为干储存分析寻找限制棒

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-11-13 DOI:10.1016/j.anucene.2024.111043
Piotr Konarski, Alexey Cherezov, Cedric Cozzo, Grigori Khvostov, Hakim Ferroukhi
{"title":"为干储存分析寻找限制棒","authors":"Piotr Konarski,&nbsp;Alexey Cherezov,&nbsp;Cedric Cozzo,&nbsp;Grigori Khvostov,&nbsp;Hakim Ferroukhi","doi":"10.1016/j.anucene.2024.111043","DOIUrl":null,"url":null,"abstract":"<div><div>Fuel rod status during reactor operation must be numerically modeled before dry storage analyses. Simulating all the rods ever irradiated in Switzerland with state-of-the-art best estimate tools would be too time consuming. The goal of this study is to develop a methodology for identifying limiting BWR rods, where the criterion of limiting is the rod internal pressure. Limiting rods are those whose parameters may challenge rod integrity during dry storage, subsequent transport, or handling. The presence of radial hydrides is of particular importance. The precipitation of radially oriented hydrides is associated with strong tensile hoop stress of the cladding. This can be a consequence of high rod internal pressure which has been chosen the limiting parameter. In the first step, the 3D core simulators provide irradiation data. Then, the core simulator results along with rod geometrical parameters are submitted to the principal component analysis. The multidimensional datasets are reduced to 2D and processed by a clustering algorithm or not, depending on the assembly design. The limiting rods are identified for each batch or cluster and simulated with the fuel performance code Falcon and the hydrogen behavior code HYPE.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111043"},"PeriodicalIF":1.9000,"publicationDate":"2024-11-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Finding limiting rods for dry storage analyses\",\"authors\":\"Piotr Konarski,&nbsp;Alexey Cherezov,&nbsp;Cedric Cozzo,&nbsp;Grigori Khvostov,&nbsp;Hakim Ferroukhi\",\"doi\":\"10.1016/j.anucene.2024.111043\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Fuel rod status during reactor operation must be numerically modeled before dry storage analyses. Simulating all the rods ever irradiated in Switzerland with state-of-the-art best estimate tools would be too time consuming. The goal of this study is to develop a methodology for identifying limiting BWR rods, where the criterion of limiting is the rod internal pressure. Limiting rods are those whose parameters may challenge rod integrity during dry storage, subsequent transport, or handling. The presence of radial hydrides is of particular importance. The precipitation of radially oriented hydrides is associated with strong tensile hoop stress of the cladding. This can be a consequence of high rod internal pressure which has been chosen the limiting parameter. In the first step, the 3D core simulators provide irradiation data. Then, the core simulator results along with rod geometrical parameters are submitted to the principal component analysis. The multidimensional datasets are reduced to 2D and processed by a clustering algorithm or not, depending on the assembly design. The limiting rods are identified for each batch or cluster and simulated with the fuel performance code Falcon and the hydrogen behavior code HYPE.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"212 \",\"pages\":\"Article 111043\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-11-13\",\"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/S0306454924007060\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454924007060","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

摘要

在进行干式贮存分析之前,必须对反应堆运行期间的燃料棒状态进行数值模拟。使用最先进的最佳估计工具模拟瑞士曾经辐照过的所有燃料棒将耗费大量时间。本研究的目标是开发一种方法,用于识别限制性生物质能反应堆燃料棒,限制性标准是燃料棒内部压力。限制性棒材是指其参数可能会在干储存、后续运输或处理过程中对棒材完整性造成挑战的棒材。径向氢化物的存在尤为重要。径向水化物的析出与包层的强拉箍应力有关。这可能是高棒内压的结果,而高棒内压被选为限制参数。第一步,三维岩心模拟器提供辐照数据。然后,将岩心模拟器结果和棒材几何参数一起提交给主成分分析。多维数据集被简化为二维数据集,并根据装配设计的不同采用聚类算法或不采用聚类算法进行处理。确定每批或每组的极限棒,并使用燃料性能代码 Falcon 和氢行为代码 HYPE 进行模拟。
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
Finding limiting rods for dry storage analyses
Fuel rod status during reactor operation must be numerically modeled before dry storage analyses. Simulating all the rods ever irradiated in Switzerland with state-of-the-art best estimate tools would be too time consuming. The goal of this study is to develop a methodology for identifying limiting BWR rods, where the criterion of limiting is the rod internal pressure. Limiting rods are those whose parameters may challenge rod integrity during dry storage, subsequent transport, or handling. The presence of radial hydrides is of particular importance. The precipitation of radially oriented hydrides is associated with strong tensile hoop stress of the cladding. This can be a consequence of high rod internal pressure which has been chosen the limiting parameter. In the first step, the 3D core simulators provide irradiation data. Then, the core simulator results along with rod geometrical parameters are submitted to the principal component analysis. The multidimensional datasets are reduced to 2D and processed by a clustering algorithm or not, depending on the assembly design. The limiting rods are identified for each batch or cluster and simulated with the fuel performance code Falcon and the hydrogen behavior code HYPE.
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
Annals of Nuclear Energy
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.
期刊最新文献
Evaluation of uranium-233 neutron capture cross section in keV region Application of data partitioned Kriging algorithm with GPU acceleration in real-time and refined reconstruction of three-dimensional radiation fields Boiling critical characteristics in narrow rectangular channel under local heat flux concentration conditions Investigation on thermal response of high temperature heat pipe under thermal mismatch conditions Numerical simulation of impurity particles migration and deposition within the 5 × 5 fuel assembly under nucleate boiling conditions
×
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