Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions

Q3 Engineering

Strojnicky Casopis Pub Date : 2017-04-01 DOI:10.1515/scjme-2017-0009

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

引用次数: 3

Abstract

Abstract The paper presents the numerical simulation of thermo-hydraulic behaviour of coolant in the VVER- 440 nuclear reactor under standard outage conditions. Heating-up and flow of coolant between the reactor pressure vessel and spent fuel storage pool are discussed.

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VVER-440核反应堆换料条件下冷却剂的热水力特性

摘要本文对VVER- 440核反应堆在标准停堆条件下的冷却剂热水力特性进行了数值模拟。讨论了反应堆压力容器与乏燃料储存池之间冷却剂的加热和流动问题。

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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