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严重事故熔融池实验热工水力特性仿真分析

Simulation Study on Thermal Hydraulic Characteristics for Corium Pool Experiment of Reactor Severe Accident
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摘要 本文基于LIVE(Late In-Vessel Phase Experiments)三维压水堆熔融池模拟实验,采用COMSOL Multiphysics软件建立了适用于熔融池的仿真计算模型。通过非等温流动模块耦合流体传热和湍流流动过程,使用相变材料模型模拟实验中的非共晶摩尔比例20%NaNO_(3)-80%KNO_(3)熔盐,湍流模型设置为低雷诺数k-ε模型。仿真结果表明,稳态下熔融池内存在较强的沿冷却壁面向下的自然对流,同时还伴随着大量的涡流,在涡流搅拌作用下温度场形成了明显的热分层结构。仿真得到的熔融池中部和顶部区域温度分布以及冷却壁面上的结壳厚度与实验值十分接近,说明COMSOL软件适用于熔融池仿真工作。 Based on 3D PWR corium pool experiments LIVE,a computational model for corium pool simulation was built by COMSOL Multiphysics.The non-isothermal flow calculation module was employed to couple the turbulent flow field and heat transfer in the corium pool,the non-eutectic binary mixture of 20%NaNO_(3)-80%KNO_(3)was simulated by phase-change material model,the Low Reynolds number k-εturbulence model was selected to calculate the velocity field.The simulation results show that,a strong downward flow natural convection is formed near the cooling wall.Besides,many vortexes are existed in the corium pool,which lead to the thermal stratification of the temperature field in a steady-state condition.Since the simulated temperature distribution in the middle and top area of the corium pool,and the simulated thickness of the crust on the cooling wall are very close to the experimental data,the COMSOL software is suitable for the simulation of the corium pool.
作者 朱光昱 张宁娜 王昆鹏 石兴伟 左嘉旭 刘福东 ZHU Guangyu;ZHANG Ningna;WANG Kunpeng;SHI Xingwei;ZUO Jiaxu;LIU Fudong(Nuclear and Radiation Safety Center,MEE,Beijing 100082,China;State Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation,Beijing 102488,China;Center for Nuclear Power Safety,China Nuclear Power Engineering Co.,Ltd.,Beijing 100084,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2022年第3期631-636,共6页 Nuclear Science and Engineering
基金 国家重点研发计划“严重事故下堆芯熔融物行为与现象研究”(No.2018YFB1900100)课题2“熔融物碎片床形成及再熔化研究”(No.2018YFB1900102)。
关键词 熔融池 COMSOL 热分层 Corium pool COMSOL Thermal stratification
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