57Co和68Ge/68Ga密封废放射源表征与记录的测量技术

IF 0.9 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY
Dimitris Mavrikis, Tatiana Siarafera, E. Ntalla, A. Markopoulos, A. Ioannidou, A. Savidou
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引用次数: 0

摘要

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