Numerical study on the characteristics of the LBE thermal stratification in a scaled-down hot pool

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2024-09-13 DOI:10.1016/j.anucene.2024.110900

Wenbo Li , Yunqing Bai , Danna Zhou , Wendong Li , Dajian Yu , Yang Li

{"title":"Numerical study on the characteristics of the LBE thermal stratification in a scaled-down hot pool","authors":"Wenbo Li , Yunqing Bai , Danna Zhou , Wendong Li , Dajian Yu , Yang Li","doi":"10.1016/j.anucene.2024.110900","DOIUrl":null,"url":null,"abstract":"<div>The thermal stratification in Lead-Based Reactors would pose a significant threat to safe operation. A numerical study is presented in this work to illustrate the effects of the Richardson number (Ri) and the Peclet number (Pe) on thermal stratification in a scaled-down hot pool of lead–bismuth eutectic (LBE). The results demonstrated the critical value of Ri for the emergence of thermal stratification was approximately 1. Moreover, when the flux Richardson number (Rif) was above 4, the temperature fluctuation at the thermal stratification interface was marginal. The interface ascending rate of thermal stratification was inversely proportional to Pe. Increasing Pe would intensify the temperature fluctuation. The dominant frequency of the temperature profile was 0.1 ∼ 1 Hz, implying a high possibility of thermal fatigue at the solid surface. The results of this work will be helpful for the design and optimization of thermohydraulic parameters in Lead-Based Reactors.</div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-09-13","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/S0306454924005632","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 thermal stratification in Lead-Based Reactors would pose a significant threat to safe operation. A numerical study is presented in this work to illustrate the effects of the Richardson number (Ri) and the Peclet number (Pe) on thermal stratification in a scaled-down hot pool of lead–bismuth eutectic (LBE). The results demonstrated the critical value of Ri for the emergence of thermal stratification was approximately 1. Moreover, when the flux Richardson number (Ri_f) was above 4, the temperature fluctuation at the thermal stratification interface was marginal. The interface ascending rate of thermal stratification was inversely proportional to Pe. Increasing Pe would intensify the temperature fluctuation. The dominant frequency of the temperature profile was 0.1 ∼ 1 Hz, implying a high possibility of thermal fatigue at the solid surface. The results of this work will be helpful for the design and optimization of thermohydraulic parameters in Lead-Based Reactors.

查看原文本刊更多论文

缩小热池中 LBE 热分层特征的数值研究

铅基反应堆中的热分层将对安全运行构成重大威胁。本研究通过数值研究说明了理查森数（Ri）和佩克莱特数（Pe）对铅铋共晶（LBE）缩比热池中热分层的影响。结果表明，出现热分层的临界值 Ri 约为 1。此外，当通量理查森数（Rif）大于 4 时，热分层界面的温度波动很小。热分层的界面上升速率与 Pe 成反比。增加 Pe 会加剧温度波动。温度曲线的主频为 0.1 ∼ 1 Hz，这意味着固体表面发生热疲劳的可能性很高。这项工作的结果将有助于铅基反应器热液压参数的设计和优化。

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 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.