用RELAP5/MOD3.2计算机代码模拟过冷沸腾实验

IF 0.6 4区 工程技术 Q4 Engineering Nuclear Engineering International Pub Date : 1998-11-15 DOI:10.1115/imece1998-1133
S. Hari, Y. Hassan, J. Tu
{"title":"用RELAP5/MOD3.2计算机代码模拟过冷沸腾实验","authors":"S. Hari, Y. Hassan, J. Tu","doi":"10.1115/imece1998-1133","DOIUrl":null,"url":null,"abstract":"\n The results of a low-pressure subcooled flow boiling experiment simulated with the RELAP5/MOD3.2 thermal-hydraulic computer program are presented. The objective of the present study is to assess the suitability of application of the RELAP5 computer program for the thermal hydraulic safety analysis of research reactors. These reactors as the High Flux Australian reactor HIFAR operate at near-atmospheric pressures with upward forced convective flow. Subcooled boiling phenomenon plays an important role in the heat transfer aspects of this reactor. It is found that the void fraction profile predicted by the code for the various experimental conditions differ considerably from the experimental results.","PeriodicalId":49736,"journal":{"name":"Nuclear Engineering International","volume":null,"pages":null},"PeriodicalIF":0.6000,"publicationDate":"1998-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"2","resultStr":"{\"title\":\"Simulation of a Subcooled Boiling Experiment Using RELAP5/MOD3.2 Computer Code\",\"authors\":\"S. Hari, Y. Hassan, J. Tu\",\"doi\":\"10.1115/imece1998-1133\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"\\n The results of a low-pressure subcooled flow boiling experiment simulated with the RELAP5/MOD3.2 thermal-hydraulic computer program are presented. The objective of the present study is to assess the suitability of application of the RELAP5 computer program for the thermal hydraulic safety analysis of research reactors. These reactors as the High Flux Australian reactor HIFAR operate at near-atmospheric pressures with upward forced convective flow. Subcooled boiling phenomenon plays an important role in the heat transfer aspects of this reactor. It is found that the void fraction profile predicted by the code for the various experimental conditions differ considerably from the experimental results.\",\"PeriodicalId\":49736,\"journal\":{\"name\":\"Nuclear Engineering International\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.6000,\"publicationDate\":\"1998-11-15\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"2\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering International\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://doi.org/10.1115/imece1998-1133\",\"RegionNum\":4,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"Engineering\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering International","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1115/imece1998-1133","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"Engineering","Score":null,"Total":0}
引用次数: 2

摘要

本文介绍了利用RELAP5/MOD3.2热液计算机程序模拟低压过冷沸腾实验的结果。本研究的目的是评估RELAP5计算机程序应用于研究堆热水力安全分析的适用性。这些反应堆,如高通量澳大利亚反应堆HIFAR,在近大气压力下运行,向上强迫对流。过冷沸腾现象在该反应器的传热方面起着重要作用。结果表明,在不同的实验条件下,程序预测的孔隙率分布与实验结果存在较大差异。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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
Simulation of a Subcooled Boiling Experiment Using RELAP5/MOD3.2 Computer Code
The results of a low-pressure subcooled flow boiling experiment simulated with the RELAP5/MOD3.2 thermal-hydraulic computer program are presented. The objective of the present study is to assess the suitability of application of the RELAP5 computer program for the thermal hydraulic safety analysis of research reactors. These reactors as the High Flux Australian reactor HIFAR operate at near-atmospheric pressures with upward forced convective flow. Subcooled boiling phenomenon plays an important role in the heat transfer aspects of this reactor. It is found that the void fraction profile predicted by the code for the various experimental conditions differ considerably from the experimental results.
求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
Nuclear Engineering International
Nuclear Engineering International 工程技术-核科学技术
自引率
0.00%
发文量
0
审稿时长
6-12 weeks
期刊介绍: Information not localized
期刊最新文献
A Review of Cybersecurity and Biometric Authentication in Cloud Network Network Security Framework, Techniques, and Design for Hybrid Cloud Wave Structures for Nonlinear Schrodinger Types Fractional Partial Differential Equations Arise in Physical Sciences Significant of Gradient Boosting Algorithm in Data Management System Handwritten Bangla Numerical Digit Recognition Using Fine Regulated Deep Neural Network
×
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