Abstract
The paper provides the analysis of the uncertainty in determining the uranium samples enrichment using non-destructive methods to ensure the functioning of the nuclear materials accounting and control system. The measurements were performed by a scintillation detector based on a sodium iodide crystal and the semiconductor germanium detector. Samples containing uranium oxide of different masses were used for the measurements. Statistical analysis of the results showed that the maximum enrichment error in a scintillation detector measurement can reach 82%. The bias correction, calculated from the data obtained by the semiconductor detector, reduces the error in the determination of uranium enrichment by 47.2% in average. Thus, the use of bias correction, calculated by the statistical methods, allows the use of scintillation detectors to account and control nuclear materials.
Highlights
One of the systems providing the required control level over the activities in the nuclear industry is a system of accounting and control of nuclear materials
Published under licence by IOP Publishing Ltd scintillation detector (Canberra, model 802-2x2), spectra processing was performed in the Genie-2000 software, and uranium dioxide UO2 with different mass of U235 enrichment by 2% was used as a sample
According to the measurement results analysis, it was found that the measurement bias correction determined using a more accurate method of standard samples analysis as well as mathematical and statistical techniques can reduce the relative systematic error component in the measurements performed by the detector approximately by 47.2% in average
Summary
One of the systems providing the required control level over the activities in the nuclear industry is a system of accounting and control of nuclear materials. The development and improvement of non-destructive methods of isotopic composition analysis are directly related to the solution of practical problems in the field of accounting and control of nuclear materials, as well as detection and prevention of illicit trafficking. One of the main methods of non-destructive analysis is the gamma-ray spectrometry which is widely applied for the nuclear materials control. This is a key method in determining the isotopic composition of the nuclear materials and uranium enrichment [1]. The research goal is to optimize the process of the uranium isotopic composition analysis with spectrometric channel based on NaI (Tl) scintillation detector by means of measurement error reduction with statistical methods
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