Thermal resistance evolution of NiFe2O4 particle deposition on nuclear fuel rods during subcooled boiling heat transfer

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yu Zhao, Zhizhong Tan, Jian Zheng
{"title":"Thermal resistance evolution of NiFe2O4 particle deposition on nuclear fuel rods during subcooled boiling heat transfer","authors":"Yu Zhao,&nbsp;Zhizhong Tan,&nbsp;Jian Zheng","doi":"10.1016/j.anucene.2025.111881","DOIUrl":null,"url":null,"abstract":"<div><div>The accumulation of particulate fouling deposition on nuclear fuel rod surfaces critically impacts reactor safety, operational stability, and economic efficiency. This study presents a numerical investigation of NiFe<sub>2</sub>O<sub>4</sub> particulate deposition on nuclear fuel rods. The framework integrates ANSYS FLUENT’s Discrete Phase Model (DPM) with customized deposition algorithms to resolve particle-laden flow dynamics and fouling mechanisms. Additionally, Boiling surface deposition dynamics were rigorously investigated through coupled Lee phase-change modeling and three-dimensional VOF interfacial tracking. Numerical results exhibit excellent agreement with experimental measurements, validating the model’s predictive accuracy. NiFe<sub>2</sub>O<sub>4</sub> particulate fouling exhibits significantly higher deposition propensity under pressurized water reactor (PWR) conditions. Parametric analysis reveals accelerated convergence to equilibrium fouling resistance with elevated flow velocities and larger particle diameters. The fouling resistance asymptotic value directly correlates with flow rate reduction and particle size increase. Boiling-induced vapor bubble nucleation suppresses deposition efficiency through microconvection effects, extending stabilization periods compared to non-boiling conditions.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111881"},"PeriodicalIF":2.3000,"publicationDate":"2025-09-15","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/S030645492500698X","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 accumulation of particulate fouling deposition on nuclear fuel rod surfaces critically impacts reactor safety, operational stability, and economic efficiency. This study presents a numerical investigation of NiFe2O4 particulate deposition on nuclear fuel rods. The framework integrates ANSYS FLUENT’s Discrete Phase Model (DPM) with customized deposition algorithms to resolve particle-laden flow dynamics and fouling mechanisms. Additionally, Boiling surface deposition dynamics were rigorously investigated through coupled Lee phase-change modeling and three-dimensional VOF interfacial tracking. Numerical results exhibit excellent agreement with experimental measurements, validating the model’s predictive accuracy. NiFe2O4 particulate fouling exhibits significantly higher deposition propensity under pressurized water reactor (PWR) conditions. Parametric analysis reveals accelerated convergence to equilibrium fouling resistance with elevated flow velocities and larger particle diameters. The fouling resistance asymptotic value directly correlates with flow rate reduction and particle size increase. Boiling-induced vapor bubble nucleation suppresses deposition efficiency through microconvection effects, extending stabilization periods compared to non-boiling conditions.
过冷沸腾换热过程中NiFe2O4颗粒沉积在核燃料棒上的热阻演变
颗粒结垢沉积在核燃料棒表面的累积严重影响反应堆的安全性、运行稳定性和经济效益。本文对NiFe2O4颗粒在核燃料棒上的沉积进行了数值研究。该框架将ANSYS FLUENT的离散相模型(DPM)与定制的沉积算法集成在一起,以解决颗粒负载的流动动力学和结垢机制。此外,通过耦合Lee相变模型和三维VOF界面跟踪,对沸腾表面沉积动力学进行了严格的研究。数值结果与实验测量结果非常吻合,验证了模型的预测精度。在压水堆(PWR)条件下,NiFe2O4颗粒污染表现出更高的沉积倾向。参数分析表明,随着流速的增大和颗粒直径的增大,向平衡结垢阻力的收敛速度加快。阻垢阻力渐近值与流量减小和粒径增大直接相关。沸腾诱导的汽泡成核通过微对流效应抑制了沉积效率,与非沸腾条件相比延长了稳定期。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
来源期刊
Annals of Nuclear Energy
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.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信