An Open-Source Coupling for Depletion During Fuel Cycle Modeling

IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Science and Engineering Pub Date : 2024-09-12 DOI:10.1080/00295639.2024.2393940
Amanda M. Bachmann, Oleksandr Yardas, Madicken Munk
{"title":"An Open-Source Coupling for Depletion During Fuel Cycle Modeling","authors":"Amanda M. Bachmann, Oleksandr Yardas, Madicken Munk","doi":"10.1080/00295639.2024.2393940","DOIUrl":null,"url":null,"abstract":"Fuel depletion is an important aspect of fuel cycle modeling, allowing a user to account for how loaded fuel compositions affect in-core and spent fuel compositions and their related fuel cycle met...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"1 1","pages":""},"PeriodicalIF":1.2000,"publicationDate":"2024-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Science and Engineering","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1080/00295639.2024.2393940","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

Fuel depletion is an important aspect of fuel cycle modeling, allowing a user to account for how loaded fuel compositions affect in-core and spent fuel compositions and their related fuel cycle met...
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
用于燃料循环建模期间损耗的开源耦合器
燃料损耗是燃料循环建模的一个重要方面,它使用户能够说明装载的燃料成分如何影响内核燃料和乏燃料成分及其相关的燃料循环满足度...
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 Science and Engineering
Nuclear Science and Engineering 工程技术-核科学技术
CiteScore
2.10
自引率
25.00%
发文量
0
审稿时长
3 months
期刊介绍: Nuclear Science and Engineering, the research journal of the American Nuclear Society, publishes articles on research and development related to peaceful utilization of nuclear energy, radiation, and alternative energy sources.
期刊最新文献
Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 235U A “Consistent” Quasidiffusion Method for Solving Particle Transport Problems An Open-Source Coupling for Depletion During Fuel Cycle Modeling Development of Target Holder for the First Experiment on an Alternative Route for 64Cu Radioisotope Production by Secondary Neutron Irradiation of a 64ZnO Target
×
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