棱柱状高温堆堆芯高效热工计算模型开发及验证  

Development and Verification of the Efficient Thermal-fluid Calculation Method for the Prismatic High Temperature Reactor Core

作　　者：郭娟娟 童朴 孔德泰 何昉 黄善仿[2] 王侃[2] GUO Juanjuan;TONG Pu;KONG Detai;HE Fang;HUANG Shanfang;WANG Kan(China Institute of Nuclear Industry Strategy,Beijing 100048,China;Tsinghua University,Beijing 100084,China)

机构地区：[1]中核战略规划研究总院有限公司,北京100048 [2]清华大学,北京100084

出　　处：《核科学与工程》2022年第4期792-800,共9页Nuclear Science and Engineering

摘　　要：棱柱状高温堆作为四代堆候选堆型之一,固有安全性高,堆芯稳定性好。该堆堆芯热工计算通常采用CFD方法,网格量大,计算效率低,且多孔介质法不适用于棱柱式高温堆堆芯的计算分析。因此,本文提出了“一维流体、三维固体”的简化热工模型,基于Multi-physics Object-Oriented Simulation Environment (MOOSE)平台开发了PHEASANT程序。分别计算了棱柱状高温堆MHTGR-350MW基准题的单通道及组件级别算例,并与CFD程序OpenFOAM的计算结果进行了对比验证,温度平均偏差为1%,最大偏差不超过3%,且PHEASANT计算时间减少90%。因此,所提出的简化热工模型准确可信,且计算效率高。Prismatic high temperature gas-cooled reactor is one of the Generation IV nuclear reactors,and has the advantages of inherent safety and core stability.Traditional thermal-fluid calculation method of this kind of reactor is the CFD simulation,but has low computational efficiency due to the large amount of the model grid.Besides,the porous media method adopted by the pebble-bed high temperature reactor is not applicable to the prismatic core.Therefore,this paper has proposed the simplified thermal-fluid model,1D fluid and 3D solid,and has also developed the PHEASANT code based on the MOOSE platform to implement this simplified model.This paper has calculated the single channel and assembly cases of the prismatic high temperature benchmark MHTGR-350MW,and compared results with that of the CFD tool OpenFOAM.The average and maximum deviations between two codes are 1% and 3%,respectively.Besides,the calculation time of the PHEASANT code is reduced by 90% compared with that of OpenFOAM.Thus,comparison results demonstrate that the proposed simplified thermal-fluid model is accurate and highly efficient.

关 键 词：棱柱状高温堆 堆芯热工计算 MOOSE PHEASANT OPENFOAM 

分 类 号：TL48[核科学技术—核技术及应用]