CEFR 3层水平热屏蔽热工流体的数值研究  

Numerical Simulation of Thermal-hydraulic Analysis for Triplex Horizontal Thermal-shielding in CEFR

作　　者：吕传凤[1] 张东辉[1] 乔雪冬[1] 吴纯良[1] 

机构地区：[1]中国原子能科学研究院中国实验快堆工程部,北京102413

出　　处：《原子能科学技术》2011年第8期925-930,共6页Atomic Energy Science and Technology

摘　　要：中国实验快堆(CEFR)采用池式结构,钠池分为冷钠池和热钠池,冷、热钠池之间的3层水平热屏蔽层既是热池的冷边界,也是冷池的热边界,其内部的热工流体直接影响着冷池和热池内的温度分布。针对CEFR满功率运行工况,利用CFX软件,对1/4区域水平热屏蔽层内的热工流体进行三维数值模拟,冷池边界为360℃,热池边界取490和516℃两种方案,数学模型采用RNGk-ε模型。与现有结果相比,由于考虑了对流换热,所得到的平均温度低于设计温度。China Experimental Fast Reactor（CEFR）is of pool-type,and the pool is divided into two plenums which are named hot plenum and cold plenum.Triplex horizontal thermal-shielding board,situated between hot plenum and cold plenum,is a cold boundary of hot plenum,and a hot boundary of cold plenum too.Thermal-hydraulic characteristic of the triplex horizontal thermal-shielding affects the temperature distribution of hot and cold plenums directly.The thermal-hydraulic characteristics of the 1/4 domain of the triplex horizontal thermal-shielding were numerically simulated when CEFR was in full power by using CFX 3-D program.The boundary temperature of cold plenum is 360℃,while hot plenum is 490℃or 516℃of two projects.The selected model is RNGk-εmodel.Compared with the results in existence,the gained average temperature is less than the designed temperature,for calculating convection heat transfer.

关 键 词：中国实验快堆 水平热屏蔽 热工流体 数值模拟 

分 类 号：TL33[核科学技术—核技术及应用]