MCNP Simulation of Physics Parameters of Dispersion Fuels for Conversion of NIRR-1 to LEU

K. Ibikunle, U. Sadiq, Y. V. Ibrahim, S. Jonah
{"title":"MCNP Simulation of Physics Parameters of Dispersion Fuels for Conversion of NIRR-1 to LEU","authors":"K. Ibikunle, U. Sadiq, Y. V. Ibrahim, S. Jonah","doi":"10.4236/wjnst.2018.82003","DOIUrl":null,"url":null,"abstract":"The Nigeria Research Reactor-1 (NIRR-1) is one of the Commercial Miniature Neutron Source Reactors (MNSRs) sited outside China and scheduled for conversion under the auspices of Reduced Enrichment for Research and Test Reactors (RERTR) program. Since 2006, the reduction in the fuel enrichment of MSNR facilities from greater than 90% HEU cores to less than 20% LEU cores has been embarked upon. Consequently in this work, the physics parameters of three dispersion LEU fuels, which include U3Si, U3Si2, and U9Mo enriched to 19.75% were determined by the MCNP code to investigate their suitability for the conversion of NIRR-1 to LEU. The following reactor core physics parameters were computed for the LEU fuel options: clean cold core excess reactivity (ρex), control rod (CR) worth, shut down margin (SDM), neutron flux distributions in the irradiation channels and kinetics data (i.e. effective delayed neutron fraction, βeff and prompt neutron lifetime, lf). Results are compared with experimental and calculated data of the current HEU core and indicate that it would be feasible to use any of the LEU options for the conversion of commercial MNSR in general and NIRR-1 in particular from HEU to LEU.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":"08 1","pages":"23-29"},"PeriodicalIF":0.0000,"publicationDate":"2018-03-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"3","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"核科学与技术国际期刊(英文)","FirstCategoryId":"1087","ListUrlMain":"https://doi.org/10.4236/wjnst.2018.82003","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 3

Abstract

The Nigeria Research Reactor-1 (NIRR-1) is one of the Commercial Miniature Neutron Source Reactors (MNSRs) sited outside China and scheduled for conversion under the auspices of Reduced Enrichment for Research and Test Reactors (RERTR) program. Since 2006, the reduction in the fuel enrichment of MSNR facilities from greater than 90% HEU cores to less than 20% LEU cores has been embarked upon. Consequently in this work, the physics parameters of three dispersion LEU fuels, which include U3Si, U3Si2, and U9Mo enriched to 19.75% were determined by the MCNP code to investigate their suitability for the conversion of NIRR-1 to LEU. The following reactor core physics parameters were computed for the LEU fuel options: clean cold core excess reactivity (ρex), control rod (CR) worth, shut down margin (SDM), neutron flux distributions in the irradiation channels and kinetics data (i.e. effective delayed neutron fraction, βeff and prompt neutron lifetime, lf). Results are compared with experimental and calculated data of the current HEU core and indicate that it would be feasible to use any of the LEU options for the conversion of commercial MNSR in general and NIRR-1 in particular from HEU to LEU.
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
核素-1转低浓铀过程中分散燃料物理参数的MCNP模拟
尼日利亚1号研究堆(NIRR-1)是位于中国境外的商业微型中子源反应堆(MNSRs)之一,计划在研究和试验反应堆(RERTR)项目的支持下进行改造。自2006年以来,已经开始将MSNR设施的燃料浓缩从高浓铀堆芯的90%以上降低到低浓铀堆芯的20%以下。因此,在这项工作中,三种分散型低浓铀燃料(U3Si, U3Si2和U9Mo)的物理参数由MCNP代码确定,以研究它们对低浓铀燃料(nir -1)转化为低浓铀的适用性。净冷堆超反应性(ρex)、控制棒(CR)值、关闭裕度(SDM)、辐照通道中的中子通量分布和动力学数据(即有效延迟中子分数,βeff和提示中子寿命,lf)。结果与现有高浓铀堆芯的实验和计算数据进行了比较,表明使用任何低浓铀方案都是可行的,一般来说,特别是将低浓铀转化为低浓铀。
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
自引率
0.00%
发文量
198
期刊最新文献
System Variables Design of Safety Analysis for Fast Reactors Numerical Analysis of Heating Technique in Corium Melt Pool Convection Flow Field & Thermal Interaction in a Volumetrically Heated Molten Pool Feasibility to Convert the NuScale SMR from UO2 to a Mixed (U, Th)O2 Core: A Parametric Study of Fuel Element—Seed-Blanket Concept Cause Analysis for Wall Thinning of Small-Bore Piping in Nuclear Power Plant by ToSPACE, FLUENT and Theoretical Evaluation The Systematics Study of (n, p) Reaction Cross-Sections at 14.7 MeV Neutron Energy
×
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