Yihu Wang , Ziang Guo , Tenglong Cong , Limin Liu , Hanyang Gu
{"title":"Investigation on coupling methods for heat transfer field between a reactor core and heat pipes","authors":"Yihu Wang , Ziang Guo , Tenglong Cong , Limin Liu , Hanyang Gu","doi":"10.1016/j.anucene.2025.111632","DOIUrl":null,"url":null,"abstract":"<div><div>Heat pipe reactors are inherently safe, compact, and capable of providing a reliable energy supply for remote areas. Heat pipe reactors are often designed as solid-state reactors, enabling the analysis of the reactor through the integration of multiple coupled physical fields. This paper proposes a numerical method that uses the equivalent convective coefficient to solve the coupled heat transfer problem between the reactor core and heat pipes under steady-state conditions. This method effectively reduces the number of iterations and accounts for the uneven heat absorption effects of the heat pipes at the corner and side channels on the azimuthal direction. In this study, an open-source code <em>Multiphysics Object-Oriented Simulation Environment</em> (<em>MOOSE</em> for short) is used to implement the numerical method. The findings will support the coupling analysis procedure of a heat pipe reactor core and heat pipes.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111632"},"PeriodicalIF":1.9000,"publicationDate":"2025-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925004499","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
Heat pipe reactors are inherently safe, compact, and capable of providing a reliable energy supply for remote areas. Heat pipe reactors are often designed as solid-state reactors, enabling the analysis of the reactor through the integration of multiple coupled physical fields. This paper proposes a numerical method that uses the equivalent convective coefficient to solve the coupled heat transfer problem between the reactor core and heat pipes under steady-state conditions. This method effectively reduces the number of iterations and accounts for the uneven heat absorption effects of the heat pipes at the corner and side channels on the azimuthal direction. In this study, an open-source code Multiphysics Object-Oriented Simulation Environment (MOOSE for short) is used to implement the numerical method. The findings will support the coupling analysis procedure of a heat pipe reactor core and heat pipes.
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.