Shuyi Sun , Chang Li , Yinqi Lei , Weiliang Jin , Liangliang Lv , Baowei Ding , Gongping Li
{"title":"Research on online monitoring methods for plutonium concentrations","authors":"Shuyi Sun , Chang Li , Yinqi Lei , Weiliang Jin , Liangliang Lv , Baowei Ding , Gongping Li","doi":"10.1016/j.nima.2025.170459","DOIUrl":null,"url":null,"abstract":"<div><div>In recent years, with the increasing global demand for clean, low-carbon, and reliable energy, nuclear energy has gained more attention and investment as a crucial component. As nuclear power plants are being constructed and operated on a large scale, the amount of nuclear waste discharged from reactors is also increasing. Currently, the PUREX reprocessing method is commonly used for recycling nuclear waste, which requires real-time measurement of nuclide concentrations in the solution to calculate the amount of material to be added. The traditional method involves staff sampling and laboratory analysis. Although this method is highly accurate, the detection results are delayed, and there is a certain radiation risk. Therefore, designing an efficient online monitoring system for spent fuel solution concentration is important for the recycling of spent fuel. While the online monitoring technology for uranium solutions is relatively mature, research on online monitoring of plutonium solutions is scarce. Against this backdrop, this paper simulates and designs an online monitoring system for plutonium concentration. Using the Geant4 simulation software, a model is designed with a silicon drift detector to explore the relationship between different concentrations of plutonium solution and its spontaneous X-ray intensity. A method for measuring plutonium concentration using spontaneous X-ray emission is proposed and validated. The paper also provides reasonable suggestions regarding the sample tube and detector parameters. Based on research into plutonium's spontaneous alpha decay, a combination of an X-ray machine and uranyl nitrate solution is proposed as an equivalent substitute model for corresponding concentrations of plutonium solution. The appropriate energy, angle, and time parameters for this model are determined through simulation, and its accuracy is experimentally verified to meet market demands, offering a new feasible solution for the calibration of plutonium concentration monitoring instruments. This provides valuable reference for the process design and management of spent fuel reprocessing.</div></div>","PeriodicalId":19359,"journal":{"name":"Nuclear Instruments & Methods in Physics Research Section A-accelerators Spectrometers Detectors and Associated Equipment","volume":"1075 ","pages":"Article 170459"},"PeriodicalIF":1.5000,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Instruments & Methods in Physics Research Section A-accelerators Spectrometers Detectors and Associated Equipment","FirstCategoryId":"101","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0168900225002608","RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"INSTRUMENTS & INSTRUMENTATION","Score":null,"Total":0}
引用次数: 0
Abstract
In recent years, with the increasing global demand for clean, low-carbon, and reliable energy, nuclear energy has gained more attention and investment as a crucial component. As nuclear power plants are being constructed and operated on a large scale, the amount of nuclear waste discharged from reactors is also increasing. Currently, the PUREX reprocessing method is commonly used for recycling nuclear waste, which requires real-time measurement of nuclide concentrations in the solution to calculate the amount of material to be added. The traditional method involves staff sampling and laboratory analysis. Although this method is highly accurate, the detection results are delayed, and there is a certain radiation risk. Therefore, designing an efficient online monitoring system for spent fuel solution concentration is important for the recycling of spent fuel. While the online monitoring technology for uranium solutions is relatively mature, research on online monitoring of plutonium solutions is scarce. Against this backdrop, this paper simulates and designs an online monitoring system for plutonium concentration. Using the Geant4 simulation software, a model is designed with a silicon drift detector to explore the relationship between different concentrations of plutonium solution and its spontaneous X-ray intensity. A method for measuring plutonium concentration using spontaneous X-ray emission is proposed and validated. The paper also provides reasonable suggestions regarding the sample tube and detector parameters. Based on research into plutonium's spontaneous alpha decay, a combination of an X-ray machine and uranyl nitrate solution is proposed as an equivalent substitute model for corresponding concentrations of plutonium solution. The appropriate energy, angle, and time parameters for this model are determined through simulation, and its accuracy is experimentally verified to meet market demands, offering a new feasible solution for the calibration of plutonium concentration monitoring instruments. This provides valuable reference for the process design and management of spent fuel reprocessing.
期刊介绍:
Section A of Nuclear Instruments and Methods in Physics Research publishes papers on design, manufacturing and performance of scientific instruments with an emphasis on large scale facilities. This includes the development of particle accelerators, ion sources, beam transport systems and target arrangements as well as the use of secondary phenomena such as synchrotron radiation and free electron lasers. It also includes all types of instrumentation for the detection and spectrometry of radiations from high energy processes and nuclear decays, as well as instrumentation for experiments at nuclear reactors. Specialized electronics for nuclear and other types of spectrometry as well as computerization of measurements and control systems in this area also find their place in the A section.
Theoretical as well as experimental papers are accepted.