VVER 440核反应堆降流器CFD分析

Q3 Engineering Strojnicky Casopis Pub Date : 2016-11-01 DOI:10.1515/scjme-2016-0018

V. Kutǐs, J. Jakubec, Juraj Paulech, Gálik Gálik, T. Sedlár

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引用次数: 10

摘要

摘要本文对VVER 440核反应堆冷却剂流动进行了CFD分析。分析的目的是研究孔口直径对反应堆堆芯内单个燃料组件质量流动的影响。在核电站运行过程中，节流孔的直径是可以改变的。所考虑的边界条件在冷却剂的研究区域是基于核反应堆VVER 440的标称冷却剂流动条件。

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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CFD Analysis of Downcomer of Nuclear Reactor VVER 440

Abstract The paper is focused on CFD analyses of the coolant flow in the nuclear reactor VVER 440. The goal of the analyses is to investigate the influence of the orifice diameter on the mass flow through individual fuel assemblies in the reactor core. The diameter of orifice can be changed during the operation of a nuclear power plant. Considered boundary conditions in the investigated region of the coolant are based on nominal coolant flow conditions in the nuclear reactor VVER 440.

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