旁通对VVER440燃料组件热工水力学的影响

Q3 Engineering

Strojnicky Casopis Pub Date : 2017-04-01 DOI:10.1515/scjme-2017-0007

J. Jakubec, Juraj Paulech, V. Kutǐs, G. Galik

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引用次数: 1

摘要

摘要本文研究了核反应堆VVER440燃料组件内冷却剂流动的CFD建模和模拟。研究了旁通冷却液流量对燃料组件出口温度分布和压降的影响。只进行了稳态分析。边界条件基于操作条件。选择ANSYS CFX作为主要的CFD软件工具，在其中执行所有分析。

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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Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly

Abstract The paper deals with CFD modelling and simulation of coolant flow within the nuclear reactor VVER 440 fuel assembly. The influence of coolant flow in bypass on the temperature distribution at the outlet of the fuel assembly and pressure drop was investigated. Only steady-state analyses were performed. Boundary conditions are based on operating conditions. ANSYS CFX is chosen as the main CFD software tool, where all analyses are performed.

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来源期刊

Strojnicky Casopis Engineering-Mechanical Engineering

CiteScore

2.00

自引率

0.00%

发文量

审稿时长

14 weeks