BORA4-PTS: Experimental reproduction of a Pressurized Thermal Shock, and building of numerical simulation with the CATHARE Code

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-07-31 DOI:10.1016/j.nucengdes.2024.113497
{"title":"BORA4-PTS: Experimental reproduction of a Pressurized Thermal Shock, and building of numerical simulation with the CATHARE Code","authors":"","doi":"10.1016/j.nucengdes.2024.113497","DOIUrl":null,"url":null,"abstract":"<div><p>When a break occurs in a nuclear reactor, a fast cooldown has to be down to prevent the melting of the core. This is done by the injection of cold water at 7 °C, in a pressurized vessel at 295 °C. This is a Pressurized Thermal Shock. To improve the safety of the nuclear reactor, an experimental facility was built to analyze the mix of hot and cold water in the downcomer of the vessel. This is the BORA4-PTS experiment. Salt water at 45 °C is injected into stagnant pure water at 20 °C, to represent the injection of cold water in hot water. Through this experiment, a scaling was establish to compare it with the reactor case. We then made a numerical simulation of this experimental facility with the CATHARE code. With this simulation come another scaling, in order to properly compare the numerical and the experimental results. The numerical simulations give results that are very similar to the experimental ones. With this experiment, we show the excellent capacity of CATHARE to simulate and model the complex thermohydraulic inside a downcomer.</p></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-07-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S0029549324005971/pdfft?md5=524c6451272a42ca4fad2a626c6251ef&pid=1-s2.0-S0029549324005971-main.pdf","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549324005971","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

When a break occurs in a nuclear reactor, a fast cooldown has to be down to prevent the melting of the core. This is done by the injection of cold water at 7 °C, in a pressurized vessel at 295 °C. This is a Pressurized Thermal Shock. To improve the safety of the nuclear reactor, an experimental facility was built to analyze the mix of hot and cold water in the downcomer of the vessel. This is the BORA4-PTS experiment. Salt water at 45 °C is injected into stagnant pure water at 20 °C, to represent the injection of cold water in hot water. Through this experiment, a scaling was establish to compare it with the reactor case. We then made a numerical simulation of this experimental facility with the CATHARE code. With this simulation come another scaling, in order to properly compare the numerical and the experimental results. The numerical simulations give results that are very similar to the experimental ones. With this experiment, we show the excellent capacity of CATHARE to simulate and model the complex thermohydraulic inside a downcomer.

查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
BORA4-PTS:加压热冲击实验再现,利用 CATHARE 代码建立数值模拟
当核反应堆发生破裂时,必须快速降温以防止堆芯熔化。具体做法是在 295 °C 的加压容器中注入 7 °C 的冷水。这就是加压热冲击。为了提高核反应堆的安全性,建造了一个实验设施来分析容器导流管中冷热水的混合情况。这就是 BORA4-PTS 实验。温度为 45 °C 的盐水被注入温度为 20 °C 的静止纯水中,以表示在热水中注入冷水。通过该实验,我们建立了一个比例尺,并将其与反应堆情况进行了比较。然后,我们使用 CATHARE 代码对该实验设施进行了数值模拟。为了正确比较数值结果和实验结果,我们又对模拟结果进行了缩放。数值模拟的结果与实验结果非常相似。通过这次实验,我们展示了 CATHARE 在模拟和模拟导流筒内复杂热流体力学方面的卓越能力。
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 去求助
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.
期刊最新文献
Monte Carlo multiphysics simulation on adaptive unstructured mesh geometry A novel method of estimating earthquake durations for the analysis of floor vibrations of nuclear power plants Strategic fuel management via implementation of a combined reload-reshuffle scheme in small modular reactors Vibrations of PWR fuel assembly under axial coolant flow and oblique impingement of jet cross-flow from LOCA holes Pareto front of sodium void worth and breeding ratio in metal-fueled sodium fast reactor with axially heterogeneous core design by coupling neutronics and genetic algorithm
×
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
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 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 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1