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Immobilization of chloride radioactive waste using a phosphate glass composite material Atom. Energy (IF 0.5) Pub Date : 2024-04-12 A. V. Frolova, S. A. Fimina, S. E. Vinokurov
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Assembly of core for the IGRIK-2 solution pulse reactor Atom. Energy (IF 0.5) Pub Date : 2024-04-12 S. A. Andreev, L. S. Ershova, S. G. Porubov, D. V. Khmelnitsky, S. V. Shugaev, A. A. Kuzinskaya
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Effect of nuclear fuel composition on neutrons yield in high-energy-density plasma Atom. Energy (IF 0.5) Pub Date : 2024-04-11 Sonia M. Reda, Dalia Anwar, Emad I. Khalil, Ahmed Youssef
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Experimental studies of combustion processes of stratified and uniform hydrogen-air mixtures Atom. Energy (IF 0.5) Pub Date : 2024-04-10 S. A. Yakovlev, E. V. Bezgodov, V. V. Stakhanov, A. A. Tarakanov, I. A. Popov, S. D. Pasyukov, M. V. Nikiforov, A. N. Savelyev, Yu. F. Davletchin
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Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software Atom. Energy (IF 0.5) Pub Date : 2024-04-09 Sahar Mojab, Ehsan Zarifi, Saeed Zare Ganjaroodi, Gholamreza Jahanfarnia
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Testing of a transportation and storage container model Atom. Energy (IF 0.5) Pub Date : 2024-04-09 V. V. Abramov, A. G. Kazantsev, O. M. Petrov, A. E. Buchelnikov, I. A. Kochura, V. P. Kravchenko, R. S. Sedov, V. V. Tausenev, M. V. Radchenko, M. V. Kharin
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Features of coolant movement at the boundary of jacketless fuel assemblies with fuel rods of various diameters Atom. Energy (IF 0.5) Pub Date : 2024-04-09 V. V. Lemekhov, V. I. Solonin, V. G. Krapivtsev, S. I. Getya, P. V. Markov, S. G. Kutychkin
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Increased sensitivity of laser monitoring of molecular iodine in the atmosphere around the location of an npp using an unmanned aerial vehicle Atom. Energy (IF 0.5) Pub Date : 2024-04-09 S. K. Mankevich, E. P. Orlov
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Optimization of the square and squared-off cascades to separate stable isotopes using meta-heuristic algorithms Atom. Energy (IF 0.5) Pub Date : 2024-04-09 Fatemeh Ardestani, Jaber Safdari, Mohammad Hassan Mallah, Morteza Imani
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Improving the efficiency of a BREST-300 NPP using the thermal energy of natural gas Atom. Energy (IF 0.5) Pub Date : 2024-04-09 S. A. Makarov
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Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling Atom. Energy (IF 0.5) Pub Date : 2024-04-09 Saeed Zare Ganjaroodi, Ehsan Zarifi
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KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors Atom. Energy (IF 0.5) Pub Date : 2024-04-05 V. I. Belousov, V. D. Davidenko, I. I. Dyachkov, N. N. Elkin, M. R. Malkov, M. V. Ioannisian, M. G. Chernetskii, A. A. Chernitskaya, V. G. Zborovskii, V. V. Likhanskii, O. V. Khoruzhii
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Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors Atom. Energy (IF 0.5) Pub Date : 2024-04-04 A. G. Volkovich, O. P. Ivanov, V. I. Kolyadin, A. V. Lemus, V. I. Pavlenko, L. A. Ryazanova, S. G. Semenov, E. A. Stepanov, A. V. Chesnokov, A. D. Shisha
The article presents the results of a radiation survey carried out on the liquid radioactive waste disposal system of decommissioned MR and RFT research reactors. The system is located in the buildings adjacent to the dismantled reactor building on the territory of the Kurchatov Institute national research center. The results of the visual and radiation survey carried out on the equipment and premises
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Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor Atom. Energy (IF 0.5) Pub Date : 2024-04-04 A. V. Kaplienko, V. V. Lemekhov, Yu. S. Cherepnin, A. V. Moiseyev, A. P. Zhirnov, A. N. Ivanyuta, I. M. Rozhdestvenskiy, D. Yu. Loginov, Ye. R. Mezhina, A. L. Izhutov, Ye. A. Zvir, G. V. Shevlyakov, I. N. Volkova, Ye. G. Batyrbekov, V. V. Baklanov, A. G. Korovikov, A. N. Kotlyar, A. A. Miller, R. A. Irkimbekov, A. D. Vurim
Fuel elements with mixed uranium-plutonium nitride fuel were tested in an IGR reactor to justify their application in a BREST-OD-300 reactor. The mid-radial enthalpy limit for the fresh mixed nitride fuel as experimentally determined during IGR launching with fast reactivity input amounted to 167 cal/g. The maximum temperature of 1000 °C and its maintenance for 100 s, comprising one of the design limits
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Numerical simulation of a hydrogen leakage in a ventilated room Atom. Energy (IF 0.5) Pub Date : 2024-04-04 K. S. Kutuzova, V. V. Stakhanov, E. V. Bezgodov, Yu. A. Tomilov, I. A. Popov, S. D. Pasyukov, A. A. Tarakanov
During the production or storage of a hydrogen gas in a confined space, the formation of an explosive mixture can occur in the event of an accidental leakage. Therefore, in order to ensure safety, it is necessary to create a room ventilation system that prevents the formation hazardous zones with an elevated content of combustible gases that can lead to a local explosion. The paper presents the results
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Experimental study of the hydrogen leakage and ignition in a ventilated room Atom. Energy (IF 0.5) Pub Date : 2024-04-04
Abstract During the storage or production of a hydrogen gas within a limited space, a combustible mixture may form in the event of an emergency leakage. In order to ensure safety, it is necessary to develop a room ventilation system for preventing the formation of areas in which there is an increased content of combustible substances. The present article considers experiments on the leakage of a hydrogen
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BM-U facility for simulating emergency processes involving the propagation and combustion of flammable gases Atom. Energy (IF 0.5) Pub Date : 2024-04-04 E. V. Bezgodov, A. S. Ivanov, V. A. Simonenko, D. V. Frolov, M. V. Nikiforov, S. D. Pasyukov, I. P. Kotlovanov, I. K. Sharapov, S. I. Yurkov, A. G. Dolgorukova
Accidents involving the release of large amounts of combustible gases, such as hydrogen, methane, carbon monoxide, etc., are possible at nuclear power plants, as well as in chemical production facilities. Currently, calculation tools are used for substantiate explosion safety. To permit their validation, experimental data obtained from a prototype facility are required. RFNC–VNIITF has developed a two-chamber
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Magnetic insulation system for a laser-plasma ion diode of a portable neutron generator Atom. Energy (IF 0.5) Pub Date : 2024-04-04
Abstract A new promising type of portable pulsed neutron generator is based on a laser-plasma ion diode with magnetic insulation. At the present stage of its evolution, such a generator requires the development of a magnetic insulation system capable of blocking secondary electrons in a laser-plasma diode. The article considers the development of such a magnetic insulation system, during which the
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Features of americium transmutation in a BN-1200M fast reactor Atom. Energy (IF 0.5) Pub Date : 2024-04-04 A. A. Tuzov, A. V. Gulevich, O. S. Gurskaya, V. M. Dekusar, V. A. Eliseev, E. M. Zarapina, V. M. Troyanov
The main approaches to americium transmutation in BN-1200M are considered: homogeneous transmutation in the core and heterogeneous transmutation with a moderator in the radial blanket. It is stated that the main limiting factor of transmutation is the residual heat release of the unloaded FAs. Within the design constraints, the annual transmutation rates are approximately the same in both cases. It
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Experimental study of hydrodynamic stability limits in the system of parallel steam-generating channels Atom. Energy (IF 0.5) Pub Date : 2024-04-02
Abstract When designing steam-generating devices, it is necessary to consider the issue of determining the limits of their stable operation. Such stable operation limits can be determined by testing a model that reflects the main design features of a full-scale steam generator. For this purpose, JSC OKBM Afrikantov has developed and tested a steam generator model. The results obtained in the tests
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Use of burnable absorbers for reducing water exchange during the VVER liquid control Atom. Energy (IF 0.5) Pub Date : 2024-04-02 A. R. Muzafarov, V. I. Savander
The paper considers the optimization of a liquid system for compensating excess reactivity by varying the number of gadolinium-containing fuel elements in a VVER fuel assembly and gadolinium mass loading into the fuel elements. Using a simplified refueling model, an ideal dependence of the neutron multiplication factor with burnable absorbers is obtained with reactor criticality, which is maintained
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Gibbsite- and kuzelite-based matrix for the preservation of radioactive aqueous sodium nitrate concentrates Atom. Energy (IF 0.5) Pub Date : 2024-04-02 O. A. Kononenko, V. I. Makarenkov
The article studies the possibility of using a matrix of gibbsite and kuzelite for the preservation of liquid radioactive wastes consisting of aqueous NaNO3 concentrates. The matrix is formed during the solidification of these wastes with cement, consisting of calcium aluminate and gypsum. The requirements for cemented solid waste are met by a matrix obtained from a mixture of the following composition:
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Calculated demonstration of VVER-1000 SNF actinide transmutation efficiency Atom. Energy (IF 0.5) Pub Date : 2024-03-27 A. V. Lopatkin, N. P. Golovin, I. B. Lukasevich
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Development of a hydrogen-air flame in a vertical channel with a horizontal diaphragm Atom. Energy (IF 0.5) Pub Date : 2024-03-22
Abstract The paper describes an experimental study of lean hydrogen-air flames in a 1490-mm-long closed vertical channel of a square 138×138 mm section behind a horizontal diaphragm with a diameter of 50 mm. Schlieren images of the flame in a homogeneous hydrogen-air mixture are given along with the pressure dynamics for the mixtures with 6, 8, and 16 vol.% of hydrogen. It is shown that shear instability
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Technology development and performance study of various thermoluminescent detectors Atom. Energy (IF 0.5) Pub Date : 2024-03-21 I. V. Mosyagina, O. V. Ivkina, M. A. Sharipova
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Lessons learned from the experience of operating lead-bismuth nuclear power reactors Atom. Energy (IF 0.5) Pub Date : 2024-03-21 V. M. Troyanov, V. A. Vasilenko, M. V. Kolik, V. S. Stepanov, G. I. Toshinsky
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Fuel cycles with advanced dispersion fuel elements of high uranium density Atom. Energy (IF 0.5) Pub Date : 2024-03-21 A. M. Savchenko, L. A. Karpyuk, E. A. Dergunova, Yu. V. Konovalov, G. V. Kulakov, S. V. Maranchak, S. A. Ershov, V. I. Kupenko, E. V. Mainikov
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Experimental and computational-theoretical capabilities of RFNC—VNIITF and the tasks of ensuring the safety of hydrogen energy technologies Atom. Energy (IF 0.5) Pub Date : 2024-03-21 E. V. Bezgodov, P. E. Belyaev, V. A. Simonenko, V. M. Kryukov, I. R. Makeeva, D. V. Frolov, M. V. Nikiforov, A. V. Ushkov, A. A. Tyaktev, I. V. Glazyrin, O. V. Shults, I. A. Kirillov
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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