Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources

IF 0.9 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Technology & Radiation Protection Pub Date : 2023-01-01 DOI:10.2298/ntrp2301053m
Dimitris Mavrikis, Tatiana Siarafera, E. Ntalla, A. Markopoulos, A. Ioannidou, A. Savidou
{"title":"Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources","authors":"Dimitris Mavrikis, Tatiana Siarafera, E. Ntalla, A. Markopoulos, A. Ioannidou, A. Savidou","doi":"10.2298/ntrp2301053m","DOIUrl":null,"url":null,"abstract":"The present work concerns the development of a technique for activity determination of 68Ge/68Ga and 57Co disused radioactive sources. This technique aims to determine the activity of these sources by measuring and Monte Carlo simulation using the MCNPX code. Therefore, efficiency calibrations of the 3 x 3 NaI(Tl) detector for specific source geometries were carried out. Spectrums for two types of disused radioactive sources were collected for different measurement times. The characteristic gamma rays of a flood source containing 57Co and a line source containing 68Ge/68Ga, were used. In case of 68Ge/68Ga, the annihilation peak of 511 keV was also used considering the disused radioactive sources as a positron emitter. Sources of the mentioned types with certified nominal activities were used to validate MCNPX models. For the 57Co source, 15 minutes measuring time was adequate for activity determination, and 2 hours measuring time provided adequate sensitivity, at the level of general clearance. For 68Ge/68Ga line source, 15 minutes measurement was adequate for activity determination by using the 511 keV from the annihilation of 1899.1 keV positrons.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":0.9000,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Technology & Radiation Protection","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.2298/ntrp2301053m","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: 0

Abstract

The present work concerns the development of a technique for activity determination of 68Ge/68Ga and 57Co disused radioactive sources. This technique aims to determine the activity of these sources by measuring and Monte Carlo simulation using the MCNPX code. Therefore, efficiency calibrations of the 3 x 3 NaI(Tl) detector for specific source geometries were carried out. Spectrums for two types of disused radioactive sources were collected for different measurement times. The characteristic gamma rays of a flood source containing 57Co and a line source containing 68Ge/68Ga, were used. In case of 68Ge/68Ga, the annihilation peak of 511 keV was also used considering the disused radioactive sources as a positron emitter. Sources of the mentioned types with certified nominal activities were used to validate MCNPX models. For the 57Co source, 15 minutes measuring time was adequate for activity determination, and 2 hours measuring time provided adequate sensitivity, at the level of general clearance. For 68Ge/68Ga line source, 15 minutes measurement was adequate for activity determination by using the 511 keV from the annihilation of 1899.1 keV positrons.
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
57Co和68Ge/68Ga密封废放射源表征与记录的测量技术
本文研究了一种测定68Ge/68Ga和57Co废弃放射源活度的方法。该技术旨在通过使用MCNPX代码进行测量和蒙特卡罗模拟来确定这些源的活动。因此,对特定源几何形状的3 × 3 NaI(Tl)探测器进行了效率校准。在不同的测量时间收集了两种废弃放射源的光谱。采用含57Co的洪水源和含68Ge/68Ga的线源的特征伽马射线。在68Ge/68Ga的情况下,考虑到废弃的放射源作为正电子发射器,也采用了511 keV的湮灭峰。使用具有认证标称活动的上述类型的来源来验证MCNPX模型。对于57Co源,15分钟的测量时间足以测定活度,2小时的测量时间在一般间隙水平上提供足够的灵敏度。对于68Ge/68Ga线源,利用1899.1 keV正电子湮灭产生的511 keV来测定活度,测量15分钟就足够了。
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
Nuclear Technology & Radiation Protection
Nuclear Technology & Radiation Protection NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.00
自引率
41.70%
发文量
10
审稿时长
6-12 weeks
期刊介绍: Nuclear Technology & Radiation Protection is an international scientific journal covering the wide range of disciplines involved in nuclear science and technology as well as in the field of radiation protection. The journal is open for scientific papers, short papers, review articles, and technical papers dealing with nuclear power, research reactors, accelerators, nuclear materials, waste management, radiation measurements, and environmental problems. However, basic reactor physics and design, particle and radiation transport theory, and development of numerical methods and codes will also be important aspects of the editorial policy.
期刊最新文献
Study on kinetic parameters of pebble bed reactor with TRISO duplex fuel Influence of electromagnetic pollution of the electron beam generator and high-energy radioactive source on the memory components Influence of ionizing radiation on the stochasticity of overvoltage protection at low, medium, and high voltage levels in gas surge arresters Assessing radiation hazards associated with natural radioactivity in building materials in Ho Chi Minh City, Vietnam Study on occupational exposure of medical staff caused by induced radioactivity in the treatment room of medical heavy-ion facility
×
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