探索在美国SCLWR中用不同钍基燃料替代UO2的潜在优势

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-09 DOI:10.1016/j.nucengdes.2024.113751
Nassar Alnassar , Muneerah A. Al-Aqeel , Sitah Alanazi , Maha Algarawi , Mohamed Y.M. Mohsen , A. Abdelghafar Galahom
{"title":"探索在美国SCLWR中用不同钍基燃料替代UO2的潜在优势","authors":"Nassar Alnassar ,&nbsp;Muneerah A. Al-Aqeel ,&nbsp;Sitah Alanazi ,&nbsp;Maha Algarawi ,&nbsp;Mohamed Y.M. Mohsen ,&nbsp;A. Abdelghafar Galahom","doi":"10.1016/j.nucengdes.2024.113751","DOIUrl":null,"url":null,"abstract":"<div><div>This work searches for enhancing the efficiency of the supercritical light water reactor SCLWR by introducing different fuels based on thorium as an alternative fuel to conventional fuel. United States fuel assembly model of SCLWR has been modeled using Monte Carlo code MCNPX, ed. 2.7. The burnup results, k<sub>inf</sub>, fuel composition and most importantly actinides and non-actinides have been examined and compared with that of the UO<sub>2</sub>. The neutronic safety coefficients such as reactivity temperature coefficient and control rod worth have been calculated for the suggested fuel cycles. Also, the radial and axial neutron flux as well as power distribution have been analyzed to verify the validity of the proposed fuels. Assessment results demonstrate the viability of the proposed fuel. Reactivity measurements indicate that the introduced fuels have an economic benefit as using <sup>232</sup>Th with <sup>233</sup>U as a fuel increased the fuel cycle by 140 EFPD compared to the standard fuel cycle of UO<sub>2</sub>. The reactivity temperature coefficients show that the proposed fuel provides a suitable level of passive safety as the fuel temperature coefficient (FTC) and the moderator temperature coefficient (MTC) values of the investigated fuel range from −1.32 to −3.34 pcm/K and −8.8 to −25.9 pcm/K, respectively. The power distribution indicates that there will be no melting of the fuel. This is because the power is not accumulated in specific fuel rods for the investigated fuels. The analysis of actinides concentrations shows that SCLWR is a good consumer of rgPu where it consumed more than 69% of the rgPu used in the fuel at the beginning of the fuel cycle.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"432 ","pages":"Article 113751"},"PeriodicalIF":2.1000,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Explore the potential advantages of replacing UO2 with different thorium-based fuels in U.S. SCLWR\",\"authors\":\"Nassar Alnassar ,&nbsp;Muneerah A. Al-Aqeel ,&nbsp;Sitah Alanazi ,&nbsp;Maha Algarawi ,&nbsp;Mohamed Y.M. Mohsen ,&nbsp;A. Abdelghafar Galahom\",\"doi\":\"10.1016/j.nucengdes.2024.113751\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>This work searches for enhancing the efficiency of the supercritical light water reactor SCLWR by introducing different fuels based on thorium as an alternative fuel to conventional fuel. United States fuel assembly model of SCLWR has been modeled using Monte Carlo code MCNPX, ed. 2.7. The burnup results, k<sub>inf</sub>, fuel composition and most importantly actinides and non-actinides have been examined and compared with that of the UO<sub>2</sub>. The neutronic safety coefficients such as reactivity temperature coefficient and control rod worth have been calculated for the suggested fuel cycles. Also, the radial and axial neutron flux as well as power distribution have been analyzed to verify the validity of the proposed fuels. Assessment results demonstrate the viability of the proposed fuel. Reactivity measurements indicate that the introduced fuels have an economic benefit as using <sup>232</sup>Th with <sup>233</sup>U as a fuel increased the fuel cycle by 140 EFPD compared to the standard fuel cycle of UO<sub>2</sub>. The reactivity temperature coefficients show that the proposed fuel provides a suitable level of passive safety as the fuel temperature coefficient (FTC) and the moderator temperature coefficient (MTC) values of the investigated fuel range from −1.32 to −3.34 pcm/K and −8.8 to −25.9 pcm/K, respectively. The power distribution indicates that there will be no melting of the fuel. This is because the power is not accumulated in specific fuel rods for the investigated fuels. The analysis of actinides concentrations shows that SCLWR is a good consumer of rgPu where it consumed more than 69% of the rgPu used in the fuel at the beginning of the fuel cycle.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"432 \",\"pages\":\"Article 113751\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-02-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0029549324008513\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"2024/12/9 0:00:00\",\"PubModel\":\"Epub\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549324008513","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2024/12/9 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

摘要

本研究通过引入以钍为基础的不同燃料替代常规燃料,探索提高超临界轻水反应堆SCLWR效率的方法。美国SCLWR燃料组件模型已使用蒙特卡罗代码MCNPX,编辑2.7建模。对UO2的燃耗结果、种类、燃料成分以及最重要的锕系元素和非锕系元素进行了检验和比较。计算了所建议燃料循环的中子安全系数,如反应性温度系数和控制棒值。此外,还分析了径向和轴向中子通量以及功率分布,以验证所提出燃料的有效性。评估结果证明了该燃料的可行性。反应性测量表明,引入的燃料具有经济效益,因为与UO2的标准燃料循环相比,使用232Th和233U作为燃料可使燃料循环增加140 EFPD。反应性温度系数表明,所研究燃料的燃料温度系数(FTC)和慢化剂温度系数(MTC)值分别为- 1.32 ~ - 3.34 pcm/K和- 8.8 ~ - 25.9 pcm/K,提供了合适的被动安全水平。功率分布表明燃料不会熔化。这是因为所研究的燃料的功率不是在特定的燃料棒中积累的。锕系元素浓度分析表明,SCLWR是rgPu的良好消费者,在燃料循环开始时,它消耗了燃料中使用的rgPu的69%以上。
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
Explore the potential advantages of replacing UO2 with different thorium-based fuels in U.S. SCLWR
This work searches for enhancing the efficiency of the supercritical light water reactor SCLWR by introducing different fuels based on thorium as an alternative fuel to conventional fuel. United States fuel assembly model of SCLWR has been modeled using Monte Carlo code MCNPX, ed. 2.7. The burnup results, kinf, fuel composition and most importantly actinides and non-actinides have been examined and compared with that of the UO2. The neutronic safety coefficients such as reactivity temperature coefficient and control rod worth have been calculated for the suggested fuel cycles. Also, the radial and axial neutron flux as well as power distribution have been analyzed to verify the validity of the proposed fuels. Assessment results demonstrate the viability of the proposed fuel. Reactivity measurements indicate that the introduced fuels have an economic benefit as using 232Th with 233U as a fuel increased the fuel cycle by 140 EFPD compared to the standard fuel cycle of UO2. The reactivity temperature coefficients show that the proposed fuel provides a suitable level of passive safety as the fuel temperature coefficient (FTC) and the moderator temperature coefficient (MTC) values of the investigated fuel range from −1.32 to −3.34 pcm/K and −8.8 to −25.9 pcm/K, respectively. The power distribution indicates that there will be no melting of the fuel. This is because the power is not accumulated in specific fuel rods for the investigated fuels. The analysis of actinides concentrations shows that SCLWR is a good consumer of rgPu where it consumed more than 69% of the rgPu used in the fuel at the beginning of the fuel cycle.
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
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
期刊最新文献
Operational flexibility enhancement of small modular reactor nuclear power plants via characterization and optimization of the cold-end system Credible fission gas release calibration: A hierarchical Metropolis–Hastings-within-Gibbs approach to address model inadequacy Thermodynamic reactivity and phase behavior of NaOH–KOH eutectic with reactive off gases for molten salt scrubber A 3D dose mapping methodology for radioactive waste repositories using MCNP and deep rectified neural networks Spatial gradients of corrosion deposits in steam generator tubes of the BN-800 sodium-cooled reactor
×
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学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:604180095
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