高通量同位素反应堆的锎-252 生产 - II:高浓铀与拟议的低浓铀核心之间的比较

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-09-27 DOI:10.1016/j.anucene.2024.110920
David Chandler, Donny Hartanto, Jin Whan Bae, Kevin M. Burg, Yves Robert, Carol Sizemore
{"title":"高通量同位素反应堆的锎-252 生产 - II:高浓铀与拟议的低浓铀核心之间的比较","authors":"David Chandler,&nbsp;Donny Hartanto,&nbsp;Jin Whan Bae,&nbsp;Kevin M. Burg,&nbsp;Yves Robert,&nbsp;Carol Sizemore","doi":"10.1016/j.anucene.2024.110920","DOIUrl":null,"url":null,"abstract":"<div><div>This is the second paper on a <sup>252</sup>Cf production study performed in support of efforts to convert the High Flux Isotope Reactor (HFIR) from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel. The first paper primarily focuses on validating computational tools and nuclear data. This companion paper evaluates another critical aspect: the <sup>252</sup>Cf production capability with a proposed LEU core. HFIR must maintain its world-class performance and missions following conversion and because <sup>252</sup>Cf is a vital, multipurpose neutron-emitting radioisotope, the ability to efficiently produce <sup>252</sup>Cf must be preserved. In this study, the HFIRCON transport and depletion tool, several nuclear data libraries, and Campaign 78 data were used to compute <sup>252</sup>Cf production, sensitivity, and safety metrics. Results indicate the <sup>252</sup>Cf production and production rates are slightly higher with a 95<!--> <!-->MW<sub>th</sub> LEU core compared with those obtained with the 85<!--> <!-->MW<sub>th</sub> HEU core. Additionally, the target peak fission rate densities, discharge cumulative fission densities, and heat deposition rates with the LEU core are within a few percent of those calculated with the HEU core. The findings suggest HFIR’s <sup>252</sup>Cf production capability can be effectively maintained with an LEU core without adversely affecting the safety metrics.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-09-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Californium-252 production at the High Flux Isotope Reactor - II: Comparison between the highly enriched uranium and a proposed low-enriched uranium core\",\"authors\":\"David Chandler,&nbsp;Donny Hartanto,&nbsp;Jin Whan Bae,&nbsp;Kevin M. Burg,&nbsp;Yves Robert,&nbsp;Carol Sizemore\",\"doi\":\"10.1016/j.anucene.2024.110920\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>This is the second paper on a <sup>252</sup>Cf production study performed in support of efforts to convert the High Flux Isotope Reactor (HFIR) from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel. The first paper primarily focuses on validating computational tools and nuclear data. This companion paper evaluates another critical aspect: the <sup>252</sup>Cf production capability with a proposed LEU core. HFIR must maintain its world-class performance and missions following conversion and because <sup>252</sup>Cf is a vital, multipurpose neutron-emitting radioisotope, the ability to efficiently produce <sup>252</sup>Cf must be preserved. In this study, the HFIRCON transport and depletion tool, several nuclear data libraries, and Campaign 78 data were used to compute <sup>252</sup>Cf production, sensitivity, and safety metrics. Results indicate the <sup>252</sup>Cf production and production rates are slightly higher with a 95<!--> <!-->MW<sub>th</sub> LEU core compared with those obtained with the 85<!--> <!-->MW<sub>th</sub> HEU core. Additionally, the target peak fission rate densities, discharge cumulative fission densities, and heat deposition rates with the LEU core are within a few percent of those calculated with the HEU core. The findings suggest HFIR’s <sup>252</sup>Cf production capability can be effectively maintained with an LEU core without adversely affecting the safety metrics.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-09-27\",\"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/S0306454924005838\",\"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/S0306454924005838","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

这是关于 252Cf 生产研究的第二篇论文,该研究旨在支持将高通量同位素反应堆 (HFIR) 的燃料从高浓铀(HEU)转换为低浓铀(LEU)。第一篇论文主要侧重于验证计算工具和核数据。这篇配套论文评估了另一个关键方面:使用拟议 LEU 内核的 252Cf 生产能力。HFIR 必须在转换后保持其世界一流的性能和任务,由于 252Cf 是一种重要的多用途中子发射放射性同位素,因此必须保持高效生产 252Cf 的能力。在这项研究中,使用了 HFIRCON 输运和耗竭工具、几个核数据库和第 78 次战役数据来计算 252Cf 的生产、灵敏度和安全指标。结果表明,95 MWth LEU 堆芯的 252Cf 产量和生产率略高于 85 MWth HEU 堆芯。此外,使用 LEU 内核计算的目标峰值裂变率密度、放电累积裂变密度和热沉积率与使用 HEU 内核计算的结果相差无几。研究结果表明,使用低浓铀堆芯可以有效维持 HFIR 的 252Cf 生产能力,而不会对安全指标产生不利影响。
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
Californium-252 production at the High Flux Isotope Reactor - II: Comparison between the highly enriched uranium and a proposed low-enriched uranium core
This is the second paper on a 252Cf production study performed in support of efforts to convert the High Flux Isotope Reactor (HFIR) from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel. The first paper primarily focuses on validating computational tools and nuclear data. This companion paper evaluates another critical aspect: the 252Cf production capability with a proposed LEU core. HFIR must maintain its world-class performance and missions following conversion and because 252Cf is a vital, multipurpose neutron-emitting radioisotope, the ability to efficiently produce 252Cf must be preserved. In this study, the HFIRCON transport and depletion tool, several nuclear data libraries, and Campaign 78 data were used to compute 252Cf production, sensitivity, and safety metrics. Results indicate the 252Cf production and production rates are slightly higher with a 95 MWth LEU core compared with those obtained with the 85 MWth HEU core. Additionally, the target peak fission rate densities, discharge cumulative fission densities, and heat deposition rates with the LEU core are within a few percent of those calculated with the HEU core. The findings suggest HFIR’s 252Cf production capability can be effectively maintained with an LEU core without adversely affecting the safety metrics.
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
The nucleation characteristics of geyser boiling in sodium heat pipes European research reactor strategy derived in the scope of the towards optimized use of research reactors (TOURR) project Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD On the Neutron Kinetics during a Promptcritical Accident in a Heavy Liquid Metal Fast Reactor and the Importance of Low-Energy Neutrons Machine-learned force fields for thermal neutron scattering law evaluations
×
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