Wenchao Zhang , Qiaochen Du , Yue Wang , Benan Cai , Chao Liu , Lipeng Du , Weihua Cai
{"title":"Numerical simulation of flow and heat transfer characteristics of liquid lithium metal inside trapezoid shaped wire rod bundle channels","authors":"Wenchao Zhang , Qiaochen Du , Yue Wang , Benan Cai , Chao Liu , Lipeng Du , Weihua Cai","doi":"10.1016/j.anucene.2025.111667","DOIUrl":null,"url":null,"abstract":"<div><div>The advancement of compact reactor technology, including the development of small and liquid metal reactors, has led to a surge of interest in the concept of wire-wound core arrangements for achieving enhanced compactness. The installation of trapezoid shaped wires permits the fuel rods to support themselves, facilitates the heat transfer through the channels, and allows for a compact configuration. However, the presence of wires introduces a degree of complexity to the flow and heat transfer process, prompting to investigate the thermo-hydraulic properties of fuel rod bundles with wires. This paper presents a numerical analysis model of a fuel rod bundle channel with trapezoid shaped wires in a hexagonal arrangement, with the objective of investigating the influence of trapezoid shaped wires on the flow and heat transfer characteristics. The results indicate the presence of transverse flow within the channel. The transverse velocity at the near-wall surface of the fuel rod is in alignment with the twisting direction of trapezoid shaped wires, whereas at the top of the wires, it is in opposition to this direction. The center rod and the corner rod exhibit low temperatures and high convective heat transfer coefficients at the trapezoidal winding wire. The transverse and axial velocities demonstrate periodic fluctuations with a period of approximately <em>H/4</em>, and a comparable pattern is evident in the fluctuations of the hot spot factor (<em>F<sub>HS</sub></em>) and Nusselt number (<em>Nu</em>). It is observed that frictional resistance coefficient (<em>f</em>) and convective heat transfer coefficient (<em>h</em>) of trapezoid shaped wire rod bundle channels are higher than those of classical round rod bundle channels. The pertinent research findings furnish a theoretical foundation for the utilization of this specific fuel rod in lithium-cooled fast reactors.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111667"},"PeriodicalIF":2.3000,"publicationDate":"2025-06-18","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/S0306454925004840","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
The advancement of compact reactor technology, including the development of small and liquid metal reactors, has led to a surge of interest in the concept of wire-wound core arrangements for achieving enhanced compactness. The installation of trapezoid shaped wires permits the fuel rods to support themselves, facilitates the heat transfer through the channels, and allows for a compact configuration. However, the presence of wires introduces a degree of complexity to the flow and heat transfer process, prompting to investigate the thermo-hydraulic properties of fuel rod bundles with wires. This paper presents a numerical analysis model of a fuel rod bundle channel with trapezoid shaped wires in a hexagonal arrangement, with the objective of investigating the influence of trapezoid shaped wires on the flow and heat transfer characteristics. The results indicate the presence of transverse flow within the channel. The transverse velocity at the near-wall surface of the fuel rod is in alignment with the twisting direction of trapezoid shaped wires, whereas at the top of the wires, it is in opposition to this direction. The center rod and the corner rod exhibit low temperatures and high convective heat transfer coefficients at the trapezoidal winding wire. The transverse and axial velocities demonstrate periodic fluctuations with a period of approximately H/4, and a comparable pattern is evident in the fluctuations of the hot spot factor (FHS) and Nusselt number (Nu). It is observed that frictional resistance coefficient (f) and convective heat transfer coefficient (h) of trapezoid shaped wire rod bundle channels are higher than those of classical round rod bundle channels. The pertinent research findings furnish a theoretical foundation for the utilization of this specific fuel rod in lithium-cooled fast reactors.
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.