Determination uranium in solutions by the method of neutron activation analysis with 252Cf radionuclide neutron source

IF 0.9 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Technology & Radiation Protection Pub Date : 2021-01-01 DOI:10.2298/ntrp201217005i
I. S. Ivannikov, S. Markin, V. Zheleznov
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Abstract

A determination option for 238U in solutions by the neutron activation analysis was investigated. A radionuclide treatment based on 252Cf was used as a neutron source. The limit for the determination of uranium using thermal neutrons of 0.1 mg L-1 was determined within the research framework. With the help of preliminary concentration of the sample via the evaporation method, it is possible to further reduce the detection limit by 2-5 times. It is defined that the optimal time for measuring the induced activity of the sample, when working with a short-life isotope of 239U, is 30 min. The influence of the effects of scattering and self-absorption of gamma radiation of the uranium line 74.6 keV on the results of the neutron activation analysis is determined. The studies conducted made it possible to determine uranium by the neutron activation analysis method in solutions of various compositions, in a wide range of concentrations.
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252Cf放射性核素中子源中子活化分析法测定溶液中的铀
研究了用中子活化分析法测定溶液中238U的方法。采用基于252Cf的放射性核素处理作为中子源。在研究框架内确定了利用热中子测定铀的极限为0.1 mg L-1。通过蒸发法对样品进行初步浓缩,可以进一步降低2-5倍的检出限。定义了用短寿命同位素239U测量样品诱导活度的最佳时间为30 min。确定了74.6 keV铀线γ辐射的散射和自吸收效应对中子活化分析结果的影响。所进行的研究使得用中子活化分析法在各种成分、各种浓度的溶液中测定铀成为可能。
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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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