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HTGR – New Prospects for Nuclear Energy Atom. Energy (IF 0.271) Pub Date : 2021-01-23 N. G. Abrosimov, N. G. Kodochigov, L. E. Kuznetsov, V. V. Petrunin, N. N. Ponomarev-Stepnoi, Yu. P. Sukharev
High-temperature gas-cooled reactors (HTGR) are a new type of environmentally clean source of nuclear energy. Their unique properties – capability of generating heat at temperatures to 1000°C and a high safety security – determine the wide possibilities for using reactors of this type to produce hydrogen from water, supply heat for technological processes in different industries, and produce electricity
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Probabilistic Safety Analysis of Nuclear Installations of Different Types and Classes Atom. Energy (IF 0.271) Pub Date : 2021-01-23 P. S. Antipin, A. M. Bakhmet’ev, I. E. Efimkina, S. P. Lin’kov, V. V. Petrunin
The OKBM Afrikantov infrastructure created for performing probabilistic safety analysis of nuclear installations used for different purposes is briefly described. The research in which the enterprise participated is presented. Included are the Voronezh nuclear plant with an AST-500 reactor for supplying heat, commercial uranium-graphite reactors ADE-2, -4, -5, a reactor installation with a high-temperature
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Commercial Uranium-Graphite and Heavy-Water Reactors: Originating and Operating Experience Atom. Energy (IF 0.271) Pub Date : 2021-01-23 V. V. Petrunin, I. V. Marov, S. E. Skorodumov, O. Yu. Vilenskii, N. L. Bazhutov, D. A. Golubeva
Information on the key stages in the origination and operation of commercial uranium-graphite and heavy-water reactors is presented. The problems solved for purposes of safety enhancement and lifetime extension of dual-purpose reactors are described and the basic approaches to decommissioning are presented. Information on the specifics of heavy-water commercial reactors is represented.
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Reactor Installations for Nuclear Icebreakers: Origination Experience and Current Status Atom. Energy (IF 0.271) Pub Date : 2021-01-23 D. L. Zverev, Yu. P. Fadeev, A. N. Pakhomov, V. Yu. Galitskikh, V. I. Polunichev, K. B. Veshnyakov, S. V. Kabin, A. Yu. Turusov
OKBM Afrikantov has been developing power installations for the icebreaker fleet for more than 60 years. The first generation of reactor installations is represented by the OK-150 loop-type installation for the icebreaker Lenin. At the exhaustion of its operating life it was replaced by the second-generation OK-900 installation. The next stage of the origination of reactor installations for civilian
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Nuclear Ship Reactor Installations: From Gen 1 to 5 Atom. Energy (IF 0.271) Pub Date : 2021-01-23 D. L. Zverev, S. M. Neevin, D. L. Doronkov, L. B. Sokolova
The use of nuclear energy on submarines has made autonomous and independent navigation possible for long periods of time. OKBM Afrikantov – one of the leading enterprises of the Rosatom State Corporation – has been supplying Russia’s naval ships with nuclear reactor installations for more than 65 years commencing with the development of equipment for the installations on first-generation submarines
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The World’s First Floating NPP: Origination and Direction of Future Development Atom. Energy (IF 0.271) Pub Date : 2021-01-23 V. M. Belyaev, M. A. Bol’shukhin, A. N. Pakhomov, A. M. Khizbullin, A. N. Lepekhin, V. I. Polunichev, K. B. Veshnyakov, A. N. Sokolov, A. Yu. Turusov
The main stages of the origination (in our country) of the world’s first floating nuclear thermal power plant based on the floating power-generating unit Akademik Lomonosov with two icebreaker-type reactor installations whose chief designer and complete supplier is OKBM Afrikantov are presented. The operational model, the motivation for choosing the technical decisions, a brief description of the design
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Reactor Installations with Sodium-Cooled Fast Reactors for Two-Component Nuclear Energy Atom. Energy (IF 0.271) Pub Date : 2021-01-23 S. V. Babushkin, B. A. Vasil’ev, A. V. Vasyaev, V. E. Vorontsov, S. A. Dushev, D. L. Zverev, A. I. Kiryushin, E. V. Marova, V. Yu. Sedakov, A. I. Staroverov, A. V. Timofeev, S. F. Shepelev
The experience of origination and operation of BN-600, -800 and development of BN-1200 commercial power units of two-component nuclear energy are recounted. Substantiation is given for the engineering solutions allowing efficient production of electricity and closure of the nuclear fuel cycle with sodium-cooled fast reactors.
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Tritium Entry Into the Atmosphere with Emissions from NPP-VVER and Population Irradiation Dose Assessment Atom. Energy (IF 0.271) Pub Date : 2021-01-13 A. I. Kryshev, M. E. Vasyanovich, A. A. Ekidin, Yu. N. Filatov, E. L. Murashova
Tritium emissions from NPP with VVER were estimated based on radiation and technical survey data. It is shown that the population in the NPP-VVER observation zone consumes a significant amount of imported food products, so that equality is not reached between the specific activity of tritium in the water of human tissues and atmospheric water. Taking this into account, an evidenced model is developed
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Thermal Insulation for AES-2006 Sealed Containment Protection from Passive Catalytic Hydrogen Recombiners Atom. Energy (IF 0.271) Pub Date : 2021-01-09 V. V. Sorokin
The heat effect of passive catalytic hydrogen recombiners on the AES-2006 sealed containment is examined. It is shown by computational means that the maximum temperature of the containment near the re-combiners is exceeded locally in regimes characteristic for accidents and without adoption of measures to limit the heat flow onto the containment. Methods are proposed for lowering the containment temperature
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Adaptation of CONV-3D Single-Phase Module for Modeling Turbulent Flow in Reactors in the Les Approximation Atom. Energy (IF 0.271) Pub Date : 2021-01-04 V. V. Chudanov, A. E. Aksenova, V. A. Pervichko
The particulars of the adaptation of the CONV-3D module for modeling turbulent flows in reactors in the LES approximation are presented. The results of modeling coolant flow in a round tube with Reynolds number 4·103–5·105 in comparison with the Blasius formula are presented. It is shown that the adapted module gives numerical results that coincide with the analytical estimates and DNS calculations
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Investigation of Local Damage Effect on Nb 3 Sn Superconductor Properties Atom. Energy (IF 0.271) Pub Date : 2021-01-04 I. M. Abdyukhanov, A. S. Tsapleva, K. A. Mareev, M. V. Alekseev, P. A. Luk’yanov, M. V. Polikarpova, G. A. Zakharova, I. A. Panashchuk, M. N. Nasibulin, E. A. Dergunova
When twisted into a cable, reduced, and wrapped, Nb3Sn composite superconductors are subject to significant deformation and can sustain damage that will affect their electrophysical properties. This article examines the effect of artificially induced surface damage on the electrophysical characteristics and microstructure of 0.82 and 0.7 mm in diameter Nb3Sn superconductors fabricated by the bronze
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Study on the Performance of Primary Means of Measurement of the Hydrogen Concentration During Severe Accidents at NPP Atom. Energy (IF 0.271) Pub Date : 2021-01-04 A. A. Fis’kov, V. G. Kritskii, A. A. Ditts, V. M. Pogrebenkov
This work is devoted to hydrogen safety security during severe accidents at NPP as well as the validation of equipment performance of passive safety systems under these conditions. The results of an experimental investigation of the performance of the primary means of measurement module of the hydrogen concentration control system under physicochemical actions on them due to the precipitation of insoluble
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Development of a Sorption Technology for Separating Uranium and Rare-Earth Elements Atom. Energy (IF 0.271) Pub Date : 2021-01-04 D. A. Elatontsev, Yu. F. Korovin, A. P. Mukhachev
The results of laboratory experiments on the sorption separation of uranium and rare-earth elements from nitrate-phosphate solutions on a solid extractant with an active phase in the composition of the heter-oradical phosphine oxide and di-(2-ethylhexyl)phosphoric acid are reported. This extractant was used to attain high capacity and degree of extraction of uranium from solutions with initial uranium
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Separative Cascade Shape Effect on the Isotopic Mixture Concentration in Cascade Holdup Atom. Energy (IF 0.271) Pub Date : 2021-01-04 A. A. Ushakov, A. A. Orlov
Numerical studies are performed of the separation of a model multi-component isotopic mixture in a three-stream cascade. The particulars of isotope accumulation as a function of cascade shape (length, stage distribution of interstage flow) are examined. The regularities of the effect of the cascade shape on the component concentration in the cascade holdup are determined. An enriched isotopic mixture
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Security of Export Deliveries of Regenerated-Uranium Light-Water Reactor Fuel from the Standpoint of IAEA Safeguards Atom. Energy (IF 0.271) Pub Date : 2021-01-04 Yu. N. Volkov, V. E. Gusev, A. Yu. Smirnov, G. A. Sulaberidze, V. Yu. Blandinskii, V. A. Nevinitsa, P. A. Fomichenko
The nonproliferation of nuclear materials is the key issue in supplying nuclear fuel to foreign countries. This article discusses the use of regenerated uranium to enhance the security of exports of fresh fuel for light-water reactors. It is shown that if the removal of fuel and its replacement with, for example, natural uranium go undetected, the criminals have long periods of time available to obtain
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Software Packages for Technical and Economic Modeling of Nuclear-Energy Systems: Status and Development Prospects Atom. Energy (IF 0.271) Pub Date : 2021-01-04 A. A. Andrianov, A. V. Gurin, E. V. Rodionova, N. D. Dyrda, I. R. Makeeva, S. A. Kvyatkovskii, P. B. Ptitsyn, N. A. Molokanov, E. V. Murav’ev, P. S. Teplov
The results of an analysis of the status and prospects for the development of software used in technical and economic modeling of nuclear-energy systems in systems-analytical and predictive studies of the validation of the prospects for nuclear energy are reported. A classification of the deployed software is given and the IT-particulars of such software are discussed. Actual problems and promising
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CONV-3D Code Aided Calculation of the Flow Parameters of Fuel-Rod Bundles Atom. Energy (IF 0.271) Pub Date : 2020-10-26 V. V. Chudanov, A. E. Aksenova, V. A. Pervichko
The results of modeling of incompressible fluid flows in fuel rod bundles performed using the CONV-3D code are reported. The modeling results obtained for different Reynolds numbers and distances between the fuel rods in comparison with experiment are presented. It is shown that the developed code satisfactorily models the flow of an incompressible fluid in fuel rod bundles and can be used to analyze
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Integrity Assessment of RBMK Physical Safety Barriers during Prolonged Station Power-Unit De-Energization Atom. Energy (IF 0.271) Pub Date : 2020-10-26 T. A. Bubnova, A. V. Kaplienko, Yu. M. Nikitin, A. V. Slobodchikov, R. M. Umyarov
Two successive stages of the control of a beyond-design basis accident with de-energization of an RBMK reactor together with multiple equipment failures are analyzed: depressurization of the circulation loop and restoration of reactor cooldown with cold water as the reactor subsequently warms up. The factors affecting the pressure surge in the circulation loop on restoration of reactor cooling as the
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Position Sensitive Detectors with Particle-Type Identification for Recording Images of Neutron and Gamma Sources in Mixed Fields Atom. Energy (IF 0.271) Pub Date : 2020-10-26 M. V. Prokuronov, V. D. Sevast’yanov, A. V. Yanushevich, R. M. Shibaev
The design and characteristics of position sensitive detectors implemented in the form of a matrix of individual detectors (modules) with selective registration of electrons and protons are examined. It is proposed that such detectors be used as a basis for considering the possibility of building introscopes with a coded aperture for detecting images of sources of mixed fast-neutron and γ-radiation
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Computational Validation of Experiments with Molten-Salt Thorium-Uranium Fuel Compositions in MBIR Test Loop Atom. Energy (IF 0.271) Pub Date : 2020-10-26 V. Yu. Blandinskii, D. S. Kuzenkova
The results of calculations of the equilibrium isotopic composition of molten-salt fuel in an experimental channel of the MBIR reactor are presented. Two organizational variants of the fuel cycle for a molten-salt test loop are examined: with extraction of protactinium and without extraction of heavy nuclei. The results show that the maximum thermal power of the test loop channel can reach 12 MW. Reprocessing
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Effect of the Electron-Emitter Parameters of a Pulsed Source of Light Penning Ions on the Extracted Current Atom. Energy (IF 0.271) Pub Date : 2020-10-26 D. S. Stepanov, A. P. Skripnik, E. Ya. Shkol’nikov
Gas-filled neutron tubes generating pulses with specified parameters are needed for neutron well-logging. These parameters are affected most by the ion-pulse shape. The results of numerical modeling of the dynamics of the electron beam, secondary ions, and electrons generated in the volume of the Penning ion source with an electron emitter and their effect on the ion-pulse parameters are examined.
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Optimal Scale of Development of Nuclear Energy in the UES of Russia to 2050 Atom. Energy (IF 0.271) Pub Date : 2020-10-26 F. V. Veselov, A. A. Khorshev
The development of nuclear power plants in the Unified Energy System (UES) of Russia in the period to 2050 under changing conditions of interfuel competition with thermal and renewable energetics is examined. The main external uncertainty factors affecting NPP competitiveness are identified and their ranges are determined. The technological factors of making NPP more competitive by improving their
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Experience in using Models of Pollutant Dispersal in an Urban Environment Atom. Energy (IF 0.271) Pub Date : 2020-10-26 S. V. Panchenko, D. A. Pripachkin, A. I. Kryshev, M. N. Katkova
The experience gained in validating calculations of the ground-surface concentration of a pollutant injected into an urban environment from a stationary high-altitude source is presented. A Gaussian model using the average annual emission, the characteristic parameters of the source, and a real annual wind rose, as well as a Lagrangian-type model, in which the input parameters were the average daily
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Physical Modeling of Hydrodynamics and Heat Transfer in Liquid-Metal Cooled Fast Reactors Atom. Energy (IF 0.271) Pub Date : 2020-10-26 A. P. Sorokin, Yu. A. Kuzina
The results of the application of the similarity theory of thermophysical processes to the modeling of hydrodynamics and heat transfer in liquid metals in intricately shaped channels and rod systems (reactor cores) as well as the temperature and velocity fields in the top chamber of a fast reactor in different operating regimes are reported. Direct modeling can be used without restrictions only for
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Optimization of a Square Cascade of Centrifuges for Separation of Multicomponent Mixtures of Stable Isotopes Atom. Energy (IF 0.271) Pub Date : 2020-10-26 T. E. Azizov, A. Yu. Smirnov, G. A. Sulaberidze
A method of optimizing the parameters of a three-stream square cascade for separation of multicomponent mixtures of stable isotopes under specified external conditions is proposed. It is based on a combination of a check calculation of the parameters of the cascade based on the separation factor approximation and a numerical search for the values of the external flows which are required to secure a
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Possibility of Capital Reserve Allocation for Nuclear-Risk Insurance Coverage on Transitioning to SMRs Atom. Energy (IF 0.271) Pub Date : 2020-10-26 I. B. Zhuravlev
It is shown that on creation of capital reserve to cover the risk of hypothetical severe accidents in NPP the size of the allocation is comparable to or greater than the fuel costs for a power-generating unit of a large NPP. The damage consequent to severe accidents in NPP is 1000 times greater than the insurance limits adopted for nuclear risks. An empirical power-law function (with exponent 1.6)
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Activation of the Structural Materials of Fast-Neutron Generators Atom. Energy (IF 0.271) Pub Date : 2020-09-28 R. N. Rodionov, A. O. Kovalev, D. V. Portnov, Yu. A. Kashchuk
The activation of a neutron generator is modeled for two operating scenarios: continuous for 16 h and 100 h at 4 h/day for one month. The distribution of the equivalent γ-ray dose rate was calculated for different times after the generator was shut down. Different grades of steel were considered for the material of the neutron generator flange. The time dependence of the γ-ray dose rate was calculated
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Physical and Technical Problems of Reprocessed Uranium Enrichment with Repeated Recycling in Light-Water Reactors and Ways to Solve Them Atom. Energy (IF 0.271) Pub Date : 2020-09-28 A. Yu. Smirnov, V. E. Gusev, G. A. Sulaberidze, V. A. Nevinitsa, E. A. Bobrov, I. A. Belov, E. V. Rodionova
Issues concerning fuel cycle closure are discussed. It is shown that from the standpoint of full utilization of reprocessed nuclear materials the main problems are associated with repeated recycling of uranium, the reason being that limitations are imposed on the content of the isotope 232U in fresh fuel produced from reprocessed materials. The losses of the isotope 235U on repeated recycling of reprocessed
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Radiation Dose Assessment for Representative Biota Organisms in the Locale of NPP with VVER-1200 Atom. Energy (IF 0.271) Pub Date : 2020-09-28 V. E. Nushtaeva, S. I. Spiridonov, R. A. Mikailova, E. I. Karpenko, S. N. Nushtaev, A. S. Nygymanova
A prognosis is made of the radiation impact of planned atmospheric emissions and liquid discharges from NPP with VVER-1200 on native ecosystems. The ERICA assessment tool was used to assess the dose loads for ICRP-recommended representative organisms. The expected irradiation dose from NPP for representatives of the biota is compared with the dose from the existing irradiation, evaluated on the basis
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Reprocessed Uranium Hexafluoride Purification from 232,234,236 U in Pentaflow Gas-Centrifuge Cascades Atom. Energy (IF 0.271) Pub Date : 2020-09-28 V. A. Palkin
A computational experiment was performed to purify reprocessed uranium hexafluoride from 232,234,236U in an additional product flow of cascades with a specified number of gas centrifuges in stages. The method used in the calculations takes into account the dependence of the separation coefficients of gas centrifuges on their feed flow and flow division factor. A cascade scheme for purification with
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Numerical Modeling of Delayed-Neutron Precursor Transport in a Sodium-Cooled Fast Reactor Atom. Energy (IF 0.271) Pub Date : 2020-09-28 S. A. Rogozhkin, S. L. Osipov, A. V. Salyaev, S. G. Usynina, V. I. Pokhilko, M. L. Sazonova
Methods of determining the efficiency of the system that controls the seal-tightness of fuel-rod cladding and localizes FA with leaky fuel rods in a fast reactor are examined. It is shown that the design procedure has significant limitations. A procedure for numerical modeling of the transport of delayed-neutron precursors was developed to take account of the special features of liquid-metal coolant
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Steel Cladding for VVER Fuel Pins in the Context of Accident-Tolerant Fuel: Prospects Atom. Energy (IF 0.271) Pub Date : 2020-09-28 L. A. Karpyuk, A. M. Savchenko, M. V. Leont’eva-Smirnova, G. V. Kulakov, Yu. V. Konovalov
Groups of materials are compared according to their possible use for fuel-pin cladding in the development of accident-tolerant fuel (ATF). Ferritic, ferritic-martensitic, and austenitic steels and chromium-nickel alloys are studied. Currently, only the chromium-nickel alloy 42KhNM can be used in VVER under normal operating conditions as cladding material for ATF. Pre-reactor and reactor studies are
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Thermohydraulics of Alkaline Liquid-Metal Coolant: A Retrospective-Perspective Look Atom. Energy (IF 0.271) Pub Date : 2020-09-26 A. P. Sorokin, Yu. A. Kuzina
Sixty years of experience in mastering alkaline liquid metals jointly with industry institutes, the Academy of Sciences, and engineering design agencies developing Nuclear Power Facilities (NPF) has culminated in the development of the scientific foundations for their use in nuclear power and the scientific substantiation of the hydraulic parameters and highly efficient technological processes ensuring
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Physical Chemistry and Technology of Alkaline Liquid-Metal Coolant: A Retrospective-Perspective Look Atom. Energy (IF 0.271) Pub Date : 2020-09-26 V. V. Alekseev, Yu. A. Kuzina, A. P. Sorokin
The results of studies on the physical chemistry, mass transfer, and technology of alkali liquid-metal coolant are reported. The state of the coolant is determined by the interaction coolant-impurities-structural materials- protective gas. The impurity sources and their intensity were determined: sodium and sodium-potassium alloy – oxygen, hydrogen (tritium), carbon, products of corrosion of structural
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Investigation of the Cooling of Water-Cooled and -Moderated Reactors Based on Electricity Generation Via Residual Heat in Emergency Situations with De-Energization Atom. Energy (IF 0.271) Pub Date : 2020-09-26 R. Z. Aminov, V. E. Yurin, D. Yu. Kuznetsov
Safety enhancement of NPP power units with water-moderated and -cooled reactors on the basis of installation of additional multifunctional low-power steam-turbine generators is studied. It is shown that the parameters of the primary and secondary loops change as the VVER-1000 reactor is cooled via the use of the residual heat in the core to generate steam that serves as the working body for a low-power
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Correction to: Excitation Functions of the Reactions Ag 109 ( p , n ); Ag 109 ( d , 2 n ); Ag 107 (α, 2 n + pn ), and Yield of Cd 109 Atom. Energy (IF 0.271) Pub Date : 2020-08-21 P. P. Dmitriev, I. O. Konstantinov, N. N. Krasnov
To the article “Excitation Functions of the Reactions Ag109 (p, n); Ag109(d, 2n); Ag107 (α, 2n+pn), and Yield of Cd109,” by P. P. Dmitriev, I. O. Konstantinov, and N. N. Krasnov, Vol. 22, No. 4, pp. 386–388, April, 1967.
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Reactivity Measurement in the Prompt-Jump Approximation for the Neutron Flux Atom. Energy (IF 0.271) Pub Date : 2020-08-18 B. D. Abramov
Methods of calculating the nuclear reactor reactivity from the measured time-dependence of the neutron flux are discussed. It is noted that the corresponding problems for the direct and inverse equations of point kinetics in the approximation of a prompt-jump change of neutron flux are not equivalent, which is expressed in that the reactivity values in these problems do not coincide with one another
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Measurement of 186 Re, 188 Re, 189 Re Yield on 186 W Target Irradiation by 4 He, 3 He, 1 H, and 2 H Atom. Energy (IF 0.271) Pub Date : 2020-08-18 V. A. Zagryadskii, S. T. Latushkin, K. A. Makoveeva, T. Yu. Malamut, V. I. Novikov, A. A. Ogloblin, V. N. Unezhev
The saturation yield of the rhenium radioisotopes 186Re, 188Re, and 189Re on irradiation of a 186W target by the nuclei 4He, 3He, 1H, and 2H with energy 47, 25, 15.3, and 19 MeV, respectively, was measured by the activation method. The chosen energy of the accelerated particles made it possible to minimize the contribution of the activity of long-lived rhenium radioisotopes in the desired radionuclides
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Hydraulic Resistance of Fine Packing in Uranium Hexafluoride Rectification Atom. Energy (IF 0.271) Pub Date : 2020-08-18 V. K. Ezhov
The hydraulic resistance of irregular fi ne packing is studied as a function of the process parameters for the rectification of metal hexafluorides. It is shown that the dependence of the hydraulic resistance of irregular fi ne packing on the rectification parameters coincides with the dependence presented in the literature but with different coefficients and exponential factors.
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Interrelation of the Iodine-Activity Limit in RBMK Coolant and the Number of Defective Fuel Pins Atom. Energy (IF 0.271) Pub Date : 2020-08-18 A. V. Krayushkin, A. K. Smirnova
A quantitative assessment of the 131I activity in RBMK coolant as a function of the number of defective fuel pins and the distribution over a fuel run is presented. The 131I yield fraction is determined using a model based on the solution of the diffusion equation with empirical coefficients. This investigation was performed for a core-average FA whose power is a function of the burnup. It is shown
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Gas-Filled Ionization Chamber and Secondary-Emission Detector for Measuring γ-Ray Dose Rate Atom. Energy (IF 0.271) Pub Date : 2020-08-18 S. V. Chuklyaev, A. S. Koshelev
The design of a KGK-2 γ-ray dose rate detector is described. The basic characteristics of the detector are presented. The readings of a KGK-2 gas-filled ionization chamber detector and VED-2 secondary-electron emission detector during power startup of BR-K1 and BR-1M reactors are compared. It is shown that by using KGK-2 and VED-2 detectors in combination the γ-ray dose rate can be measured in the
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Analysis of the Long-Term Yearly Average Volumetric Activity of Radionuclides and the Yearly Absorbed Dose in the Surface Air with Continuous Radioactive Emissions (For Leningrad NPP-2) Atom. Energy (IF 0.271) Pub Date : 2020-08-18 T. V. Perevolotskaya, A. N. Perevolotskii
The purpose of the present work is to analyze the long-term yearly average volumetric activity in the surface air and the yearly absorbed dose of β- and γ-radiation in the spread zone of continuous emissions from NPP. The particulars of the spreading of the emission radionuclides and the associated yearly absorbed radiation dose are determined. It is shown that the atmospheric volumetric activity of
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Deformation of Experimental Fuel Pins with Improved Zirconium-Alloy Cladding in Reactor Tests Atom. Energy (IF 0.271) Pub Date : 2020-08-18 A. V. Burukin, A. I. Dolgov, A. L. Izhutov, P. A. Il’in, V. V. Kalygin, M. A. Mokeichev, A. V. Ugryumov, Yu. N. Dolgov
A stand for inspecting experimental fuel pins in the cooling pool of the MIR.M1 reactor and methodological approaches to measuring the height and diameter of experimental fuel pins are described. The basic characteristics of the equipment used for performing measurements are described. The structural features of an experimental FA (EFA) and the test parameters of experimental fuel pins in an assembly
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On an Optimal Minor-Actinide Transmutation Regime in a Molten-Salt Reactor Atom. Energy (IF 0.271) Pub Date : 2020-08-18 M. N. Belonogov, I. A. Volkov, D. G. Modestov, G. N. Rykovanov, V. A. Simonenko, D. V. Khmel’nitskii
The basic regularities in the transmutation Np, Am, and Cm in a molten-salt burner reactor are examined on the basis of the results of neutronic calculations of an idealized infinite homogeneous medium consisting of metal halogenides with low atomic mass. It is shown that an optimal equilibrium regime for the transmutation of Np, Am, and Cm in a molten-salt burner reactor could exist. In this regime
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Grids with Mixing Elements for VVER Fuel Assemblies Atom. Energy (IF 0.271) Pub Date : 2020-08-18 N. I. Perepelitsa
Grid designs with mixing elements for VVER FA and experimental studies of their thermohydraulic and mass transfer characteristics are analyzed. The Novosibirsk Chemical Concentrates Plant and the Machine Building Plant manufacture the grids. Comparative assessments of the coolant mixing intensity, increase of the critical heat flux and critical power, and coefficient of hydraulic resistance are made
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Effect of NJOY and Grucon Processing Codes in Nuclear Data Preparation for Steel Nuclides Atom. Energy (IF 0.271) Pub Date : 2020-08-18 A. I. Blokhin, E. F. Mitenkova, N. V. Novikov
The observed differences of the neutron fluxes between experiments and calculations on passage of neutrons through thick layers of iron and steel are conditioning the use of better models for representing the scattering cross-sections and energy-angle distributions of neutrons in elastic and inelastic scattering. The effect of the NJOY99 and GRUCON prepared nuclear data for Fe, Cr, and Ni on Keff and
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Kinetic Theory Analysis of Radionuclide Behavior in the Vacuum-Cesium System of a Thermionic Converter Reactor Atom. Energy (IF 0.271) Pub Date : 2020-08-18 V. V. Abannikov, Yu. Yu. Kloss, O. K. Shaikhatarov, O. I. Dodulad, D. V. Shcherbakov, D. Yu. Lyubimov
The behavior of radionuclides (Kr and Xe) and process gases (CO) in the vacuum-cesium channel of a thermionic converter reactor is modeled by solving Boltzmann’s equation numerically. Modeling techniques and a software system were developed in the course of this work. Series of calculations were performed for the variation of the initial flux of radionuclides, the dependence of the radionuclide flux
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Molybdenum Isotope Separation in a Cascade with a Specified Number of Gas Centrifuges in Stages Atom. Energy (IF 0.271) Pub Date : 2020-08-18 V. A. Palkin
A method of calculating and optimizing a multi-flow cascade with a specified number of gas centrifuges in stages on cuts of their partial flows were developed. A special feature of the method is an iterative fitting of the separation coefficients of the gas centrifuges that depend on the feed flow and the division factor of the flow. A computational experiment was conducted on the separation of molybdenum
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EVKLID/V1 Modeling of a Lead-Cooled Reactor Core with Water Vapor Ingress into the Coolant Atom. Energy (IF 0.271) Pub Date : 2020-07-10 D. A. Koltashev
This article is devoted to model calculations of a lead-cooled reactor core performed using the EVKLID/V1 code. The ingress of water vapor into the core is modeled for the stationary state of the reactor at the rated power capacity. The change in the reactivity and power at different mass flow of water vapor is analyzed. Baseline calculations performed using the MCU-FR code were performed in order
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High-Temperature Radiation Embrittlement of Neutron-Irradiated Austenitic Stainless Steels 08Kh18N10T, Ei-847, EP-172, and ChS-68 Atom. Energy (IF 0.271) Pub Date : 2020-07-10 S. I. Porollo, A. A. Ivanov, Yu. V. Konobeev, S. V. Shulepin
The results of research on the influence of the chemical composition, cold-deformation, and irradiation temperature on the short-time mechanical properties of the austenitic stainless steels 08Kh18N10T, EI-847, EP-172, and ChS-68 after neutron irradiation in the BN-350 fast reactor to damaging dose 57–59 dpa in the range 400–490°C are reported. The investigation showed that high-temperature radiation
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Possibility of Irradiating in Russian Reactors the Plutonium Recycled From Mixed Uranium-Plutonium Fuel Fabricated in Marcoule (France) Atom. Energy (IF 0.271) Pub Date : 2020-07-09 N. Camarcat, D. Settimo, J. F. Dhédin, F. Laugier, D. Lemasson, P. Dubuisson, M. Miguirditchian, A. Gay, M. H. Mouliney, V. S. Bezzubtsev, V. M. Troyanov
EdF’s idea of irradiating in Russian fast reactors fuel pins with recycled plutonium arose in February 2016 during a discussion with CEA of testing experimental FA in BN-600. EdF proposed to additionally irradiated several fuel pins fabricated using plutonium obtained after reprocessing of mixed fuel irradiated in PWR. In 2017, the studies with fabrication of full-scale FA were to expensive, so that
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Investigation of High-Temperature Uranium-Dioxide Kernel Creep in Nuclear Reactors Atom. Energy (IF 0.271) Pub Date : 2020-07-09 A. S. Gontar’, V. V. Kuznetsov, M. V. Nelidov, V. S. Serikov
The operation of a high-temperature fuel rod with a fuel kernel consisting of uranium dioxide is accompanied by significant changes in the initial structure of the fuel – a multi-zone dioxide structure with different grain size and shape (growth of initially uniaxial grains, formation of a columnar structure) can form in the transverse section of the kernel. For low level of stress appearing in the
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Celsist Subchannel Module Aided Simulation of Liquid-Metal Coolant Flow in Experimental FA Atom. Energy (IF 0.271) Pub Date : 2020-07-09 E. E. Orlova, V. P. Smirnov, A. E. Vlasenko, A. V. Palagin
The CELSIST subchannel module is described. The results of the simulation of experiments on the flow of liquid metal coolant in model FA are presented: lead-bismuth eutectic alloy in a 19-rod FA on the THEADES stand (Karlsruhe Liquid Metal Laboratory, Germany), sodium in a 19-rod FA on the Bundle 2A FFM stand (ORNL, USA), sodium-potassium eutectic alloy in a 37-rod FA on the 6B stand (IPPE, Russia)
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Methods of Calculating the γ-Radiation Absorbed Dose Rate in Case of Radioactive Contamination of Meadow Biogeocenoses Atom. Energy (IF 0.271) Pub Date : 2020-07-09 T. V. Perevolotskaya, A. N. Perevolotskii, Yu. A. Kurachenko
The absorbed dose rate of external γ-radiation from two sources of radiation – surface soil layer and subsurface phytomass of plants in stand grass – is calculated by different methods. The calculation of the absorbed dose rate based on integration of the dose attenuation function of a point source taking into account the dose accumulation factor was compared with the results of a Monte Carlo solution
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Possibility of Burning Americium in Fast Reactors Atom. Energy (IF 0.271) Pub Date : 2020-07-09 A. V. Gulevich, V. A. Eliseev, D. A. Klinov, L. V. Korobeinikova, M. V. Kryachko, V. A. Pershukov, V. M. Troyanov
The possibilities of burning americium from spent nuclear fuel of thermal reactors in the operating BN-800 are examined. It is shown that because of the small fission cross-section in the neutron spectrum of a fast reactor all of the americium cannot be directly converted into fission products. This can be done only by transmutation of americium into plutonium, which must be separated and directed
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Radioactive Contamination at the Epicenter of a Nuclear Accident and on the Territory of a Ship Repair Yard in Bukhta Chazhma Atom. Energy (IF 0.271) Pub Date : 2020-07-09 A. A. Sarkisov, V. L. Vysotskii, D. V. Dzama, D. A. Pripachkin, V. E. Kalantarov, I. N. Khokhlov
The radiation conditions at a ship repair yard in Bukhta Chazhma after a nuclear accident on a submarine on August 10, 1985 were reconstructed by means of hindcasting taking into account a 3D model of the enterprise and dose rate measurements during the first few days after the accident. The submarine presented the greatest danger during the first few days. The dose rate was equal to 1500–2500 mSv/h
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Space Nuclear Power Systems Startup Optimization Methods Atom. Energy (IF 0.271) Pub Date : 2020-07-09 V. V. Skorlygin
The startup of a space nuclear power system is conducted after the space vehicle is put into its operational orbit. The reactor is in a deeply subcritical state, it is technically unfeasible to use a startup source of neutrons, and ground-based operator intervention is excluded. Since payload usage before the nuclear reactor starts is supported by storage batteries, the problem of reducing the startup
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Radwaste Characteristics in Uranium-Plutonium Nuclear Fuel Production Atom. Energy (IF 0.271) Pub Date : 2020-07-09 V. A. Kashcheev, M. A. Chernikov, A. Yu. Shadrin
Radioactive wastes are formed during the production of uranium-plutonium nuclear fuel at enterprises. In the present article the concentration ranges for uranium, plutonium, and neptunium in liquid and cemented wastes corresponding to different radioactivity classes are determined. The concentration ranges are determined for wastes formed in the production of nitride fuel for the initial load, as well
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General and Particular Separation Potentials for Multicomponent Mixtures Atom. Energy (IF 0.271) Pub Date : 2020-07-09 O. E. Aleksandrov
The definition of the separation potential for multicomponent separation is analyzed. The possibility of introducing a particular separation potential together with the general separation potential for concrete setups is examined. An expression is obtained for the particular separation potential of a gas centrifuge.
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Comparison of D–D and D–T Tubes for Neutron Generators with Sorbed and Stuffed Targets Atom. Energy (IF 0.271) Pub Date : 2020-05-30 S. V. Syromukov
The neutron fluxes of D–D and D–T tubes with sorbed and stuffed targets are compared. Calculations of the change of the neutron flux in generators when a tube of one type is replaced by a tube of a different type are presented. The influence of the atomic-molecular composition of the ion beam and the target material, the hydride stoichiometry, and the isotopic composition of the gas in the getter is
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