Feasibility Study on the Initial Kartini Reactor Core Using Plate Type Fuel Elements

IF 1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Science and Technology of Nuclear Installations Pub Date : 2022-10-14 DOI:10.1155/2022/9629413
Argo Satrio Wicaksono, S. Takeda, T. Kitada
{"title":"Feasibility Study on the Initial Kartini Reactor Core Using Plate Type Fuel Elements","authors":"Argo Satrio Wicaksono, S. Takeda, T. Kitada","doi":"10.1155/2022/9629413","DOIUrl":null,"url":null,"abstract":"The plate type fuel element conversion is proposed to solve a supply problem of TRIGA standard rod type fresh fuel in the long term and to extend the lifetime by reducing the dependence of buying imported elements. The plate type fuel is an alternative since the Indonesian industry has been able to produce such fuel elements. The change of core configuration is expected to improve the reactor performance for irradiation facilities and fuel element lifetime. The SRAC2006 is used to perform neutronic calculations while the nuclear fuel lifetime is calculated by SWAT. This study begins with performing a core properties comparison of UZrH1.6 as the current fuel material and U3Si2-Al as the fuel material candidate. The results show that the Kartini reactor core is possible to load U3Si2-Al as the fuel material and makes higher excess reactivity compared to the current fuel material. Furthermore, U3Si2-Al in the plate type element geometry is variedly arranged in the new reactor core configuration to optimize the neutronic core parameters. The new core configuration is composed of 10 standard fuel elements, 4 fuel control elements, and the graphite material baffle that is located between the active core and annular reflector for serves as an additional reflector. The configuration produced sufficient core excess reactivity and adequate shutdown margin. It also produced negative temperature feedback reactivity and power peaking factor that fulfilled the safety requirements. Improvement of new reactor core performance was obtained by more irradiation facilities, higher thermal neutron flux, and longer maximum estimated burn up compared to the current core configuration.","PeriodicalId":21629,"journal":{"name":"Science and Technology of Nuclear Installations","volume":" ","pages":""},"PeriodicalIF":1.0000,"publicationDate":"2022-10-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Science and Technology of Nuclear Installations","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1155/2022/9629413","RegionNum":4,"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: 1

Abstract

The plate type fuel element conversion is proposed to solve a supply problem of TRIGA standard rod type fresh fuel in the long term and to extend the lifetime by reducing the dependence of buying imported elements. The plate type fuel is an alternative since the Indonesian industry has been able to produce such fuel elements. The change of core configuration is expected to improve the reactor performance for irradiation facilities and fuel element lifetime. The SRAC2006 is used to perform neutronic calculations while the nuclear fuel lifetime is calculated by SWAT. This study begins with performing a core properties comparison of UZrH1.6 as the current fuel material and U3Si2-Al as the fuel material candidate. The results show that the Kartini reactor core is possible to load U3Si2-Al as the fuel material and makes higher excess reactivity compared to the current fuel material. Furthermore, U3Si2-Al in the plate type element geometry is variedly arranged in the new reactor core configuration to optimize the neutronic core parameters. The new core configuration is composed of 10 standard fuel elements, 4 fuel control elements, and the graphite material baffle that is located between the active core and annular reflector for serves as an additional reflector. The configuration produced sufficient core excess reactivity and adequate shutdown margin. It also produced negative temperature feedback reactivity and power peaking factor that fulfilled the safety requirements. Improvement of new reactor core performance was obtained by more irradiation facilities, higher thermal neutron flux, and longer maximum estimated burn up compared to the current core configuration.
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
卡尔蒂尼堆初始堆芯采用板式燃料元件的可行性研究
板型燃料元件转换是为了解决TRIGA标准棒型新燃料的长期供应问题,并通过减少购买进口元件的依赖性来延长寿命。板式燃料是一种替代方案,因为印尼工业已经能够生产这种燃料元件。堆芯配置的改变有望提高反应堆辐照设施的性能和燃料元件的寿命。SRAC2006用于进行中子计算,而核燃料寿命由SWAT计算。本研究首先对当前燃料材料UZrH1.6和候选燃料材料U3Si2-Al进行堆芯性能比较。结果表明,Kartini堆芯可以装载U3Si2-Al作为燃料材料,并且与当前的燃料材料相比具有更高的过剩反应性。此外,在新的反应堆堆芯配置中,板型元件几何形状的U3Si2-Al被可变地布置,以优化中子堆芯参数。新的堆芯配置由10个标准燃料元件、4个燃料控制元件和石墨材料挡板组成,石墨材料挡板位于活性堆芯和环形反射器之间,用作附加反射器。该配置产生了足够的堆芯过剩反应性和足够的停堆裕度。它还产生了负温度反馈反应性和功率峰值因子,满足了安全要求。与目前的堆芯配置相比,通过更多的辐照设施、更高的热中子通量和更长的最大估计燃耗,新反应堆堆芯性能得到了改善。
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
Science and Technology of Nuclear Installations
Science and Technology of Nuclear Installations NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.30
自引率
9.10%
发文量
51
审稿时长
4-8 weeks
期刊介绍: Science and Technology of Nuclear Installations is an international scientific journal that aims to make available knowledge on issues related to the nuclear industry and to promote development in the area of nuclear sciences and technologies. The endeavor associated with the establishment and the growth of the journal is expected to lend support to the renaissance of nuclear technology in the world and especially in those countries where nuclear programs have not yet been developed.
期刊最新文献
Assessment of Radiation Dose Associated with the Atmospheric Release of 41Ar from the TRIGA Mark-II Research Reactor in Bangladesh Design Change and Operational Consideration of the HVAC System during Nuclear Power Plant Decommissioning Accuracy Evaluation of Monte Carlo Simulation Results Using ENDF/B-VIII.0 and JENDL-5 Libraries for 10 MWth Micro Heat Pipe-Cooled Reactor Effect of Photomultiplier Tube Voltage on the Performance of Sealed NaI (Tl) Scintillator Detectors An Association Rule Mining-Based Method for Revealing the Impact of Operational Sequence on Nuclear Power Plants Operating
×
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