高温气冷堆事故工况下舱室冷却系统排热性能分析  

Heat Removal Performance Analysis of HTR-PM Reactor Cavity Cooling System under Accident Condition

作　　者：秦亥琦 李晓伟 张丽 柳雄斌 郑艳华 吴莘馨 QIN Haiqi;LI Xiaowei;ZHANG Li;LIU Xiongbin;ZHENG Yanhua;WU Xinxin(Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education,Collaborative Innovation Center of Advanced Nuclear Energy Technology,Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China)

机构地区：[1]清华大学核能与新能源技术研究院,先进核能技术协同创新中心,先进反应堆工程与安全教育部重点实验室,北京100084

出　　处：《原子能科学技术》2025年第4期838-845,共8页Atomic Energy Science and Technology

基　　金：国家重点研发计划(2020YFB1901600);国家自然科学基金(51576103);国家科技重大专项(ZX06901)。

摘　　要：舱室冷却系统(RCCS)是球床模块式高温气冷堆(HTR-PM)的重要安全设施,预测事故工况下混凝土温度分布对于核安全具有重要意义。本文依托HTR-PM事故分析,采用计算流体动力学(CFD)方法,开展了RCCS全比例二维辐射传热及对流换热模拟。结果显示:RCCS具备充分的排热能力以实现反应堆舱室的有效冷却,在严重事故工况下,混凝土最高温度约为111℃,远低于设计限值;事故引起的舱室内热扰动穿透混凝土所需时间约为48 h,混凝土内部温度分布在约120 h后趋于稳定;给出了混凝土内、外壁面换热量分布。本文结果可为RCCS设计、高温气冷堆事故分析提供参考。The reactor cavity cooling system(RCCS) is an important safety facility for high-temperature gas-cooled reactor pebble-bed module(HTR-PM).The RCCS relies on two coupled natural circulations to passively remove the reactor cavity heat to the ultimate heat sink(atmosphere),i.e.,the air natural circulation within the cooling tower and the cooling-water natural circulation.It does not depend on any active equipment for example pumps,fans,and diesel engines.Even under accident conditions,it also does not require operator intervention and control signals.Therefore,the RCCS is called a fully passive cooling system.During normal operation,the RCCS is responsible for cooling the reactor cavity.Under accident conditions,the RCCS can stably and passively remove the core decay heat to ensure the thermal integrity of the reactor pressure vessel(RPV) and reactor cavity.For each reactor module of the HTR-PM,the RCCS is divided into three independent units.According to the design requirements,any two units operating normally can provide the required heat removal power under any operation condition.Based on the accident analysis of HTR-PM,the reactor cavity heat about 500 kW and 1200 kW is needed to be removed under normal operation and accident conditions,respectively.Correspondingly,the maximum concrete temperature should be controlled below 65 ℃ and 180 ℃,as mentioned in the division 2(Code for Concrete Containments) of ASME BPVC-Ⅲ(Rules for Construction of Nuclear Facility Components).In the current investigation,the computational fluid dynamics(CFD) method was used to carry out a 2D full-scale simulation of RCCS convection and radiation heat transfer.Specifically,the symmetric boundary conditions were used for a local one twentieth model(18°chamfer),including 15 RCCS water cooling pipes.There were three types of the simulated operation conditions,such as the shielding cooling system failure,one RCCS unit failure and the pressurized loss of forced cooling(PLOFC) accident.The results show that under any operation condit

关 键 词：球床模块式高温气冷堆 舱室冷却系统 混凝土 排热性能 

分 类 号：TL352.1[核科学技术—核技术及应用]