事故条件下UO2燃料精细碎裂和裂变气体释放的建模

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2019-09-01 DOI:10.1051/epjn/2019030
L. Jernkvist
{"title":"事故条件下UO2燃料精细碎裂和裂变气体释放的建模","authors":"L. Jernkvist","doi":"10.1051/epjn/2019030","DOIUrl":null,"url":null,"abstract":"In reactor accidents that involve rapid overheating of oxide fuel, overpressurization of gas-filled bubbles and pores may lead to rupture of these cavities, fine fragmentation of the fuel material, and burst-type release of the cavity gas. Analytical rupture criteria for various types of cavities exist, but application of these criteria requires that microstructural characteristics of the fuel, such as cavity size, shape and number density, are known together with the gas content of the cavities. In this paper, we integrate rupture criteria for two kinds of cavities with models that calculate the aforementioned parameters in UO2 LWR fuel for a given operating history. The models are intended for implementation in engineering type computer programs for thermal-mechanical analyses of LWR fuel rods. Here, they have been implemented in the FRAPCON and FRAPTRAN programs and validated against experiments that simulate LOCA and RIA conditions. The capabilities and shortcomings of the proposed models are discussed in light of selected results from this validation. Calculated results suggest that the extent of fuel fragmentation and transient fission gas release depends strongly on the pre-accident fuel microstructure and fission gas distribution, but also on rapid changes in the external pressure exerted on the fuel pellets during the accident.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":" ","pages":""},"PeriodicalIF":0.9000,"publicationDate":"2019-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019030","citationCount":"10","resultStr":"{\"title\":\"Modelling of fine fragmentation and fission gas release of UO2 fuel in accident conditions\",\"authors\":\"L. Jernkvist\",\"doi\":\"10.1051/epjn/2019030\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"In reactor accidents that involve rapid overheating of oxide fuel, overpressurization of gas-filled bubbles and pores may lead to rupture of these cavities, fine fragmentation of the fuel material, and burst-type release of the cavity gas. Analytical rupture criteria for various types of cavities exist, but application of these criteria requires that microstructural characteristics of the fuel, such as cavity size, shape and number density, are known together with the gas content of the cavities. In this paper, we integrate rupture criteria for two kinds of cavities with models that calculate the aforementioned parameters in UO2 LWR fuel for a given operating history. The models are intended for implementation in engineering type computer programs for thermal-mechanical analyses of LWR fuel rods. Here, they have been implemented in the FRAPCON and FRAPTRAN programs and validated against experiments that simulate LOCA and RIA conditions. The capabilities and shortcomings of the proposed models are discussed in light of selected results from this validation. Calculated results suggest that the extent of fuel fragmentation and transient fission gas release depends strongly on the pre-accident fuel microstructure and fission gas distribution, but also on rapid changes in the external pressure exerted on the fuel pellets during the accident.\",\"PeriodicalId\":44454,\"journal\":{\"name\":\"EPJ Nuclear Sciences & Technologies\",\"volume\":\" \",\"pages\":\"\"},\"PeriodicalIF\":0.9000,\"publicationDate\":\"2019-09-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://sci-hub-pdf.com/10.1051/epjn/2019030\",\"citationCount\":\"10\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"EPJ Nuclear Sciences & Technologies\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1051/epjn/2019030\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q3\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"EPJ Nuclear Sciences & Technologies","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1051/epjn/2019030","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 10

摘要

在涉及氧化物燃料快速过热的反应堆事故中,充满气体的气泡和孔隙的过压可能导致这些空腔破裂,燃料材料的细碎裂,以及空腔气体的爆裂型释放。存在各种类型空腔的分析破裂准则,但这些准则的应用需要知道燃料的微观结构特征,如空腔的大小、形状和数量密度,以及空腔的气体含量。在本文中,我们将两种空腔的破裂准则与计算给定运行历史下UO2轻水堆燃料上述参数的模型相结合。这些模型的目的是在工程型计算机程序中实现对轻水堆燃料棒的热-力学分析。在这里,它们已经在FRAPCON和FRAPTRAN程序中实现,并针对模拟LOCA和RIA条件的实验进行了验证。根据本次验证的选定结果,讨论了所提出模型的能力和缺点。计算结果表明,燃料碎裂和瞬态裂变气体释放的程度在很大程度上取决于事故前燃料微观结构和裂变气体分布,但也取决于事故期间施加在燃料球团上的外部压力的快速变化。
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
Modelling of fine fragmentation and fission gas release of UO2 fuel in accident conditions
In reactor accidents that involve rapid overheating of oxide fuel, overpressurization of gas-filled bubbles and pores may lead to rupture of these cavities, fine fragmentation of the fuel material, and burst-type release of the cavity gas. Analytical rupture criteria for various types of cavities exist, but application of these criteria requires that microstructural characteristics of the fuel, such as cavity size, shape and number density, are known together with the gas content of the cavities. In this paper, we integrate rupture criteria for two kinds of cavities with models that calculate the aforementioned parameters in UO2 LWR fuel for a given operating history. The models are intended for implementation in engineering type computer programs for thermal-mechanical analyses of LWR fuel rods. Here, they have been implemented in the FRAPCON and FRAPTRAN programs and validated against experiments that simulate LOCA and RIA conditions. The capabilities and shortcomings of the proposed models are discussed in light of selected results from this validation. Calculated results suggest that the extent of fuel fragmentation and transient fission gas release depends strongly on the pre-accident fuel microstructure and fission gas distribution, but also on rapid changes in the external pressure exerted on the fuel pellets during the accident.
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
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
×
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