基于蒙特卡罗方法的IVR熔融池内热源时序模型构建及分析  

Construction and Analysis of Time-series Heat Source Model in IVR Molten Pool Based on Monte Carlo Method

作　　者：陈俊逸 黄善仿[1] 郝以昇 刘国栋 胡钰文 黎阳[2] 宫厚军[2] 昝元锋 郭啸宇[1] 骆浩 CHEN Junyi;HUANG Shanfang;HAO Yisheng;LIU Guodong;HU Yuwen;LI Yang;GONG Houjun;ZAN Yuanfeng;GUO Xiaoyu;LUO Hao(Department of Engineering Physics,Tsinghua University,Beijing 100084,China;CNNK Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China,Chengdu 610041,China)

机构地区：[1]清华大学工程物理系,北京100084 [2]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,四川成都610041

出　　处：《原子能科学技术》2022年第6期1163-1170,共8页Atomic Energy Science and Technology

基　　金：国家重点研发计划(2018YFB900104)。

摘　　要：堆内熔融物滞留(IVR)作为反应堆严重事故的关键缓解策略,目前已广泛应用于新一代压水堆(PWR)。针对IVR的有效性,如熔融池内对流、下封头传热、壁面临界热流密度(CHF)的估算等研究,是该领域数年来的热点。针对上述问题,国内外先后开展了数起实验,如COPO、BALI、SEMICO、COPRA等,并基于实验结果展开了大量数值模拟,以探索IVR下的传热规律,为其性能及设计提供参照。本文基于中子物理蒙特卡罗程序RMC对压力容器下封头熔融池模型进行了细网格建模及材料填充,并通过燃耗/衰变热计算DEPTH程序构建了熔融池内热源时序模型。研究结果显示,该模型能体现熔融池内热源变化趋势,得到的时序数据对IVR的进一步研究有重要意义。In-vessel retention(IVR)was widely recognized as the key mitigation strategy for severe reactor accidents in the new-generation PWR.The research on the effectiveness of IVR is a hot spot presently.Experiments like COPO,BALI,SEMICO and COPRA were carried out to solve problems above,and many numerical simulations were also conducted to explore heat transfer characteristics of IVR.However,in previous experiments and simulations,lack of real-time volumetric heat source renders results uncertainty.Previous experiments mostly use a constant heat source to simulate the molten pool heat generation.However,the heat released consists of fission power and decay heat,which is closely related to neutron physics and nuclide evolution in the molten pool.Artificial constant heat source cannot simulate the physical process in the molten pool,and therefore cannot accurately reflect the fine real-time pattern of heat released,rendering simulation and heat flux measurement uncertainties.To accurately calculate the power generated by physical analysis,Tsinghua University proposed a new molten pool decay heat calculation method based on the Reactor Monte Carlo program,which was verified to be accurate.At distinct core operation times,the nuclide composition,heat release pattern and physical evolution of molten pool are different.The previous work managed to explore the molten pool decay power distribution,but failed to consider how different core operation times and other nuclear reactions affect power distributions,which is necessary for safety analysis and design.Therefore,it is important to establish the fine time-series model of heat source in the molten pool and analyze the corresponding physical mechanism.RMC is a Monte Carlo neutron transport program with functions of critical calculation and burnup calculation.DEPTH module is a built-in burnup calculation module of RMC with the functions of large-scale burnup calculation and decay heat calculation.The code can be used to simulate the fission process driven by delayed neutron a

关 键 词：堆内熔融物滞留 蒙特卡罗方法 DEPTH 内热源 时序模型 

分 类 号：TL364[核科学技术—核技术及应用]