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Лаборатория прикладной спектрометрии и неразрушающих методов измерений ядерных материалов (Кафедра №5 ИЯФиТ)

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Experience of long-term U-Al fuel performance in research reactors with low energy generation
(2020) Andreev, D. V.; Gaiduchenko, A. B.; Alferov, V. P.; Geraskin, N. I.; Kozhin, A. F.; Kruglikov, A. E.; Ozherelev, S. A.; Serebryakov, A. A.; Shchurovskaya, M. V.; Yakovlev, L. I.; Aleeva, T. B.; Алферов, Владимир Петрович; Гераскин, Николай Иванович; Кожин, Александр Федотович; Кругликов, Антон Евгеньевич; Ожерельев, Сергей Анатольевич; Щуровская, Мария Владимировна; Яковлев, Леонид Иванович; Алеева, Татьяна Борисовна
© Published under licence by IOP Publishing Ltd.Life cycle extension practices for U-Al fuel in Al cladding used at the OR and the IRT MEPhI research reactors are discussed. The IRT MEPhI reactor uses tube type IRT-3M FA with dispersed UO2-Al fuel meat and SAV-1 aluminum alloy as cladding. The OR reactor uses pin type fuel elements with U-Al alloy fuel meat in cladding of Al alloy AMSN. The necessity of life cycle extension for the fuel elements is caused by a large calendar time of fuel assembly operation (10-30 years) and regulatory bodies concerns about this issue. The results of fuel cladding corrosion effects estimation using available empirical correlations for the corrosion rate and the rate of oxide film growth are presented. The results of visual inspection of the fuel elements are shown. Water chemistry monitoring practises in the reactor pool and in spent fuel storage are analysed. The successful experience of the IRT MEPhI (in 2003-2007) on repeated operation of the fuel assemblies previously discharged from the core (after the storage over 5-21 years) is presented.
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Investigation of radioactive reactor graphite by gamma-spectrometric method
(2020) Bazdnikin, N. I.; Zubarev, V. N.; Aleeva, T. B.; Зубарев, Виктор Николаевич; Алеева, Татьяна Борисовна
© Published under licence by IOP Publishing Ltd.In this research radioactive contamination of graphite of the 4th block of the Leningrad NPP was determined using the method of gamma-spectrometric analysis. The obtained results of the specific activity of isotopes were compared with the contamination of the graphite masonry of industrial uranium-graphite reactors. It was found that in comparison with graphite of industrial uranium-graphite reactors, the LAES-4 masonry has less contamination with decay products and actinoids, which indicates that, unlike industrial reactors, there were no incidents of fuel Rod destruction in power plants. But at the same time, it was noted that the RBMK masonry has an increased content of60Co. It was determined that this is due to the increased content of iron and cobalt impurities in unradiated graphite for RBMK. This research is important in terms of confirming the view that spent graphite from each specific uranium-graphite reactor has important features that need to be taken into account when planning decommissioning measures.
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Comparing Metrological Characteristics of Methodologies for Determining Uranium Enrichment Using NaI and LEGe Detectors
(2020) Bartev, N. O.; Aleeva, T. B.; Zubarev, V. N.; Алеева, Татьяна Борисовна; Зубарев, Виктор Николаевич
© Published under licence by IOP Publishing Ltd.The purpose of this work was to compare metrological characteristics of methodologies for determining uranium enrichment using different types of detectors and the IMCA software. This software includes several programs (applications), two of which were used in this work: IMCN was used for NaI detector, and IMCG was used for LEGe detector. The principle of enrichment measurement is that the uranium enrichment is directly proportional to the count rate at the 185.7 keV peak resulting from decay of 235U, provided that the sample's thickness is sufficient ("infinite thickness"method). Based on the results of repeated measurements of samples with known enrichment, metrological characteristics of methodologies for different count times were calculated and compared. Analysis of the results led us to the following conclusions: reproducibility of results when performing measurements using LEGe detector is just as good as when using NaI detector; at that, uncertainty reported by the IMCG program is almost the same as the reproducibility estimate, while the IMCN program reports uncertainties that are several times smaller than the estimated reproducibility.
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Институт ядерной физики и технологий
Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.
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Направления исследований: - Методы измерения характеристик ядерных материалов и радиоактивных отходов Разработка гамма/Х-спектрометрических и нейтронных методов измерения изотопного состава и массы ядерных материалов в образцах разной физико-химической формы, в том числе в топливе ядерных реакторов, твэлах, контейнерах и т.д. - Методы измерения выгорания отработавших тепловыделяющих сборок ядерных реакторов Разработка неразрушающих методов измерения выгорания и остаточного содержания делящихся изотопов в отработавших тепловыделяющих сборках исследовательских реакторов - Нейтронно-активационный анализ Применение нейтронно-активационных методов для исследования нейтронно-физических характеристик материалов, анализа состава примесей и определения характеристик нейтронных полей - Исследования радиоактивного загрязнения объектов окружающей среды Отбор проб окружающей среды и анализ их радиоактивного загрязнения с применением гамма-, бета- и альфа-спектрометрических методов
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