Effect of Kinetic Parameters on I-129 Activity from Fuel to Coolant in PWRs

Rubina Nasir
{"title":"Effect of Kinetic Parameters on I-129 Activity from Fuel to Coolant in PWRs","authors":"Rubina Nasir","doi":"10.4236/WJNST.2017.74022","DOIUrl":null,"url":null,"abstract":"Effect of kinetic model parameters on fission product (I-129) activity from fuel to coolant in PWRs has been studied in this work. First a computational model was developed for fission product release into primary coolant using ORIGEN-2 as subroutine. The model is based on set of differential equations of kinetic model which includes fuel-to-gap release model, gap-to-coolant leakage model, and Booths diffusion model. A Matlab based computer program FPAPC (Fission Product Activity in Primary Coolant) was developed. Variations of I-129 activity in Primary Heat Transport System were computed and computed values of i-129 were found in good agreement and deviations were within 2% - 3% of already published data values. Finally, the effects of coolant purification rate, diffusion constant and gas escape rate on I-129 activity were studied and results indicated that the coolant purification rate is the most sensitive parameter for fission product activity in primary circuit. For changes of 5% in steps from −10% to +10% in the coolant purification rate constant (Β), the activity variation after 200 days of reactor operation was 23.1% for the change.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":"07 1","pages":"284-291"},"PeriodicalIF":0.0000,"publicationDate":"2017-08-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","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.2017.74022","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

Effect of kinetic model parameters on fission product (I-129) activity from fuel to coolant in PWRs has been studied in this work. First a computational model was developed for fission product release into primary coolant using ORIGEN-2 as subroutine. The model is based on set of differential equations of kinetic model which includes fuel-to-gap release model, gap-to-coolant leakage model, and Booths diffusion model. A Matlab based computer program FPAPC (Fission Product Activity in Primary Coolant) was developed. Variations of I-129 activity in Primary Heat Transport System were computed and computed values of i-129 were found in good agreement and deviations were within 2% - 3% of already published data values. Finally, the effects of coolant purification rate, diffusion constant and gas escape rate on I-129 activity were studied and results indicated that the coolant purification rate is the most sensitive parameter for fission product activity in primary circuit. For changes of 5% in steps from −10% to +10% in the coolant purification rate constant (Β), the activity variation after 200 days of reactor operation was 23.1% for the change.
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
动力学参数对PWR中从燃料到冷却剂的I-129活性的影响
本文研究了动力学模型参数对压水堆燃料到冷却剂裂变产物(I-129)活性的影响。首先,利用ORIGEN-2作为子程序,建立了裂变产物释放到主冷却剂的计算模型。该模型基于一组动力学模型微分方程,该动力学模型包括燃料到间隙释放模型、间隙到冷却剂泄漏模型和booth扩散模型。开发了基于Matlab的一次冷却剂裂变产物活度(FPAPC)计算程序。计算了一次热输运系统中I-129活性的变化,发现I-129的计算值与已发表的数据值一致,偏差在2% - 3%以内。最后,研究了冷却剂净化速率、扩散常数和气体逸出速率对I-129活性的影响,结果表明冷却剂净化速率是一次回路裂变产物活性最敏感的参数。对于冷却剂净化速率常数(Β)从- 10%到+10%的步骤变化5%,反应堆运行200天后的活度变化为23.1%。
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