摘要
本文为计算和分析钠冷快堆自然循环组件的热工水力特性,开发了钠冷快堆堆芯自然循环冷却组件子通道分析程序。基于61棒单组件模型,通过将本程序的结果与COBRA程序进行比较,验证了钠冷快堆堆芯自然循环冷却组件子通道分析程序对自然循环冷却组件的适用性。基于多盒组件模型,初步验证了本程序具备自然循环冷却组件的流量分配和盒间换热计算的功能。本程序能为池式快堆自然循环冷却组件提供有效的设计和分析工具。
In order to calculate and study thermal-hydraulic characteristics of natural convection assembly(NCA)of sodium cooled fast reactor(SFR),a sub-channel code was developed in the paper.Based on a single assembly model with 61 rods,the applicability of the developed sub-channel code to NCA was validated by comparison with COBRA code.Based on a multi-assembly model,the automatic flow distribution model and the inter-assembly heat transfer model of the code were preliminarily validated.This code will provide an effective design and analysis tool for NCA of SFR.
作者
林超
杨红义
周志伟
LIN Chao;YANG Hongyi;ZHOU Zhiwei(Division of Reactor Engineering Technology Research,China Institute of Atomic Energy,Beijing 102413,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2021年第3期423-431,共9页
Atomic Energy Science and Technology
关键词
钠冷快堆
自然循环组件
子通道分析
sodium cooled fast reactor
natural convection assembly
sub-channel analysis