利用OpenFOAM对核工程中过冷流动沸腾进行数值模拟

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
Kerntechnik Pub Date : 2023-03-17 DOI:10.1515/kern-2022-0112
Zhi Yang, J. Herb
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引用次数: 0

摘要

摘要本工作的重点是利用计算流体力学(CFD)代码OpenFOAM开发和验证核工程应用中壁沸腾模拟的模型和方法。新的chtMultiRegionReactingTwoPhaseEulerFoam求解器是在OpenFOAM Foundation version 7的reactingTwoPhaseEulerFoam求解器的基础上开发的。利用该求解器对考虑壁面沸腾和固体结构与两相流体区域之间的共轭传热的两相流动进行了模拟。采用欧拉-欧拉法求解两相流。采用扩展的Rensselaer理工学院壁面热流分配模型计算壁面沸腾过程的热流密度,其中考虑了固体壁面与高空隙率两相流之间的对流热流密度。求解器根据OECD/NEA压水堆子通道和束测试基准的实验数据进行了验证。这个核能公司(NUPEC)数据库提供了不同热工条件下不同燃料组件子通道几何形状的数据。利用chtMultiRegionReactingTwoPhaseEulerFoam求解器对基准练习I-1中不同边界条件下的10个实验运行进行了模拟。求解器在所有测试的情况下都表现出良好的数值稳定性,在不同的沸腾状态下,截面平均孔隙分数高达0.6。研究结果与实测数据进行了比较,得到了所研究几何孔隙分数截面上的平均值。与实验数据吻合较好。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM
Abstract This work is focused on the development and validation of models and methods for the simulation of wall boiling in nuclear engineering applications with the computational fluid dynamics (CFD) code OpenFOAM. The new chtMultiRegionReactingTwoPhaseEulerFoam solver was developed based on the reactingTwoPhaseEulerFoam solver of OpenFOAM Foundation version 7. The solver is used for the simulation of two-phase flow under consideration of wall boiling and conjugate heat transfer (CHT) between solid structure and two-phase fluid regions. The Euler–Euler approach for two-phase flows was used. The heat flux during wall boiling was calculated with the help of the extended Rensselaer Polytechnic Institute wall heat flux partitioning model, in which the convective heat flux between solid wall and two-phase flow with high void fractions was also considered. The solver was validated against experimental data from the OECD/NEA PWR Subchannel and Bundle Tests benchmark. This Nuclear Power Energy Corporation (NUPEC) database provides data for different fuel assembly subchannel geometries at different thermal-hydraulic conditions. 10 experimental runs with different boundary conditions of the benchmark exercise I-1 were simulated with the chtMultiRegionReactingTwoPhaseEulerFoam solver. The solver showed good numerical stability in all examined cases, which captured different boiling regimes with up to cross-section averaged void fractions of 0.6. The results were compared with measured data for the averaged over the cross-section of the investigated geometry void fractions. Good agreement with experimental data was observed.
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来源期刊
Kerntechnik
Kerntechnik 工程技术-核科学技术
CiteScore
0.90
自引率
20.00%
发文量
72
审稿时长
6-12 weeks
期刊介绍: Kerntechnik is an independent journal for nuclear engineering (including design, operation, safety and economics of nuclear power stations, research reactors and simulators), energy systems, radiation (ionizing radiation in industry, medicine and research) and radiological protection (biological effects of ionizing radiation, the system of protection for occupational, medical and public exposures, the assessment of doses, operational protection and safety programs, management of radioactive wastes, decommissioning and regulatory requirements).
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