多平行通道系统中流动分裂的分析与计算分析

A. Lazarte, J. Ferreri
{"title":"多平行通道系统中流动分裂的分析与计算分析","authors":"A. Lazarte, J. Ferreri","doi":"10.4236/WJNST.2016.63019","DOIUrl":null,"url":null,"abstract":"Previous analytical results on flow splitting are generalized to consider \nmultiple boiling channels systems. The analysis is consistent with the \napproximations usually adopted in the use of systems codes (like RELAP5 and TRACE5, among others) commonly applied to perform \nsafety analyses of nuclear power \nplants. The problem is related to multiple, identical, parallel boiling \nchannels, connected through common plena. A theoretical model limited in \nscope explains this flow splitting without \nreversal. The unified analysis performed and the confirmatory computational \nresults found are summarized in this \npaper. New maps showing the zones where this behavior is predicted are also shown considering again twin \npipes. Multiple pipe systems have been found not easily amenable for \nanalytical analysis when dealing with more than four parallel pipes. However, \nthe particular splitting found (flow along N pipes dividing in one standalone \npipe flow plus N -1 identical pipe flows) has been verified up to fourteen pipes, involving \ncalculations in systems with even and odd number of pipes using the RELAP5 systems \nthermal-hydraulics code.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0000,"publicationDate":"2016-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":"{\"title\":\"Analytical and Computational Analysis of Flow Splitting in Multiple, Parallel Channels Systems\",\"authors\":\"A. Lazarte, J. Ferreri\",\"doi\":\"10.4236/WJNST.2016.63019\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Previous analytical results on flow splitting are generalized to consider \\nmultiple boiling channels systems. The analysis is consistent with the \\napproximations usually adopted in the use of systems codes (like RELAP5 and TRACE5, among others) commonly applied to perform \\nsafety analyses of nuclear power \\nplants. The problem is related to multiple, identical, parallel boiling \\nchannels, connected through common plena. A theoretical model limited in \\nscope explains this flow splitting without \\nreversal. The unified analysis performed and the confirmatory computational \\nresults found are summarized in this \\npaper. New maps showing the zones where this behavior is predicted are also shown considering again twin \\npipes. Multiple pipe systems have been found not easily amenable for \\nanalytical analysis when dealing with more than four parallel pipes. However, \\nthe particular splitting found (flow along N pipes dividing in one standalone \\npipe flow plus N -1 identical pipe flows) has been verified up to fourteen pipes, involving \\ncalculations in systems with even and odd number of pipes using the RELAP5 systems \\nthermal-hydraulics code.\",\"PeriodicalId\":61566,\"journal\":{\"name\":\"核科学与技术国际期刊(英文)\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2016-07-09\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"核科学与技术国际期刊(英文)\",\"FirstCategoryId\":\"1087\",\"ListUrlMain\":\"https://doi.org/10.4236/WJNST.2016.63019\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"核科学与技术国际期刊(英文)","FirstCategoryId":"1087","ListUrlMain":"https://doi.org/10.4236/WJNST.2016.63019","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 1

摘要

将以往关于流动分裂的分析结果推广到考虑多沸腾通道系统。该分析与通常用于执行核电厂安全分析的系统代码(如RELAP5和TRACE5等)通常采用的近似一致。这个问题与多个相同的平行沸腾通道有关,这些通道通过共同的全气池连接。一个有限范围的理论模型解释了这种无反转的流动分裂。本文对所进行的统一分析和得到的验证计算结果进行了总结。新的地图显示了预测这种行为的区域,同样考虑到双管道。当处理超过四个平行管道时,发现多个管道系统不容易进行分析分析。然而,发现的特殊分裂(沿N根管道的流动在一个独立的管道流中划分,加上N -1个相同的管道流)已经被验证了多达14根管道,包括使用RELAP5系统热工水力学代码对偶数和奇数管道的系统进行计算。
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
Analytical and Computational Analysis of Flow Splitting in Multiple, Parallel Channels Systems
Previous analytical results on flow splitting are generalized to consider multiple boiling channels systems. The analysis is consistent with the approximations usually adopted in the use of systems codes (like RELAP5 and TRACE5, among others) commonly applied to perform safety analyses of nuclear power plants. The problem is related to multiple, identical, parallel boiling channels, connected through common plena. A theoretical model limited in scope explains this flow splitting without reversal. The unified analysis performed and the confirmatory computational results found are summarized in this paper. New maps showing the zones where this behavior is predicted are also shown considering again twin pipes. Multiple pipe systems have been found not easily amenable for analytical analysis when dealing with more than four parallel pipes. However, the particular splitting found (flow along N pipes dividing in one standalone pipe flow plus N -1 identical pipe flows) has been verified up to fourteen pipes, involving calculations in systems with even and odd number of pipes using the RELAP5 systems thermal-hydraulics code.
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
自引率
0.00%
发文量
198
期刊最新文献
System Variables Design of Safety Analysis for Fast Reactors Numerical Analysis of Heating Technique in Corium Melt Pool Convection Flow Field & Thermal Interaction in a Volumetrically Heated Molten Pool Feasibility to Convert the NuScale SMR from UO2 to a Mixed (U, Th)O2 Core: A Parametric Study of Fuel Element—Seed-Blanket Concept Cause Analysis for Wall Thinning of Small-Bore Piping in Nuclear Power Plant by ToSPACE, FLUENT and Theoretical Evaluation The Systematics Study of (n, p) Reaction Cross-Sections at 14.7 MeV Neutron Energy
×
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