首页|基于MOOSE平台的西安脉冲反应堆多物理耦合计算研究

基于MOOSE平台的西安脉冲反应堆多物理耦合计算研究

Study on Multi-physics Coupling Calculation of Xi'an Pulsed Reactor Based on MOOSE Platform

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反应堆中涉及一系列复杂相互作用的多物理耦合过程,随着高性能计算技术的迅速发展,基于多物理耦合的分析越来越受到重视.基于多物理耦合平台MOOSE开展了西安脉冲反应堆的稳态和瞬态多物理耦合计算研究,综合应用Picard迭代和Jacobian Free Newton-Krylov(JFNK)方法处理多物理耦合中的非线性问题,实现了三维中子扩散时空动力学、三维固体导热和一维流体流动传热的多物理耦合计算,计算了西安脉冲反应堆2MW稳态运行和3.45$(1$表示一个有效缓发中子份额)脉冲运行条件下的反应堆行为,得到了堆芯三维功率和温度分布计算结果,计算结果与实验结果符合较好,证明了多物理耦合的正确性.开发的多物理耦合计算方法具有几何适应性好、耦合灵活等特点,具有应用于其他小型反应堆的潜力.
Nuclear reactors involve a series of multi-physics coupling processes with complex interactions.With the rapid development of high-performance computing technology,the analysis based on multi-physics coupling has been paid more and more attention.Based on the multi-physics coupling platform MOOSE,the steady-state and transient multi-physics coupling simulation of Xi'an pulsed reactor is studied.The nonlinear problems in multi-physics coupling are solved by Picard iteration and Jacobian Free Newton-Krylov(JFNK)method,and the multi-physical coupling calculation of three-dimensional neutron spatio-temporal dynamics,three-dimensional solid heat conduction and one-dimensional fluid flow and heat transfer is realized.The reactor behavior under 2 MW steady-state operation and 3.45$(1$ represents an effective delayed neutron fraction)pulse operation of Xi'an pulsed reactor is calculated,and the three-dimensional power and temperature distribution of the core are obtained.The calculated results are in good agreement with the experimental results,which proves the correctness of multi-physics coupling.The multi-physics coupling method developed in this paper has the advantages of good geometric adaptability and flexible coupling,and has the potential to be applied to other micro reactors.

Multi-physics couplingXi'an Pulsed ReactorMOOSESteady-state analysisTransient-state analysis

胡田亮、姜夺玉、张信一、王召浩、王立鹏、曹璐、李达、陈立新

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西北核技术研究所强脉冲辐射环境模拟与效应国家重点实验室,西安,710024

西安交通大学,西安,710049

多物理耦合 西安脉冲反应堆 MOOSE 稳态分析 瞬态分析

国家自然科学基金项目国家自然科学基金项目

1220523712275219

2024

核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
年,卷(期):2024.45(3)