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Validation of the EUCLID/V1 integrated computer code against the BOR-60 experimental data Atom. Energy (IF 0.5) Pub Date : 2024-03-14 D. P. Veprev, S. A. Kuzmichev, A. V. Shershov, N. A. Mosunova, V. F. Strizhov, A. V. Boev, I. Yu. Zhemkov, Yu. V. Naboyshchikov
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Enthalpy and heat capacity of lead in a condensed state Atom. Energy (IF 0.5) Pub Date : 2024-03-13
Abstract The relevance of research into the thermophysical properties of lead is associated with the implementation of a BREST-300 reactor project. The enthalpy of solid and liquid lead in the range of 432–1327 K was measured by the mixing method using a massive isothermal calorimeter. The enthalpy of melting was determined. Approximation equations for the temperature dependence of enthalpy in the
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Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel Atom. Energy (IF 0.5) Pub Date : 2024-03-12 E. F. Mitenkova, N. V. Novikov, E. V. Solovjeva
The use of extended libraries of one-group cross-sections in precision nuclide composition calculations confirms the importance of including high-threshold reactions in the libraries. Particular attention is paid to impurity nuclides, which are increasingly relevant in solving problems of nuclear engineering. The existing ambiguity in the formation of extended libraries with high-threshold reactions
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Coolant nuclid kinetics for fast reactors Atom. Energy (IF 0.5) Pub Date : 2024-03-12 E. F. Seleznev, A. M. Boldyrev, E. P. Lyapin
Within the modernization of programs for calculating nuclide kinetics of BN-600 and BN-800 Beloyarskaya NPP reactors, programs for calculating nuclide kinetics of the fuel and fission products, nuclides in absorbing rods, as well as impurities in structural materials and the coolant, were developed using various methods including the possibility of an uncertainty analysis. The concentration of 116
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Coolant hydrodynamic features at the outlet of a RITM SNPP fuel cassette Atom. Energy (IF 0.5) Pub Date : 2024-03-11 S. M. Dmitriev, T. D. Demkina, A. A. Dobrov, D. V. Doronkov, D. S. Doronkova, D. D. Kuritsin, A. N. Pronin, A. V. Ryazanov
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The effect of charge accumulation in a dielectric under the action of bremsstrahlung with a photon energy above 1 MeV Atom. Energy (IF 0.5) Pub Date : 2024-03-11 B. Yu. Bogdanovich, G. O. Buyanov, A. V. Nesterovich
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A study of plutonium fluoride solubility in LiF–BeF2 melt for the substantiation of a molten salt reactor for Np, Am, Cm transmutation Atom. Energy (IF 0.5) Pub Date : 2024-02-12 M. N. Belonogov, N. D. Dyrda, G. N. Rykovanov, I. V. Sannikov, P. A. Sannikova, V. A. Simonenko, V. G. Subbotin, R. R. Fazylov, D. V. Khmelnitsky, V. A. Shelan, O. V. Shults
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Determining the swelling of mixed nitride uranium-plutonium fuel based on the post-reactor studies of experimental BN-600 and BOR-60 fuel rods Atom. Energy (IF 0.5) Pub Date : 2024-01-31
Abstract A total number of 18 experimental fuel assemblies (FAs), containing mixed nitride fuel rods with claddings of various geometry, were irradiated in an BN-600 core. By the end of 2022, JSC SSC NIIAR had completed the post-reactor studies of 16 ETVS BN-600 nitride fuel rods, 4 fuel rods with a gas sublayer irradiated in the composition of OU‑1 and OU‑2 collapsible irradiation devices, and 3 OU‑4
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Scientific and technical aspects of developing a RITM-200N innovative reactor for SNPPs Atom. Energy (IF 0.5) Pub Date : 2024-01-31 V. V. Petrunin, N. V. Sheshina, S. A. Fateev, A. V. Kurachenkov, D. V. Shchekin, S. M. Brykalov, A. A. Bezrukov
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Utilization of spent nuclear fuel and transuranic actinides in a two-component nuclear power industry Atom. Energy (IF 0.5) Pub Date : 2024-01-26 E. O. Adamov, A. A. Kashirsky, V. I. Rachkov, E. A. Rodina, Yu. S. Khomyakov
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New fuel types for thermal reactors in LOCA conditions Atom. Energy (IF 0.5) Pub Date : 2024-01-09 L. A. Karpuk, V. V. Novikov, M. I. Gozman, O. V. Khomyakov
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Corrosion tests of triuran disilicide fuel pellets Atom. Energy (IF 0.5) Pub Date : 2024-01-05 L. A. Karpyuk, V. I. Kuznetsov, V. V. Novikov, E. N. Mikheev, A. V. Fedotov, A. V. Lysikov, R. B. Sivov, N. M. Rysev, O. A. Bakhteev, M. A. Lutkov
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Assessing the durability of nuclear plant elements under high‑frequency broadband loading Atom. Energy (IF 0.5) Pub Date : 2024-01-05 O. V. Goryunov, S. V. Evropin, S. V. Slovtsov
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Kinetic model of electrochemical aqueous coolant decontamination Atom. Energy (IF 0.5) Pub Date : 2024-01-05 A. L. Shimkevich
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Prospects of SNPPs in the electric power industry Atom. Energy (IF 0.5) Pub Date : 2024-01-05 S. P. Filippov, F. V. Veselov, T. G. Pankrushina
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Modeling of an ACE-L4 experiment on the interaction of the melt with concrete used in the construction of VVER-1000 NPPs Atom. Energy (IF 0.5) Pub Date : 2024-01-05 V. D. Ozrin, A. S. Filippov
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Fast neutron spectrometer based on a diamond sensor detector Atom. Energy (IF 0.5) Pub Date : 2024-01-05 R. F. Ibragimov, I. V. Urupa, E. V. Ryabeva, Y. A. Kokorev, V. V. Gaganov, I. S. Vershinin
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Flow formation features at the inlet to the fuel catridge of a ritm snpp reactor Atom. Energy (IF 0.5) Pub Date : 2023-12-22 S. M. Dmitriev, T. D. Demkina, A. A. Dobrov, D. V. Doronkov, D. S. Doronkova, D. D. Kuritsyn, M. A. Legchanov, A. N. Pronin, A. V. Ryazanov, D. N. Solntsev, D. L. Shipov
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Analysis of fuel cycle scenarios for a two-unit SCWR NPP Atom. Energy (IF 0.5) Pub Date : 2023-12-21 M. V. Kormilitsyn, L. A. Kormilitsyna, Ya. A. Kotov, V. A. Nevinitsa, S. B. Pustovalov, A. A. Sedov, S. S. Simonov, S. A. Subbotin, P. A. Fomichenko
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Development of approaches to regulatory safety in industrial water-electrolysis production of hydrogen at NPPs Atom. Energy (IF 0.5) Pub Date : 2023-12-21 I. A. Kirillov, N. L. Kharitonova, V. A. Simonenko, V. M. Kryukov
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Release of radioactive cesium to the environment during standard npp operations Atom. Energy (IF 0.5) Pub Date : 2023-12-21 D. D. Desyatov, A. A. Ekidin, S. G. Goliboroda
The article analyzes the specific emission and discharge of cesium isotopes at NPPs in the USA, Russia, and Europe for the periods of 2005–2021, 2007–2021, and 1995–2021, respectively. The ranking of NPPs with seven types of reactors according to “best,” “worst,” and “sustainable” categories was carried out. Less than 0.01% of radiation accidents involve radioactive cesium released to the environment
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Scientific and practical aspects of a radiation inspection for a decommissioned NPP unit Atom. Energy (IF 0.5) Pub Date : 2023-12-21 A. S. Gryaznov, E. A. Ivanov, A. S. Korotkov, S. S. Selkin, L. E. Sukhikh, D. A. Sharov
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Study of the Sensitivity of the Calculated Radiation Load on VVER-1000 Internals to the Uncertainty of Initial Data Atom. Energy (IF 0.5) Pub Date : 2023-10-20 Yu. S. Daichenkova, M. A. Kalugin, D. N. Prokhorov, D. A. Shkarovsky
One of the limiting factors of the service life of a nuclear power plant involves the state of the reactor vessel and its internals. The structural materials of the vessel and its internals are subjected to intense irradiation and thermomechanical loads, resulting in radiation embrittlement that affects the mechanical properties of these elements. For this reason, determination of the radiation load
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A Comparative Study of the EP823 Steel Corrosion Resistance in Lead and Lead-Bismuth Coolants Atom. Energy (IF 0.5) Pub Date : 2023-10-20 G. A. Birzhevoy, V. M. Troyanov
The article considers EP823 12% Cr ferrite-martensite steel, selected in terms of the material for fuel rod claddings, as well as the control and protection elements of BREST OD-300 and SVBR-100 reactors. Based on the analysis of the published results of non-isothermal circulation facility tests, a comparison of EP823 steel corrosion rates in a liquid lead and lead-bismuth eutectic system demonstrated
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Informativity of the Status Parameters for Fuel Rod Claddings of Transport NPPs Atom. Energy (IF 0.5) Pub Date : 2023-10-20 S. N. Orlov, A. A. Zmitrodan, R. V. Fomenkov, S. G. Mysik, V. N. Epimakhov, I. A. Dvoryanov
The main parameter for assessing the status of the transport NPP core consists of the total specific activity of iodine in the primary coolant samples 2 h after the sampling. The article analyzes the variations in this parameter of the primary coolant used at the KLT-40S transport nuclear power plant. When taken in the modes of the radiation and technological control, the total specific activity of
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Calculation and Experimental Study of the Interaction Between a KZh Steel Structure and RBMK-1000 Graphite Stack Atom. Energy (IF 0.5) Pub Date : 2023-10-20 A. V. Slobodchikov, A. N. Biryukov, A. P. Rakhmanov, A. A. Podosinnikov, S. A. Koretsky, S. V. Timofeyev, S. M. Usov, A. M. Yevstafyev, D. A. Kondrashin
For the possible operation of power units with the RBMK-1000 reactor during the period of the formation of a graphite stack, NIKIET performed a series of experiments to recreate the force action of the graphite stack on the sealed vessel of the reactor, represented by the KZh metal structure. The experiments justified the joint movement of the graphite stack and 50 mm metal structure with the assumption
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Uncertainty Assessment and Sensitivity Analysis in the Problems of Nuclide Kinetic Modeling Using the Sun Module of BPSD Software Atom. Energy (IF 0.5) Pub Date : 2023-10-20 O. I. Chertovskikh, A. A. Belov, O. N. Andrianova
Features and capabilities of the SUN BPSD module for assessing the error in fuel burnup calculations due to the uncertainty of nuclear data and reactor plant process parameters, as well as fuel irradiation conditions, are described. Using the SUN module, two different methods for estimating the uncertainty of irradiated fuel characteristics were implemented. The post-reactor studies of fuel rods irradiated
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Purification of Regenerated Uranium Hexafluoride from 232, 234, 236U in a Double Cascade with an Additional Feeding Atom. Energy (IF 0.5) Pub Date : 2023-10-20 V. A. Palkin
The paper considers features of enriched regenerated uranium hexafluoride purification from 232, 234, 236U in a double cascade with a supply of uranium hexafluoride wastes for the additional feeding of the first cascade. The effective purification from 236U is carried out in the first cascade at a 235U concentration of less than 20% in long cascades with a large number of stages. The parameters of
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Separation of a Gas Mixture Containing Uranium Hexafluoride, Hydrogen Fluoride, and Chlorine Trifluoride Atom. Energy (IF 0.5) Pub Date : 2023-10-20 O. B. Gromov
The paper describes the design and the process mode of an M-1281 sorption unit for the extraction of uranium hexafluoride and hydrogen fluoride from gases based on chlorine trifluoride or fluorine using the fluorides of lithium and sodium. The extraction of uranium hexafluoride by sodium fluoride yields over 99.8%. Hydrogen fluoride in combination with lithium and sodium fluorides is extracted at 95
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Effects of Accident-Tolerant Nuclear Fuel on NPP Economic Parameters Atom. Energy (IF 0.5) Pub Date : 2023-10-20 E. V. Semenov, V. V. Kharitonov
One of the relevant factors when increasing the competitiveness of water-cooled reactors is the introduction of accident-tolerant fuel to significantly reduce economic risks during NPP operation. The present study aims to develop a methodology for assessing the impact of this fuel on NPP competitiveness criteria. The main attention is paid to the assessment of the maximum permissible increase in production
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Methods for Estimating a Neutron Spectrum Using a Diamond Detector, Plastic Scintillator, and Set of Activation Detectors Atom. Energy (IF 0.5) Pub Date : 2023-10-20 E. V. Ryabeva, A. P. Denisenko, R. F. Ibragimov, I. V. Urupa
The paper considers and compares methods for obtaining spectra of fast neutrons using detectors based on a diamond sensor, an organic (plastic) scintillator for separating neutrons and γ-quants, and a spectrometric set of threshold activation detectors. The neutron spectrum was unfolded using the methods of least squares, Tikhonov regularization, neural networks, and maximum entropy, implemented in
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Conversion of CPS Channels at the Leningrad NPP Power Units 3 and 4 for the Production of Radionuclides Atom. Energy (IF 0.5) Pub Date : 2023-10-20 Yu. V. Alimov, A. N. Biryukov, A. Yu. Mamontov, A. Yu. Nikonov, I. M. Rozhdestvensky, A. V. Slobodchikov
The article considers the possibility of producing isotopes at nuclear power plants with RBMK-1000 reactors. In particular, the specialists of NIKIET developed technical documentation for substantiating the production and expanding the range of medical isotopes at the Phase 2 power units of the Leningrad NPP. The combination of design works and calculation justification demonstrated the possibility
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Approaches to the Assessment of the Cost for the Construction of Innovative Nuclear Power Facilities at the Early Stages of Design Atom. Energy (IF 0.5) Pub Date : 2023-10-20 P. V. Atnyukova, I. V. Presnyakov, D. A. Tolstoukhov
The article considers the specifics of innovative nuclear power facilities from the perspective of cost estimation. Approaches to cost estimation, which aim to ensure the greatest reliability and provide for composing detailed calculations and using analogs, were identified taking into account the initial data available at the pre-design stage. An attention is focused on the importance of competitiveness
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Natural Suppression of Lif–Naf–Kf Corrosion Activity in a Liquid Salt Reactor Atom. Energy (IF 0.5) Pub Date : 2023-10-20 A. L. Shimkevich
The present paper considers the physicochemical properties of valence electrons in the LiF–NaF–KF system within the framework of energy band theory. Here, the movement of the Fermi level in its band gap is equivalent to variations in the redox potential of the salt. When used to determine the limit level of the triple eutectic deoxidation, the electrochemical window identifi ed in the band gap may
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Study of Effects Caused by the Neutron Value Function on Kinetic Functionals Using the MCU Software Atom. Energy (IF 0.5) Pub Date : 2023-10-20 D. M. Arkhangelsky, D. S. Oleynik
The results of calculating the βeff effective fraction of delayed neutrons and the Λ lifetime of prompt neutrons, both when taking into account and excluding the value function, are presented. The analysis, concerning the effects of accounting for the neutron value function at various degrees of its expansion, as well as depending on the physical and geometric parameters of the system, is conducted
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Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation Atom. Energy (IF 0.5) Pub Date : 2023-10-18 S. A. Fateev, V. V. Petrunin, G. N. Kodochigov, I. V. Marov, S. V. Alekseev, P. L. Ipatov, A. Yu. Petrov, N. N. Ponomarev-Stepnoy, A. V. Shutikov
By reducing the consumption of hydrocarbons for the production of thermal and electric energy, problems associated with global heating can be mitigated. Industrial, transport, and utility sectors currently account for about 70% of total consumption of fossil energy resources. In order to significantly reduce carbon emissions, it will be necessary to replace the energy of burning fossil fuels with nuclear
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Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP Atom. Energy (IF 0.5) Pub Date : 2023-09-09 D. Yu. Kuznetsov, R. Z. Aminov, V. E. Yurin
Given the obligation to safely navigate a full de-energization condition of NPP it is important to study the natural circulation of the coolant in the primary loop of NPP with water-moderated/cooled [pressurized-water] reactors in the event of de-energization of the main circulation pump. At Balakovo NPP No. 3 with 104% load, the power unit underwent complete de-energized along with the main circulation
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Calculation of X-Ray Dose Loads in the Human Body Using Voxel Phantoms and the MCU Program Atom. Energy (IF 0.5) Pub Date : 2023-09-09 M. Yu. Nikulin, D. S. Oleynik, G. S. Sergeev, D. A. Shkarovsky
A benchmark experiment modeling two typical medical x-ray procedures – chest and abdominal x-rays – was calculated for the purpose of verifying the MCU computer program for performing calculations in the field of radiation medicine. The dose load calculations were performed with the aid of voxel phantoms developed by the ICRP for different sexes. Comparison of the absorbed dose calculated in this work
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Implementation of Software and Hardware for Continuous Radiation Monitoring of Gas-Aerosol Media Atom. Energy (IF 0.5) Pub Date : 2023-09-08 V. A. Kishev, A. A. Ivanov, E. M. Vetoshkin, S. B. Chebyshov, V. G. Golubev
The means for measuring the volumetric activity of radioactive noble gases, aerosols, and radioiodine were developed in line with the current requirements of the designed nuclear energy facilities. This article presents aspects of equipment design and the metrological characteristics of technical means and indicates directions for further research aimed at increasing reliability in assessing emissions
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R&D Test Bench for Investigating the Dynamic Adsorption of Radon from Airflows Atom. Energy (IF 0.5) Pub Date : 2023-09-09 E. P. Magomedbekov, A. V. Obruchikov, A. O. Merkushkin, V. S. Pokalchuk, G. A. Sarychev
The plan of an R&D test bench with 222Rn and 220Rn (thoron) generators for investigating the dynamic adsorption of radon is described. An approach to the investigation of dynamic radon adsorption based on the measurement of gamma-emitting daughter decay products of radon (214Pb or 214Bi) and thoron (212Pb) in sections of a collapsible adsorption column is proposed. The proposed approach has a number
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Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel Atom. Energy (IF 0.5) Pub Date : 2023-09-09 A. L Shimkevich
The Fermi level in uranium dioxide with band gap εg = 2.1 eV is a logarithmic identifier of the oxidation state of the dioxide and serves as a measure of the electron occupation of the local energy levels in the band gap. An impurity additive in the form of a trivalent metal is required in order to transfer the dioxide into a stable hypostoichiometric state with a high density of oxygen vacancies.
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One-Group Cross-Sections of High-Threshold Reactions for Precision Neutronics Calculations Atom. Energy (IF 0.5) Pub Date : 2023-09-08 E. F. Mitenkova, N. V. Novikov, E. V. Solovjeva
Low-concentration nuclides – impurity nuclides – are increasingly in demand in radiochemistry for defining more precisely the neutronic characteristics of the medium. On use in precision calculations, impurity nuclides afford more accurate calculations. This article considers aspects of the calculation of one-group cross sections of the high-threshold reactions (n, nt), (n, 2α), (n, 2p), (n, pα), (n
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Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction Atom. Energy (IF 0.5) Pub Date : 2023-09-08 V. D. Ozrin, A. S. Filippov
The results of a simulation of ACE MCCI test L8 facility (ANL, Argonne, USA) on the interaction of melt with concrete are presented. The objectives of this work are the validation of previously developed models of the melt–concrete interaction and an analysis of inconsistencies in the yield of carbon oxides, which are explained by aspects of the thermochemistry of the interaction. The computational
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Calculation of Multistage Schemes for Concentrating Isotopes in a Gas-Centrifuge Cascade with Variable Separation Factors Atom. Energy (IF 0.5) Pub Date : 2023-09-08 V. A. Palkin
A method is proposed for calculating a gas-centrifuge cascade with variable separation factors depending on their feed flow and flow division factor. On its basis, a computational experiment was performed on the separation of germanium tetrafluoride, nickel trifluorophosphine, and tungsten hexafluoride in a cascade with a specified number of gas centrifuges in steps. The most efficient multistage separation
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Radiation and Radiological Consequences of a Hypothetical Nuclear Accident at a Nuclear Facility Located in the Positional-Home District of Atomflot Atom. Energy (IF 0.5) Pub Date : 2023-09-08 A. A. Sarkisov, S. V. Antipov, V. L. Vysotskii, D. A. Pripachkin, D. V. Dzama, V. P. Bilashenko, M. N. Kobrinsky, I. N. Khokhlov, P. A. Shvedov, I. M. Gubenko, K. G. Rubinshtein, R. Yu. Ignatov, V. E. Kalantarov
The population dose loads resulting from the maximum possible and least likely (hypothetical) nuclear accident on one of the nuclear icebreakers under construction at FSUE Atomflot were determined. Assessments were made of 1) the population danger of radioactive contamination of the environment by comparing the predicted data with the acceptable norms and 2) the contribution of the determining technogenic
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Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter Atom. Energy (IF 0.5) Pub Date : 2023-09-08 S. V. Kolesnikov, A. P. Denisenko, E. V. Ryabeva
The signal characteristics of a ZnS(Ag) + 6LiF scintillator-based detector were investigated. The amplitude and width of the pulses from slow neutrons and electrons 90Sr–90Y were measured on a test bench. The parameter Q, the threshold for detecting neutron events, and the probability of error in determining particles were determined. The selected threshold ensures neutron detection against the electron
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Experimental Study of Departure from Nucleate Boiling on the Surface of a Molten Core Catcher Under Conditions of Boiling Borated Water with Debris Atom. Energy (IF 0.5) Pub Date : 2023-08-25 O. D. Chernyi, A. S. Sazontov, M. V. Devyatkin, P. Yu. Klimov, V. K. Efimov, A. G. Mitryukhin, L. A. Matyushev, V. G. Sidorov, V. O. Kukhtevich, Yu. G. Verbitskii, V. O. Astafieva, A. E. Moloskin
The results of an experimental study associated with the departure from nucleate boiling flux on the surface of a flat plate in the absence of a directional movement of borated water burdened with debris are presented. The experiments model the external surface cooling of a water-water energy reactor molten core catcher in the case of a severe accident involving the destruction of the reactor vessel
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First Cryogenic Tests of Superfluid Helium Heat Exchanger for an Ultracold Neutron Source Atom. Energy (IF 0.5) Pub Date : 2023-08-25 V. A. Lyamkin, A. P. Serebrov, A. O. Koptyukhov
Currently, works on the construction and commission of a PIK reactor using an ultracold neutron source are underway. The source uses two stages of neutron moderation: superfluid helium and liquid deuterium. In order to maintain the isotopic purity of superfluid helium, it is proposed to use a liquefaction heat exchanger in which isotopically pure helium is liquefied and thermostated by industrial helium
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Arrangement of a Concrete Slab in the Backfill as a Means of Altering the Seismic Response of a Building Structure Atom. Energy (IF 0.5) Pub Date : 2023-08-25 N. A. Antonov
One of the options for modifying the soil foundation of massive critical buildings involves the arrangement of a concrete slab between soils having the required properties and the foundation slab of the building in a preliminary excavated pit. By subsequently backfilling the pit with soils in which seismic waves have low velocity, it is possible to effect a change in the reaction of the building to
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Development of a Risk Monitoring Model for NPPs with a VVER-440 Reactor Atom. Energy (IF 0.5) Pub Date : 2023-08-25 P. L. Aksenov, I. A. Komolov, P. A. Molodov
Risk monitoring technologies are actively used to improve the operational efficiency of nuclear power plants, as well as for ensuring compliance with technological and operational regulatory requirements. The present article describes the process of developing a defense-in-depth tree and justifying the boundaries of risk zones based on international experience in developing such models. Based on the
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Severe Accident Management at NPP-2006 Reactor Plants (Leningrad NPP-2) Atom. Energy (IF 0.5) Pub Date : 2023-08-25 V. G. Sidorov, V. O. Astafieva, Yu. V. Krylov, K. S. Titov, V. O. Kukhtevich, S. E. Semashko, A. G. Mitryukhin
The article examines measures involved in severe accident management for NPP-2006 reactor plants based on the Leningrad NPP-2 prototype and their substantiation using deterministic analysis and special computer codes. The results obtained during the analysis should be considered in the development of severe accident management guidelines for these reactor plants in terms of the composition and priority
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Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs Atom. Energy (IF 0.5) Pub Date : 2023-08-25 I. A. Magola, V. O. Kukhtevich, N. A. Osmakov, L. A. Matyushev, E. L. Shamray, A. G. Mitryukhin, V. K. Efimov, T. B. Malikov, O. D. Chernyi, M. V. Devyatkin
The present article examines sources and conditions for the formation of debris during loss-of-coolant accidents due to the influence of a high-energy jet on the thermal insulation of pipelines, valves, and containment structures. Described debris characteristics include fractional composition and particle settling velocity, zone-of-influence factors for the breaking jet impact on the various types
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Effects of the Thermal Exposure and Organosilicate Coating on the Properties of a Specialized Concrete for NPP Construction Atom. Energy (IF 0.5) Pub Date : 2023-08-25 A. A. Fiskov, V. G. Kritskiy, I. A. Magola, A. A. Ditz, V. I. Vereshchagin
The work sets out to study the effect of an OS-51-03 organosilicate coating on the properties of a specialized concrete used in the construction of nuclear power plants (NPPs) under thermal exposure. The article considers the determination of the concrete density and water absorption, the quantity of free and bound water, as well as the ultimate compressive strength both before and after thermal exposure
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3D Modeling of NPP Containment Medium Mixing During the Development of Severe Accidents Atom. Energy (IF 0.5) Pub Date : 2023-08-25 A. A. Ignatiev, E. E. Avdeev, R. B. Povarenskiy, D. V. Kapiza, V. O. Kukhtevich, S. E. Semashko
The article considers the 3D modeling of a gaseous medium mixing during a NPP severe accident using the STAR-CCM+ commercial code. The mathematical model of a passive hydrogen recombiner is described. The results of calculating a severe accident scenario and its comparison with the results obtained using the KUPOL-M code of lumped parameters are given. An analysis of possible hydrogen combustion and
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Experimental Substantiation of NPP-2006 Sump Tank Strainers Atom. Energy (IF 0.5) Pub Date : 2023-08-25 I. A. Magola, L. A. Matyushev, E. L. Shamray, A. G. Mitryukhin, P. A. Arsenyev, V. B. Shtilman
The study aims to experimentally substantiate the operability of sump tank strainers in the case of loss-of-coolant accidents. The article discusses the requirements for emergency core cooling system (ECCS) sump tank strainers of the NPP-2006 design. The principles of operation and special features of the design concept are examined; the results of the ECCS strainer experimental substantiation are
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Methodological Problems in Assessing the Availability Indicators of NPP Power Units at the Design Stage Atom. Energy (IF 0.5) Pub Date : 2023-08-25 A. A. Nagibin, Yu. I. Kozlov, I. A. Kaplichnaya, P. V. Legoshin
The article discusses methodological problems that arise when assessing the availability indicators of NPP power units at the design stage. A description of the availability analysis process and indicators is provided. The downtimes of power units at NPPs with the VVER-1000 reactor in excess of the established standard are statistically evaluated. A computational model simulating the scheduled shutdown
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Optimization of Neutron Radiation Detection Assemblies Atom. Energy (IF 0.5) Pub Date : 2023-07-27 T. Kh. Badretdinov
The paper considers the use of reactor neutron-activation analysis for optimizing neutron radiation detection assemblies using gas-discharge proportional and corona detectors in the presence of sources of interference that decrease their sensitivity. A set of measures provided for the discrimination of associated γ-radiation, which concerns the detection assembly design, the type of utilized radiation
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Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies Atom. Energy (IF 0.5) Pub Date : 2023-07-27 I. V. Mosyagina, O. V. Ivkina, M. A. Sharipova, S. B. Chebyshov
The article presents results of research and development in creating new combined neutron-detecting materials based on scintillating polymer elements, as well as actinide dioxide radiators. New functional combinations of materials for detecting neutrons in a wide energy range are proposed. The obtained spectral and counting rate characteristics of the samples can be used in the selective detection
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Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles Atom. Energy (IF 0.5) Pub Date : 2023-07-27 N. B. Anikin, M. E. Ignatyuk, Yu. A. Piskunov, A. A. Tyaktev
The accumulation of hydrogen during a hypothetical accident poses a danger to nuclear power plants based on light-water reactors (LWR). Currently, flameless hydrogen oxidation systems – or recombiners – are widely used to neutralize this danger at nuclear power plants. However, when heated to a high temperature during the oxidation of hydrogen, catalytic recombiner elements can become the sources of
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Nitriding and Carburization of a Mixed Nitride Uranium-Plutonium Fuel Pin Cladding Atom. Energy (IF 0.5) Pub Date : 2023-07-27 S. I. Porollo, E. E. Marinenko, F. N. Kryukov, O. N. Nikitin, I. F. Gilmutdinov, L. M. Zabudko, A. F. Grachev, B. A. Tarasov
Post-reactor studies of experimental fuel pins with mixed nitride uranium-plutonium fuel and EP823-Sh, ChS68-ID kh.d., and EK164-ID kh.d. steel cladding, which have been irradiated in BOR-60 and BN-600 reactors, indicated the nitriding and carburization of the cladding inner layer, which leads to an increase in its microhardness and a reduction in ductility characteristics. In fuel pin claddings, made