Isotopic Identification of Photofissed Nuclear Materials in Stainless Steel Containers Using Delayed Gamma-Rays

Pylypchynets, I.V.; Парлаг, О. О.; Maslyuk, V. T.; Oleynikov, E.V.; Lengyel, A.

doi:10.46813/2022-141-103

Cited by 3 publications

(1 citation statement)

References 16 publications

(37 reference statements)

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“…As a rule, such nuclear materials are stored in sealed containers. One of the main methods for analyzing the isotopic and quantitative composition of shielded nuclear materials is based on gamma-ray spectrometric measurements of their characteristic [2] or stimulated gamma radiation [3]. In addition, during the analysis, there is a need for gamma-spectrometric measurements of high-intensity γ-radiation fluxes from high-level nuclear materials.…”

Section: Introductionmentioning

confidence: 99%

EMPIRICAL FORMULA FOR THE DEPENDENCE OF HPGe-DETECTOR EFFICIENCY ON ENERGY AND DISTANCE FOR SHIELDED GAMMA-RAY SOURCES

Pylypchynets¹,

Lengyel²,

Парлаг³

et al. 2023

Problems of Atomic Science and Technology

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The accuracy of gamma-spectrometric measurements in the isotopic analysis of shielded nuclear materials depends on the accuracy of the detector calibration in terms of energy efficiency, which should take into account corrections related to the measurement geometry and the absorption of γ-radiation by the shield material. The results of experimental studies of the energy efficiency of the HPGe-detector measured at fixed distances between the calibration source and the detector (50 and 100 mm) in the presence and absence of an absorbing shield made of stainless steel 12X18H10T (thickness ‒ 9.6 mm) are presented. On the basis of experimental data, an empirical description of the efficiency dependence for fixed distances between the gamma radiation source and the detector in the presence of a stainless steel absorbing shield was obtained.

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Section: Introductionmentioning

confidence: 99%

EMPIRICAL FORMULA FOR THE DEPENDENCE OF HPGe-DETECTOR EFFICIENCY ON ENERGY AND DISTANCE FOR SHIELDED GAMMA-RAY SOURCES

Pylypchynets¹,

Lengyel²,

Парлаг³

et al. 2023

Problems of Atomic Science and Technology

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Gamma-Ray Self-Absorption Corrections in Stainless Steel 12Х18Н10Т for the Needs of Non-Destructive Isotopic Differentiation of Shielded Actinides

Pylypchynets,

Lengyel,

Parlag

et al. 2024

International Journal of Innovative Science and Research Techno

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One of the main tasks of nuclear science and technology is related to the development of methods of countermeasures, circulation, non-proliferation, and safe use of shielded nuclear materials - actinides. To solve this problem, information about their isotopic and quantitative composition is necessary. One of the main methods of non-destructive differentiation of shielded actinides, which is constantly being developed, is based on the use of their characteristic or stimulated gamma rays. For its implementation, information on the self- absorption of gamma rays of a wide energy range in screens (combinations of the elements from which they are made) is required. The results of calculations of the dependence of the self-absorption values of gamma rays in stainless steel 12X18N10 on their energy (100 keV ÷ 3000 keV) at fixed values of the screen thickness (0.1 ÷ 20 mm) are presented in the article. It was established that the self-absorption of gamma rays has smaller values for the energy range of spectrometric measurements of stimulated gamma rays compared to the energy range of spectrometry of characteristic gamma rays during the differentiation of shielded actinides. The energy range of gamma rays from 1000 to 3000 keV was determined, which can be considered optimal for the spectrometry of stimulated gamma rays from shielded actinides during their differentiation.

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Optimal scheme for stimulating photofission of shielded nuclear materials on the Microtron M-30: a combination of theoretical and experimental studies

Pylypchynets¹

2022

Scientific Herald of Uzhhorod University Series Physics

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Relevance. The photofission of shielded nuclear materials is widely used to develop methods for non-destructive analysis of their isotopic composition. To stimulate the photofission reaction, bremsstrahlung beams obtained on electronic accelerators are used. Their parameters significantly depend on the design features of accelerators and sample activation schemes. Purpose. Theoretical modelling of parameters of an optimal scheme for stimulating the photofission of shielded nuclear materials on an electronic accelerator – Microtron M-30 for the analysis of their isotopic composition, considering its technical characteristics, and experimental verification of its parameters. Methodology. Theoretical calculations of the parameters of bremsstrahlung beams for the Microtron M-30 were carried out using the GEANT4 toolkit. For experimental studies of the influence of structural elements of the optimal stimulation scheme on the integral characteristics of inhibitory photons, secondary photoneutrons, the method of activation of detectors made of gold was used; for residual electrons – the transmission method based on a passage chamber and a Faraday cylinder. Results. As a result of the combination of theoretical and experimental studies, optimal parameters of the activation scheme of nuclear materials on the Microtron M-30 have been established. The scheme provides experimental conditions under which the losses of bremsstrahlung photon beams interacting with the test samples (with energies ≥6 MeV) do not exceed 35% of their initial values, with the practical absence of residual electrons (98% of electrons are absorbed) and secondary photoneutrons (no more than 1E-9 n/e). Conclusions. The parameters of the developed stimulation scheme for the Microtron M-30 can be applied to various types of accelerators, considering their design features, characteristics of the samples, and implemented activation schemes

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Isotopic Identification of Photofissed Nuclear Materials in Stainless Steel Containers Using Delayed Gamma-Rays

Cited by 3 publications

References 16 publications

EMPIRICAL FORMULA FOR THE DEPENDENCE OF HPGe-DETECTOR EFFICIENCY ON ENERGY AND DISTANCE FOR SHIELDED GAMMA-RAY SOURCES

EMPIRICAL FORMULA FOR THE DEPENDENCE OF HPGe-DETECTOR EFFICIENCY ON ENERGY AND DISTANCE FOR SHIELDED GAMMA-RAY SOURCES

Gamma-Ray Self-Absorption Corrections in Stainless Steel 12Х18Н10Т for the Needs of Non-Destructive Isotopic Differentiation of Shielded Actinides

Optimal scheme for stimulating photofission of shielded nuclear materials on the Microtron M-30: a combination of theoretical and experimental studies

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