Journal Issue: Nuclear Energy and Technology (NUCET)
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Volume
2025-11
Number
3
Issue Date
Journal Title
Nuclear Energy and Technology (NUCET)
Journal ISSN
2452-3038
Том журнала
Том журнала
Nuclear Energy and Technology (NUCET)
Nuclear Energy and Technology (NUCET) (2025-11)
Статьи
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Assessment of the capabilities of the MBIR reactor’s horizontal experimental channels for neutron therapy
(НИЯУ МИФИ, 2025) Kravets, S. V.; Klinov, D. A.; Kurachenko, Yu. A.
The paper presents the results of determining the possibility of using the horizontal experimental channels of the MBIR reactor for neutron capture therapy studies. The collimator configuration for the neutron beam extraction with specified properties was justified computationally. The peculiarities of the reactor give grounds for a positive assessment of this prospect, primarily the hard spectrum and the uniquely high intensity of the beams. The paper considers the capability of channel No.5 as the most suitable for neutron capture therapy due to a combination of characteristics. The simplest possible axisymmetric collimator was selected for the calculations to assess the key functionalities of neutron capture therapy. The configuration and material composition of the collimator are defined by the experience of calculations. Two fundamental characteristics were analyzed to assess the capabilities of the neutron beam of MBIR’s channel No.5 for neutron capture therapy. These are the dose in the target (soft tumor tissue) containing 65 ppm of 10B, and the dose in healthy tissue containing 18 ppm of 10B. The task in the series of calculations was as follows: to determine the dynamics of the key values for neutron capture therapy with a variable thickness of the moderator in the collimator channel – the time for gaining a fixed “therapeutic” dose in the target (tumor) and the time for gaining the maximum “tolerance” dose in healthy tissue when the target moves along the depth of the phantom. The distribution of these characteristics through the depth of the tissue allows us to conclude that the beam extraction configuration under consideration is effective. The obtained results of the spectral neutron distribution at the outlet of channel No.5 and the estimated dose characteristics in healthy tissue and in the tumor confirm that it is technically possible to use this channel for neutron capture therapy.
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Development of an international system of education and professional training of specialists in the field of nuclear technologies for food and agriculture
(НИЯУ МИФИ, 2025) Panov, A. V.; Koz’min, G. V.
The article presents the experience of training foreign students of Rosatom State Corporation’s flagship universities at the MEPhI Resource Center. It is shown that over the period 2018–2024, more than 500 bachelor’s, specialist and master’s students from 33 countries studying at the five largest flagship universities of the state corporation (VSU, MEPhI, SPbPU, TPU, UrFU) underwent practical training in English and Russian at the Resource Center of Obninsk Institute for Nuclear Power Engineering (IATE MEPhI). Students were trained in six educational programs of 13 and 14 specialty groups. In the field of non-energy application of nuclear technologies, practice-oriented training at the Resource Center is carried out to a greater extent on radiation technologies in agriculture and the food industry. High results of cooperation in training foreign students in the field of agro-nuclear technologies between the IATE MEPhI and the National Research Center “Kurchatov Institute” – RIRAE were noted. Practical training of students at RIRAE is carried out on a unique gamma-installation GUR-120 for irradiation of agricultural raw materials and food products for the purposes of phytosanitary and microbiological safety, increase in shelf life, radiation stimulation. The competencies acquired by students in the field of agricultural radiation technologies are in demand by them when applying for jobs in the Centers of Nuclear Science and Technology. The interaction of the Resource Center of the IATE MEPhI and the leading research institutes of Obninsk in training foreign students is the basis for the development of the international scientific and educational center “Obninsk Tech” for training personnel for foreign businesses of the State Corporation “Rosatom” in the nuclear industry and related areas of application of nuclear technologies.
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Ring laser fusion: A novel approach
(НИЯУ МИФИ, 2025) Makar, A. K.
Laser-induced nuclear fusion offers the tantalizing prospect of a clean, virtually limitless energy source. Traditional inertial confinement fusion (ICF) approaches struggle with challenges in laser efficiency, beam uniformity, and target design. The present research paper proposes a novel method of laser-induced nuclear fusion utilizing a ring laser configuration. The ring laser’s unique geometry enables highly focused, omnidirectional energy delivery to a fusion fuel target. This design aims to overcome the limitations of traditional ICF systems by enhancing energy deposition efficiency and increasing compression symmetry.Numerical simulations using specialized codes such as HYADES,LILAC and VORPAL has been used to investigate the potential advantages of this concept.
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Analysis of excitation function for an induced reaction by nucleon on Arsenic-75 isotope using COMPLET code
(НИЯУ МИФИ, 2025) Zegeye, S. M.; Asres, Yi. H. ; Belete, G. D.; Mekuriyaw, T. A.; Alemu, Ye. E.; Worku, K. T.; Abeje, M. A.
Nucleon-induced nuclear reactions are a significant field in nuclear physics with numerous applications like as in the production of medically important radioisotopes. The primary objective of this study is to analyze the excitation function of nucleon-induced nuclear reactions on the arsenic-75 isotope across projectile energies from 10 MeV to 100 MeV using COMPLET code. The excitation functions of the seven reaction channels: 75As(p, 3n)73Se, 75As(p, pn)74As, 75As(p, p5n)70As, 75As(p, p2p)73As, 75As(p, n)75Se, 75As(n, 2n)74As, and 75As(n, p)75mGe were investigated, analyzed and compared with experimental data within the energies from 10 MeV to 100 MeV. The calculated excitation functions showed strong agreement with experimental data obtained from the EXFOR data base, as assessed using Pearson’s correlation coefficient. Both pre-equilibrium and equilibrium nuclear excitation functions for all nucleon-induced reaction channels displayed a strong correlation with experimental results, except for the neutron-induced reaction channel, 75As(n, p)75mGe, which exhibited a moderate correlation. Studies have indicated that the pre-equilibrium reaction mechanism primarily governs the high-energy segment of the excitation function, whereas the low-energy segment is dominated by the equilibrium reaction mechanism for both neutron and proton-induced nuclear reactions on arsenic-75. Thus, utilization of the COMPLET code and the EXFOR data base has facilitated a detailed analysis of induced nuclear reactions in producing radionuclides with diverse applications.
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Preliminary performance evaluation of an LEU+ based dual-cooled duplex UO2-ThO2 fuel for advanced PWR assembly
(НИЯУ МИФИ, 2025) Rifai. H.; Kabach, O.; Chakir, E. M.; Sadoune, Z.
This study presents a comprehensive neutronic analysis of dual-cooled annular duplex fuel assemblies incorporating UO2-ThO2 composition for application in advanced pressurized water reactors (PWRs). The investigation employs a 13 × 13 fuel assembly configuration to evaluate the operational enhancement potential of modern reactor systems. The research methodology focuses on the comparative assessment of burnup characteristics across varying uranium enrichment levels, benchmarking the neutronic performance of dual-cooled duplex fuel against conventional solid 17 × 17 and dual-cooled 13 × 13 UO2 assemblies.
The results demonstrate that the proposed UO2-ThO2 dual-cooled duplex fuel configuration with 7 wt.% U-235 achieves discharge burnup equivalent to that of conventional solid UO2 assemblies. Safety analysis encompasses the quantification of plutonium isotope production and minor actinide generation, revealing that dual-cooled duplex assemblies produce significantly reduced quantities of plutonium isotopes and lower concentrations of minor actinides, including neptunium (Np), americium (Am), and curium (Cm), relative to conventional all-UO₂ assemblies. Reactivity coefficient analysis confirms that both the fuel temperature coefficient (FTC) and moderator temperature coefficient (MTC) maintain consistently negative values throughout the operational cycle. These coefficients not only satisfy but exceed the established safety criteria for PWR operations, thereby demonstrating the enhanced safety margins and operational performance characteristics inherent to the dual-cooled duplex fuel assembly design.