Numerical simulation for the thermal behavior of three-layer molten pool based on TROSE experiment

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Lian Chen , Zongyang Li , Kun Han , Chengcheng Deng , Xicheng Wang
{"title":"Numerical simulation for the thermal behavior of three-layer molten pool based on TROSE experiment","authors":"Lian Chen ,&nbsp;Zongyang Li ,&nbsp;Kun Han ,&nbsp;Chengcheng Deng ,&nbsp;Xicheng Wang","doi":"10.1016/j.nucengdes.2025.114508","DOIUrl":null,"url":null,"abstract":"<div><div>In advancing the study of the In-Vessel Retention (IVR) strategy, a three-layer corium pool configuration has been proposed. Owing to density inversion and the thinning of the top metallic layer, the thermal focusing effect on the vessel sidewall becomes more pronounced, posing a higher risk to Reactor Pressure Vessel (RPV) integrity. To investigate the thermal behavior of this configuration, Computational Fluid Dynamics (CFD) simulations were conducted based on the TROSE experiment, which features a three-dimensional hemispherical vessel (diameter = 2.4 m) and employs mineral oil, water, and Cerrobend alloy as simulants. The results demonstrate that the Wall-Modeled Large Eddy Simulation (WMLES) turbulence model effectively captures the corium pool behavior under a Rayleigh number of 10<sup>15</sup>. Additionally, assuming only energy exchange (without mass transfer) across the interfacial boundaries is shown to be a reasonable simplification that improves computational efficiency. In Test-T3 of the TROSE experiment, strong natural convection in the light metallic layer produces a nearly uniform temperature field, whereas limited convection in the oxidic layer leads to significant thermal stratification. In the heavy metallic layer, heat transfer is dominated by conduction, accompanied by crust formation at the boundaries. These findings confirm the applicability of the CFD method for simulating three-layer molten pools and highlight its potential for future safety analyses in large-scale passive nuclear power plants.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114508"},"PeriodicalIF":2.1000,"publicationDate":"2025-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325006855","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

In advancing the study of the In-Vessel Retention (IVR) strategy, a three-layer corium pool configuration has been proposed. Owing to density inversion and the thinning of the top metallic layer, the thermal focusing effect on the vessel sidewall becomes more pronounced, posing a higher risk to Reactor Pressure Vessel (RPV) integrity. To investigate the thermal behavior of this configuration, Computational Fluid Dynamics (CFD) simulations were conducted based on the TROSE experiment, which features a three-dimensional hemispherical vessel (diameter = 2.4 m) and employs mineral oil, water, and Cerrobend alloy as simulants. The results demonstrate that the Wall-Modeled Large Eddy Simulation (WMLES) turbulence model effectively captures the corium pool behavior under a Rayleigh number of 1015. Additionally, assuming only energy exchange (without mass transfer) across the interfacial boundaries is shown to be a reasonable simplification that improves computational efficiency. In Test-T3 of the TROSE experiment, strong natural convection in the light metallic layer produces a nearly uniform temperature field, whereas limited convection in the oxidic layer leads to significant thermal stratification. In the heavy metallic layer, heat transfer is dominated by conduction, accompanied by crust formation at the boundaries. These findings confirm the applicability of the CFD method for simulating three-layer molten pools and highlight its potential for future safety analyses in large-scale passive nuclear power plants.
基于TROSE实验的三层熔池热行为数值模拟
为了推进容器内保留(IVR)策略的研究,提出了一种三层堆芯池结构。由于密度反转和顶部金属层变薄,容器侧壁的热聚焦效应变得更加明显,对反应堆压力容器(RPV)的完整性构成更高的风险。为了研究这种结构的热行为,基于TROSE实验进行了计算流体动力学(CFD)模拟,该实验采用三维半球形容器(直径= 2.4 m),并使用矿物油、水和Cerrobend合金作为模拟物。结果表明,壁式大涡模拟(WMLES)湍流模型能有效地捕捉到瑞利数为1015时堆芯熔池的行为。此外,假设只有能量交换(没有传质)跨界面边界被证明是一个合理的简化,提高了计算效率。在TROSE实验的Test-T3中,轻金属层强烈的自然对流产生了一个几乎均匀的温度场,而氧化层有限的对流导致了明显的热分层。在重金属层中,传热以传导为主,边界处伴有结壳形成。这些发现证实了CFD方法在模拟三层熔池中的适用性,并突出了其在未来大型被动核电站安全分析中的潜力。
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
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
×
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