRHRS due to the lack of specialized model for in-pool heat exchanger.Therefore,the model development for the in-pool heat exchanger is necessary for accurate simulation of PRHRS and safety assessment of the reactor system.In this study,the in-pool bundle boiling model and large-diameter tube condensation model were selected and implemented in RELAP5 code as the in-pool heat exchanger model.Firstly,the relevant heat transfer models in original RELAP5 were evaluated.The results show that Chen correlation developed initially for in-tube boiling is not suitable for bundle boiling heat transfer.Thus Cooper correlation developed initially for in-pool boiling considering the surface roughness is used to replace Chen correlation for the bundle geometry.On the other hand,the calculation in original RELAP5 for in-tube condensation encounters some faults under the condition with low gas speed in the natural circulation of PRHRS.The Shah method modified through fluid viscosity and pressure is chosen for the calculation of condensation heat transfer coefficient in the largediameter tube.Secondly,the separate effect validation was carried out for the two heat transfer models.For the validation of in-pool bundle boiling model,the root-mean-square error of the heat transfer coefficient predicted by the improved RELAP5 is reduced to 16.2%,compared to the value of 53.8%obtained by the original code.For the validation of in-tube condensation model,the root-mean-square error of the heat flux predicted by the improved RELAP5 is reduced from 10.9% to 7.6%.Both mod

关 键 词：池式非能动余热排出系统 热工水力 系统程序改进 节点划分方式 模型验证 

分 类 号：TL334[核科学技术—核技术及应用]