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作 者:王子健 隋丹婷 张珺 陆道纲[1,2] 王莺旭 余金源 WANG Zijian;SUI Danting;ZHANG Jun;LU Daogang;WANG Yingxu;YU Jinyuan(School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China;Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy,North China Electric Power University,Beijing 102206,China)
机构地区:[1]华北电力大学核科学与工程学院,北京102206 [2]北京市非能动安全重点实验室,北京102206
出 处:《核科学与工程》2024年第6期1226-1238,共13页Nuclear Science and Engineering
摘 要:将堆芯熔融物滞留在压力容器内部是严重事故重要的缓解措施之一,但是保证该措施有效的前提是准确计算熔池内含有内热源的熔融物的分布和流动,并基于该结果评价压力容器结构的完整性。本文对传统的MPS方法进行改进,增加了粒子间的传热计算部分,探究了定温壁面处粒子在权函数中的权重。基于方腔导热基准题和方腔对流换热基准题,验证了MPS对于导热现象的最大误差为1.5%,确定了定温壁面处粒子在权函数中的权重因子是流体域内部粒子的4倍。针对COPRA实验进行模拟,MPS计算平均误差为3%,验证了带内热源的熔池模型模拟结果的准确性。为MPS方法在反应堆熔池中与熔融物相关的流动及传热问题的数值模拟研究提供支持。One of the important mitigation measures after reactor severe accident is to retain the core corium in the pressure vessel.However,the premise of corium retention and cooling is to accurately calculate the heat source distribution and flow in the lower plenum of pressure vessel,which will form molten pool after severe accident.In this paper,the traditional MPS method is improved by adding the part of heat transfer calculation between particles,and the weights of particles in the weight function at the constant-temperature wall are explored.Based on the square-cavity thermal conductivity benchmark problem and the square-cavity convective heat transfer benchmark problem,the maximum error of MPS for thermal conductivity phenomena is verified to be 1.5%,and it is deter mined that the weight factor of the particles at the fixed-temperature wall in the weight function is four times that of the particles inside the fluid domain.Simulations were performed for the COPRA experiment with an average error of 3%in the MPS calculations,verifying the accuracy of the simulation results for the melt pool model with an internal heat source.Support is provided for the numerical simulation study of the MPS method for melt-related flow and heat transfer problems in reactor melt pools.
分 类 号:TL48[核科学技术—核技术及应用]
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