比较燃耗计算的实现

V. Los', A. Kuryndin, A. Kirkin, S. Sinegribov, S. Makovskiy
{"title":"比较燃耗计算的实现","authors":"V. Los', A. Kuryndin, A. Kirkin, S. Sinegribov, S. Makovskiy","doi":"10.55176/2414-1038-2020-3-19-29","DOIUrl":null,"url":null,"abstract":"Features of calculation methods implemented in computer codes, evaluated nuclear data libraries and computer models have a significant impact on the results of burnup calculations. This article contains comparative calculations of VVER-1000 reactor nuclear fuel burnup and demonstrates an influence of different factors on the results of these calculations. The results of comparative analisys demonstrate the necessity to intensify creation of benchmarks with experimental data on nuclide concentarions in fuel including fuel for fast neutron reactors.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0000,"publicationDate":"2020-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"IMPLEMENTATION OF COMPARATIVE BURNUP CALCULATIONS\",\"authors\":\"V. Los', A. Kuryndin, A. Kirkin, S. Sinegribov, S. Makovskiy\",\"doi\":\"10.55176/2414-1038-2020-3-19-29\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Features of calculation methods implemented in computer codes, evaluated nuclear data libraries and computer models have a significant impact on the results of burnup calculations. This article contains comparative calculations of VVER-1000 reactor nuclear fuel burnup and demonstrates an influence of different factors on the results of these calculations. The results of comparative analisys demonstrate the necessity to intensify creation of benchmarks with experimental data on nuclide concentarions in fuel including fuel for fast neutron reactors.\",\"PeriodicalId\":20426,\"journal\":{\"name\":\"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2020-09-26\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.55176/2414-1038-2020-3-19-29\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.55176/2414-1038-2020-3-19-29","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

摘要

计算机代码、评估核数据库和计算机模型中实现的计算方法的特点对燃耗计算的结果有重大影响。本文包含了VVER-1000反应堆核燃料燃耗的比较计算,并论证了不同因素对这些计算结果的影响。比较分析的结果表明,有必要加强用燃料(包括快中子反应堆燃料)中核素浓度的实验数据建立基准。
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
IMPLEMENTATION OF COMPARATIVE BURNUP CALCULATIONS
Features of calculation methods implemented in computer codes, evaluated nuclear data libraries and computer models have a significant impact on the results of burnup calculations. This article contains comparative calculations of VVER-1000 reactor nuclear fuel burnup and demonstrates an influence of different factors on the results of these calculations. The results of comparative analisys demonstrate the necessity to intensify creation of benchmarks with experimental data on nuclide concentarions in fuel including fuel for fast neutron reactors.
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
0
期刊最新文献
POSSIBILITY OF APPLICATION OF ZrO2-MgO-CaO CRUCIBLES FOR PRODUCING ALLOY U-10 % Zr CALCULATION ESTIMATION OF THE REQUIRED HEAT GENERATION IN TESTING FUEL ELEMENTS TO ACHIEVE SUPERCRITICAL PARAMETERS OF THE COOLANT UNDER IRRADIATION IN THE RESEARCH NUCLEAR REACTOR FEATURES OF THERMAL HYDRAULICS OF ACTIVE ZONES OF FAST LOW-POWER AND HIGH-POWER SODIUM PRODUCTION REACTORS FOR A CLOSED FUEL CYCLE SYSTEM CALCULATION OF THE STRUCTURAL MATERIALS ACTIVATION BY A FUSION NEUTRON FLUX WITH BPSD CODE HEAT PIPES IN NUCLEAR ENGINEERING
×
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