2020, Ibragimov, R. F., Kokorev, Ya. A., Denisenko, A. P., Ryabeva, E. V., Samosadny, V. T., Hasnaoui, H., Ибрагимов, Ренат Фаридович, Кокорев, Яков Александрович, Денисенко, Анастасия Павловна, Рябева, Елена Васильевна

© 2020 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.The paper presents the results of experimental determination of the induced activity in copper"/aluminum"based activation detectors when irradiated with neutrons with energy of about 14 MeV. The activation detectors were square"shaped metal plates with a thickness from 1.0 to 1.5 mm and a side size about 5.0 cm. Such samples require a specific method for measuring the induced activity, which will take into account large sizes of the plate relate to the size of gamma"detector or neutron source. The detectors described in this work can be used to study low"intensity neutron fluxes (with a flux density of up to 106n/cm2·s). It is shown that, when working with such detectors, the usual methods for calculating the induced activity in thin activation detectors are applicable, with corrections that take into account the emerging features of the "neutron source - activation detector" and "activation detector - secondary radiation detector" geometries. The effects of absorption of primary and secondary radiation by the detector substance are also revealed. The Geant4 tools were used to calculate the geometric factors and theoretical induced activity value. The study confirms the applicability of such activation detectors for solving the problem of determining the yield of neutrons with energy of about 14 MeV from a neutron generator target. The results of the experiments coincide, within the margin of error, with the results of simulations performed using the Geant4 tools.

2022, Gaganov, V. V., Ryabeva, E. V., Molodtsev, D. A., Ibragimov, R. F., Vershinin, I. S., Kokorev, Y. A., Urupa, I. V., Рябева, Елена Васильевна, Ибрагимов, Ренат Фаридович, Кокорев, Яков Александрович, Урупа, Илья Викторович

2018, Ибрагимов, Р. Ф., Ибрагимов, Ренат Фаридович, Кадилин В.В.

В ходе выполнения данной диссертационной работы доказана как возможность, так и актуальность использования детекторов ионизирующего излучения с алмазным чувствительным элементом в качестве регистрирующего элемента системы мониторинга для нейтронного генератора.

2023, Ryabeva, E. V., Denisenko, A. P., Ibragimov, R. F., Urupa, I. V., Рябева, Елена Васильевна, Денисенко, Анастасия Павловна, Ибрагимов, Ренат Фаридович, Урупа, Илья Викторович

2024, Блохин, Н. О., Рябева, Е. В., Ибрагимов, Р. Ф., Чакилев, О. В., Чакилев, Олег Васильевич, Рябева, Елена Васильевна, Ибрагимов, Ренат Фаридович

В работе рассмотрены основные пассивные и активные нейтронные методы обнаружения делящегося вещества в образце, применяемые, например, в досмотровых установках и при контроле отходов ядерного топливного цикла. Приведены расчеты для оценки возможности использования данных методов при обнаружении обогащенного урана. Подробно рассмотрен метод по анализу времени жизни нейтрона в материалах установки (DDA). Разработана модель для обнаружения наличия 235U в образце DDA методом с использованием инструментов пакета программ Geant4. В разработанной модели предложен и проверен критерий определения массы U235. Предлагаемые модель и критерий могут значительно упростить процесс разработки и оптимизации параметров дорогостоящих устройств по обнаружению делящихся веществ за счет создания цифровой модели.

2022, Gaganov, V. V., Vershinin, I. S., Ryabeva, E. V., Molodtsev, D. A., Urupa, I. V., Ibragimov, R. F., Lupar, E. E., Savin, D. I., Рябева, Елена Васильевна, Урупа, Илья Викторович, Ибрагимов, Ренат Фаридович, Лупарь, Евгений Эдуардович

© 2022 Elsevier B.V.This article demonstrates the performance of the EJ-276 plastic scintillator-based neutron radiation spectrometer with neutron–gamma separation capability. This work continues the earlier research devoted to the demonstration of the EJ-276 spectrometric capabilities. An NG-150M generator located at RFNC-VNIIEF (Sarov) was used as a neutron source. Neutron energy distribution was unfolded for several angles between neutron generator and the target-scintillator direction using a Geant4 simulated response matrix and a set of experimental response spectra. The experimental neutron spectra are compared with the calculated ones. DT neutron unfolded energy uncertainty is 2%. The accompanying gamma radiation spectra were unfolded with the same uncertainty.

2020, Yurkov, D. I., Mikerov, V. I., Ryabeva, E. V., Idalov, V. A., Ibragimov, R. F., Urupa, I. V., Юрков, Дмитрий Игоревич, Микеров, Виталий Иванович, Рябева, Елена Васильевна, Ибрагимов, Ренат Фаридович, Урупа, Илья Викторович

© 2020 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.A package of organizational and engineering arrangements has been considered to ensure safe operation of portable neutron generators in a university environment. The dose rate from the fast neutron generator's neutron radiation in rooms permanently or temporarily occupied by personnel or the public was mathematically simulated using the GEANT4 code. Dedicated biological shielding has been developed and built, and measures have been put in place for the radiation dose monitoring using state of the art health physics equipment and for remote control of the fast neutron generator's neutron yield, as well as to limit the neutron yield and the neutron generator operating time, to prevent access into rooms with operating generators, and to monitor the radiation dose values using special purpose devices (dosimeters, radiometers, etc.). It has been shown that the biological shielding built and the fast neutron generator's yield of up to 5.106 n/s provide for the equivalent dose rate in permanently occupied rooms not exceeding 0.3 μ Sv/h, which is an order of magnitude as low as the university dose rate limit of 3 μSv/h.

2021, Ryabeva, E. V., Urupa, I. V., Lupar, E. E., Kadilin, V. V., Skotnikova, A. V., Kokorev, Y. A., Ibragimov, R. F., Рябева, Елена Васильевна, Урупа, Илья Викторович, Лупарь, Евгений Эдуардович, Кокорев, Яков Александрович, Ибрагимов, Ренат Фаридович

© 2021 Elsevier B.V.Calibration of the scintillator detector based on a plastic scintillator EJ-276 for neutron–gamma pulse shape discrimination (PSD) experiments was carried out. Optical characteristics of electrons as the function of their deposited energy were experimentally studied. The calibration was implemented by comparing the experimental response from gamma sources with that obtained by means of GEANT4 simulation. It is shown that a similar relationship for protons built on the basis of the published data on EJ-299-33, is also applicable to EJ-276 which confirms the information about the equivalence of these scintillators. The experimental response of the EJ-276 to 14 MeV neutrons is compared with Geant4 simulation data. The experimental and simulated data were also presented as the function of light output in electronic equivalent (MeVee) obtained by both exponential and Birks’ laws. An experimental setup was constructed with Ø51 × 51 mm EJ-276 scintillator. The CAEN DT5730B digitizer was used for PSD signal discrimination. Based on the current experiments and the earlier published data a calibration relation between the setup channels and the light output was obtained in electronic equivalent (MeVee).

2022, Savin, D. I., Urupa, I. V., Lupar, E. E., Ibragimov, R. F., Ryabeva, E. V., Урупа, Илья Викторович, Лупарь, Евгений Эдуардович, Ибрагимов, Ренат Фаридович, Рябева, Елена Васильевна

2023, Ibragimov, R. F., Urupa, I. V., Ryabeva, E. V., Ибрагимов, Ренат Фаридович, Урупа, Илья Викторович, Рябева, Елена Васильевна