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Realistic CFD simulation of HTR-10 reactor using a face centred cubic column

机译:使用面心立方柱对HTR-10反应堆进行逼真的CFD模拟

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摘要

High-temperature gas-cooled reactors (HTGRs) have the potential to be used as possible energy generation sources in the near future, owing to their inherently safe performance, low power density design, and high conversion efficiency. However, safety is the most important issue for its commercialisation in the nuclear energy industry. The research of the thermal-hydraulic characteristics is very important for safe design and operation of an HTGR. In this article, the thermal-hydraulic simulation of compressible flow inside the core of the pebble bed reactor HTR-10 (High Temperature Reactor) using Computational Fluid Dynamics (CFD) is described. The realistic approach was considered, where every closely packed pebble is realistically modelled considering a graphite layer and sphere of fuel. Owing to the high computational cost it is impossible to simulate the full core; therefore, the geometry used is an FCC (Face Centred Cubic) cell with the total height of the core, with 41 layers of pebbles and 82 full pebbles. The input data used were taken from the thermal-hydraulic IAEA Benchmark. The results show the profiles of temperature of the coolant in the core, and the temperature distribution inside the pebbles. The maximum temperatures in the pebbles do not exceed the allowable limit for this type of nuclear fuel. The obtained results are consistent with the results of other authors using other simulation techniques and models.
机译:高温气冷堆(HTGR)由于其固有的安全性能,低功率密度设计和高转换效率,在不久的将来有可能被用作可能的能源产生源。然而,安全是其在核能工业中商业化的最重要问题。热工液压特性的研究对于高温气冷堆的安全设计和运行非常重要。在本文中,描述了使用计算流体动力学(CFD)对卵石床反应器HTR-10(高温反应堆)堆芯内部的可压缩流动进行热工水力模拟。考虑了现实的方法,其中每个紧密堆积的卵石均以石墨层和燃料球为现实模型。由于高昂的计算成本,无法模拟整个内核。因此,所使用的几何形状是FCC(面心立方)单元,其芯的总高度为41个卵石层和82个全卵石。所使用的输入数据取自IAEA热工液压基准。结果显示了堆芯中冷却剂的温度分布以及卵石内部的温度分布。卵石中的最高温度不超过此类核燃料的允许极限。获得的结果与使用其他模拟技术和模型的其他作者的结果一致。

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    Instituto Federal de Educacao, Ciencia e Tecnologia da Bahia Av. Amazonas, 3150, Bairro Zabele 45075-26, Vitoria da Conquista, BA, Brazil and Programa de Pos-graduacao em Modelagem Computacional, Universidade Estadual de Santa Cruz Rodovia Jorge Amado, Km 16, Salobrinho, 45662-900 Ilheus, BA, Brazil;

    Instituto Superior de Tecnologias y Ciencias Aplicadas (InSTEC), Av. Salvador Allende y Luaces, La Habana, 10400, Cuba and Departamento de Energia Nuclear, Universidade Federal de Pernambuco (UFPE), Av. Luiz Freire 1000, Cid. Universitaria, Recife, Brazil;

    Programa de Pos-graduacao em Modelagem Computacional, Universidade Estadual de Santa Cruz Rodovia Jorge Amado, Km 16, Salobrinho, 45662-900 Ilheus, BA, Brazil;

    Instituto Superior de Tecnologias y Ciencias Aplicadas (InSTEC), Av. Salvador Allende y Luaces, La Habana, 10400, Cuba;

    Departamento de Energia Nuclear, Universidade Federal de Pernambuco (UFPE), Av. Luiz Freire 1000, Cid. Universitaria, Recife, Brazil;

    Departamento de Energia Nuclear, Universidade Federal de Pernambuco (UFPE), Av. Luiz Freire 1000, Cid. Universitaria, Recife, Brazil;

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  • 正文语种 eng
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  • 关键词

    very high temperature reactor; pebble bed reactor; HTR-10; CFD;

    机译:高温反应堆;卵石床反应器HTR-10;差价合约;

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