Development of point model for recombiner and its validation with tests conducted in THAI facility using CFD

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-04-29 DOI:10.1016/j.nucengdes.2025.114100

Rupak Kumar Raman , R.S. Rao , Kannan N. Iyer , Sanjeev Gupta

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引用次数: 0

Abstract

A point model for a recombiner compatible for CFD code to simulate hydrogen distribution and mitigation in nuclear power plant containments is developed in this study. Given the significantly smaller size of the recombiner compared to containment compartments, fully resolving the recombination process requires detailed geometric modeling and a highly refined mesh within the recombiner channels, which require high computational demand. Present study simplifies the recombiner channel into a single computational node while ensuring conservation of momentum, energy and species to address the issue of computational demand. A set of correlations for pressure drop, heat generation and heat transfer coefficients has been developed for recombiner channel in the presence of a steam environment through parametric studies. This model is incorporated in CFD code FLUENT using UDF. Through various simulations the derived point model is verified under both steady-state and transient condition with the detailed computational model. Further validation is performed using CFD simulations of the HR-49, HR 2 and HR 5 tests from the THAI experiment program for various test conditions. The simulation with the point model successfully predicted the recombiner performance and species concentration with experimental data.

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基于CFD的重组器点模型的建立及其在泰国设备上的验证

本文建立了一个适用于CFD代码的重构器点模型，用于模拟核电站安全壳内氢气的分布和减缓。考虑到重组器的尺寸比隔离室小得多，完全解决重组过程需要详细的几何建模和重组通道内高度精细的网格，这需要很高的计算需求。本研究将重组通道简化为单个计算节点，同时保证动量、能量和物种守恒，以解决计算需求问题。通过参数化研究，建立了蒸汽环境下复合管道的压降、产热和换热系数的关系式。该模型使用UDF合并到CFD代码FLUENT中。通过各种模拟，用详细的计算模型验证了导出的点模型在稳态和瞬态条件下的正确性。进一步的验证使用CFD模拟了泰国实验项目中不同测试条件下的HR-49、HR 2和HR 5测试。利用点模型进行模拟，成功地预测了复合材料的性能和菌种浓度。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.