摘要
为了支持压水堆数字反应堆中栅元级核热耦合模拟,基于中国核动力研究设计院研发的反应堆多物理耦合框架MORE研制了堆芯栅元级核热耦合计算系统,其中采用堆芯细网输运计算模块CORCA-SPn求解三维SP3方程,采用三种堆芯热工水力计算模块CORTH、CORTH-R、TH1D求解通道内流动换热和燃料导热方程。并对华龙一号堆芯和压水堆栅元级耦合例题COPHP进行栅元级核热耦合计算,可提供栅元尺度的功率、冷却剂温度、燃料温度等计算结果。该耦合系统为棒/平板元件压水堆堆芯多种精度需求的数字反应堆模拟提供了有效工具。
In order to support the simulation of pin-by-pin wise coupling between neutronics and thermal-hydraulic in pressurized water reactor(PWR)digital reactors,a full core pin-by-pin wise neutronics thermal-hydraulic coupling calculation system was developed based on the multi physics coupling framework MORE developed by Nuclear Power Institute of China(NPIC).The core fine mesh transport calculation module CORCA-SPn was used to solve the three-dimensional SP3 equation,and three thermal-hydraulic calculation modules CORTH,CORTH-R,and TH1D were used to solve the flow and heat transfer equations and fuel thermal conductivity equations in the channel.And conduct pin-by-pin wise neutronics thermal-hydraulic coupling calculations for the core of HPR1000 and COPHP,which can provide pin-by-pin wise power,coolant temperature,fuel temperature,and other calculation results.This coupling system provides an effective tool for digital reactor simulation of rod/plate element pressurized water reactor cores with various precision requirements.
作者
李治刚
赵文博
潘俊杰
强胜龙
夏榜样
方超
芦韡
汤琪芬
Li Zhigang;Zhao Wenbo;Pan Junjie;Qiang Shenglong;Xia Bangyang;Fang Chao;Lu Wei;Tang Qifen(Nuclear Power Design and Research Institute,Chengdu 610041,China;Science and Technology on Reactor System Design Technology Laboratory,Chengdu 610041,China)
出处
《电子技术应用》
2024年第S01期223-229,共7页
Application of Electronic Technique
关键词
多物理耦合框架
栅元级核热耦合
标准接口
基准题
multi physical coupling framework
pin-by-pin wise coupling between neutronics and thermalhydraulic
standard interface
benchmark
