原子能机构研究堆冷却剂通道多重堵塞的CFD分析

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-09-03 DOI:10.1016/j.anucene.2025.111839

Muhammad Abdullah, Muhammad Nadeem, Arif, Adnan Hamid

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引用次数: 0

摘要

本研究的目的是对国际原子能机构10mw材料试验堆在冷却剂通道流动堵塞情况下的设计安全性进行分析。越来越多地使用研究反应堆以及国际原子能机构制定的更加严格的管理和操作安全标准，导致越来越多地依赖于在稳态和瞬态条件下对电厂现象的更现实的模拟。该研究将阻塞建模为长方体，在冷却剂通道的入口和中间有六种不同的组合，阻塞率为80%。分析了所有堵塞情况下的速度和温度分布。据报道，无堵塞情况下的温度为348 K。与此相比，入口-底部-中底堵塞通道的最高温度提高了11.12%，达到389 K。由于热应力的结构分析也被执行，以确保反应堆的完整性，因为堵塞影响包层温度。此外，包层材料需要107个热循环才能失效。

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Analysis of multiple blockages in a coolant channel of IAEA research reactor using CFD

The aim of this study is to perform a design safety analysis of the IAEA 10 MW material testing reactor under flow blockage of coolant channels. Increased use of research reactors along with enhanced regulatory and operational safety standards set by the International Atomic Energy Agency has led to an increased reliance on more realistic simulations of plant phenomena under both steady-state and transient conditions. The study models the blockage as cuboids, having an 80% blockage ratio at the inlet and middle of the coolant channel with six different combinations. The velocity and temperature profiles for all the cases of blockage have been analyzed. The temperature in the no-blockage case is reported to be 348 K. Compared to this, the maximum temperature in the case of the blocked channel is increased by 11.12% to a value of 389 K in the case of inlet-bottom-middle-bottom blockage. Structural analysis due to the thermal stresses is also performed to ensure the integrity of the reactor as the blockages affect the cladding temperature. Moreover,

1 0^{7}

thermal cycles are required for the cladding material to fail.

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.