基于"一维系统+三维CFD"耦合方法的快堆非能动余热排出系统自然循环特性的数值模拟

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中文摘要：池式快堆采用了新型非能动堆内直接余热排出(DRACS)方式，提升了快堆的安全性。目前针对池式快堆自然循环开展的数值模拟研究中，系统程序难以准确预测池内复杂自然循环路径，难以准确模拟池内三维热工水力现象，如果采用三维CFD计算建模及网格划分难度较高，且所需计算资源较大。为此本文开发了"一维系统+三维CFD"耦合方法，用于快堆非能动余热排出系统自然循环特性计算分析。利用日本大型钠回路实验台架(PLANDTL)DRACS自然循环模式对该耦合方法进行验证，稳态工况关键位置参数相对误差小于3％，瞬态工况关键位置参数与实验值变化趋势吻合较好，相对误差小于10％，验证了该耦合方法的适用性和准确性。利用该耦合方法，开展了中国实验快堆(CEFR)自然循环及余热排出特性计算分析，识别了池内自然循环流动路径，揭示了池内温度分层以及盒间流现象。本文方法可为大型钠冷快堆自然循环三维瞬态特性分析提供重要数值方法。

外文标题：Numerical Simulation of Natural Circulation Characteristic of Fast Reactor Passive Decay Heat Removal System Based on "1-D System+3-D CFD" Coupled Method

外文摘要：The sodium-cooled fast reactor is one of the important reactor types of the fourth-generation advanced nuclear energy system.The safety of sodium-cooled fast reactors is improved by introducing a new passive decay heat removal system.The China Experimental Fast Reactor(CEFR)adopts the direct reactor auxiliary cooling system(DRACS)method.The passive decay heat removal system is directly installed in the primary loop,which can further improve the decay heat removal capability of the sodium-cooled fast reactor under accident conditions.However,due to the complex structure of the pool fast reactor and the special arrangement of the passive decay heat removal system,the innovative design of DRACS also brings about problems such as"multipath"of natural circulation.In the current numerical simulation research on the natural circulation of pool fast reactors,it is difficult for the system program to accurately predict the complex natural circulation paths in the pool,and it is difficult to accurately simulate the three-dimensional thermal and hydraulic phenomena in the pool,and the three-dimensional CFD computational modeling and meshing are more difficult.It is high and requires large computing resources.Combining the advantages and disadvantages of one-dimensional programs and three-dimensional CFD,this study developed a"1-D system+3-D CFD"coupled method for calculation and analysis of the natural circulation characteristics of the fast reactor passive decay heat removal system.The innovative method was verified using the DRACS natural circulation mode of Japan's large-scale sodium loop experimental bench(PLANDTL).The relative error of key position parameters under steady-state operating conditions is less than 3％.The change trend of key position parameters under transient operating conditions is in good agreement with the experimental values,the relative error is less than 10％.Which verifies the applicability and accuracy of the coupling method.Using this coupling method,calculation and analysis of the CEFR natural circulation and decay heat removal characteristics were carried out,the natural circulation flow path in the pool is identified,and the temperature stratification and"inter-wrapper flow"phenomenon in the pool are revealed,which are three-dimensional transient characteristics of the natural circulation of large sodium-cooled fast reactors.This coupled method can provide important numerical methods for the three-dimensional transient characteristics analysis of natural circulation in large sodium-cooled fast reactors.

外文关键词：

"1-D system+3-D CFD"coupled methodfast reactor passive decay heat removalnatural circulationdirect reactor auxiliary cooling system

作者：

陆道纲、宋海洁、郭劲松、赵海琦、张钰浩、隋丹婷

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作者单位：

华北电力大学核科学与工程学院,北京 102206

非能动核能安全技术北京市重点实验室,北京 102206

关键词：

"一维系统+三维CFD"耦合方法快堆非能动余热排出自然循环堆内直接余热排出系统

基金：

北京市科协青年人才托举工程河北省自然科学基金优秀青年基金中央高校基本科研业务费专项资金

项目编号：

BYESS2023091A20235020062023MS052

出版年：

2024

DOI：

10.7538/yzk.2024.youxian.0324

原子能科学技术

中国原子能科学研究院

原子能科学技术

CSTPCD北大核心

影响因子：0.372

ISSN：1000-6931

年,卷(期)：2024.58(9)