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ENERGY (184 journals)                 | Last

Showing 1 - 200 of 406 Journals sorted alphabetically
ActaEnergetica     Open Access  
Advances in Building Energy Research     Hybrid Journal   (Followers: 9)
Advances in Energy and Power     Open Access   (Followers: 9)
Advances in High Energy Physics     Open Access   (Followers: 19)
Advances in Natural Sciences: Nanoscience and Nanotechnology     Open Access   (Followers: 28)
American Journal of Energy Research     Open Access   (Followers: 10)
Annals of Nuclear Energy     Hybrid Journal   (Followers: 8)
Annual Reports on NMR Spectroscopy     Full-text available via subscription   (Followers: 4)
Annual Review of Resource Economics     Full-text available via subscription   (Followers: 12)
Applied Nanoscience     Open Access   (Followers: 8)
Applied Solar Energy     Hybrid Journal   (Followers: 17)
Archives of Thermodynamics     Open Access   (Followers: 7)
Artificial Photosynthesis     Open Access   (Followers: 1)
Asian Bulletin of Energy Economics and Technology     Open Access   (Followers: 2)
Atomic Energy     Hybrid Journal   (Followers: 4)
Atoms for Peace: an International Journal     Hybrid Journal   (Followers: 3)
Batteries     Open Access   (Followers: 4)
Biofuel Research Journal     Open Access   (Followers: 4)
Biofuels     Hybrid Journal   (Followers: 11)
Biofuels Engineering     Open Access  
Biomass Conversion and Biorefinery     Partially Free   (Followers: 10)
Bulletin de droit nucleaire     Full-text available via subscription   (Followers: 1)
Canadian Journal of Remote Sensing     Full-text available via subscription   (Followers: 41)
Canadian Water Resources Journal     Hybrid Journal   (Followers: 20)
Carbon Management     Hybrid Journal   (Followers: 6)
Catalysis for Sustainable Energy     Open Access   (Followers: 7)
CERN courier. International journal of high energy physics     Free   (Followers: 7)
Chain Reaction     Full-text available via subscription  
Clefs CEA     Full-text available via subscription   (Followers: 1)
Computational Water, Energy, and Environmental Engineering     Open Access   (Followers: 4)
Dams and Reservoirs     Hybrid Journal   (Followers: 4)
Development of Energy Science     Open Access   (Followers: 4)
Distributed Generation & Alternative Energy Journal     Hybrid Journal   (Followers: 3)
E3S Web of Conferences     Open Access  
Economics and Policy of Energy and the Environment     Full-text available via subscription   (Followers: 8)
Electrical and Power Engineering Frontier     Open Access   (Followers: 23)
Electricity Journal     Partially Free   (Followers: 1)
ENERGETIKA. Proceedings of CIS higher education institutions and power engineering associations     Open Access   (Followers: 1)
Energy     Partially Free   (Followers: 26)
Energy & Environment     Hybrid Journal   (Followers: 18)
Energy & Fuels     Full-text available via subscription   (Followers: 29)
Energy and Buildings     Hybrid Journal   (Followers: 10)
Energy and Emission Control Technologies     Open Access   (Followers: 4)
Energy and Environment Focus     Free   (Followers: 6)
Energy and Environment Research     Open Access   (Followers: 13)
Energy and Environmental Engineering     Open Access   (Followers: 7)
Energy and Power     Open Access   (Followers: 9)
Energy and Power Engineering     Open Access   (Followers: 18)
Energy Conversion and Management     Hybrid Journal   (Followers: 11)
Energy Efficiency     Hybrid Journal   (Followers: 11)
Energy Harvesting and Systems : Materials, Mechanisms, Circuits and Storage     Hybrid Journal   (Followers: 3)
Energy Law Journal     Full-text available via subscription   (Followers: 4)
Energy Materials : Materials Science and Engineering for Energy Systems     Hybrid Journal   (Followers: 20)
Energy Policy     Partially Free   (Followers: 58)
Energy Prices and Taxes     Full-text available via subscription   (Followers: 5)
Energy Procedia     Open Access   (Followers: 2)
Energy Reports     Open Access   (Followers: 5)
Energy Research & Social Science     Full-text available via subscription   (Followers: 7)
Energy Science & Engineering     Open Access   (Followers: 4)
Energy Science and Technology     Open Access   (Followers: 11)
Energy Storage Materials     Full-text available via subscription   (Followers: 1)
Energy Strategy Reviews     Partially Free   (Followers: 10)
Energy Studies Review     Open Access   (Followers: 6)
Energy Systems     Hybrid Journal   (Followers: 13)
Energy Technology     Partially Free   (Followers: 5)
Energy Technology & Policy     Open Access   (Followers: 2)
Energy, Sustainability and Society     Open Access   (Followers: 18)
Environmental Progress & Sustainable Energy     Hybrid Journal   (Followers: 8)
EPJ Photovoltaics     Open Access   (Followers: 5)
Facta Universitatis, Series : Electronics and Energetics     Open Access  
Foundations and Trends® in Renewable Energy     Full-text available via subscription   (Followers: 2)
Frontiers in Energy     Hybrid Journal   (Followers: 4)
Frontiers in Energy Research     Open Access   (Followers: 4)
Fuel and Energy Abstracts     Full-text available via subscription   (Followers: 6)
Functional Materials Letters     Hybrid Journal   (Followers: 2)
Gcb Bioenergy     Open Access   (Followers: 2)
Geomechanics for Energy and the Environment     Full-text available via subscription   (Followers: 1)
Geothermal Energy     Open Access   (Followers: 3)
Geothermal Energy Science     Open Access   (Followers: 2)
Green     Hybrid Journal   (Followers: 1)
Green Energy & Environment     Open Access   (Followers: 2)
IEA Electricity Information     Full-text available via subscription   (Followers: 3)
IEA Natural Gas Information     Full-text available via subscription   (Followers: 3)
IEEE Power and Energy     Full-text available via subscription   (Followers: 25)
IEEE Transactions on Energy Conversion     Hybrid Journal   (Followers: 14)
IEEE Transactions on Nuclear Science     Hybrid Journal   (Followers: 10)
IEEE Transactions on Power Systems     Hybrid Journal   (Followers: 28)
IET Power Electronics     Hybrid Journal   (Followers: 31)
Ingeniería Energética     Open Access  
Innovations : Technology, Governance, Globalization     Hybrid Journal   (Followers: 12)
International Journal of Alternative Propulsion     Hybrid Journal   (Followers: 6)
International Journal of Ambient Energy     Hybrid Journal   (Followers: 1)
International Journal of Applied Power Engineering     Open Access   (Followers: 5)
International Journal of Clean Coal and Energy     Open Access   (Followers: 5)
International Journal of Coal Science & Technology     Open Access   (Followers: 1)
International Journal of Electric and Hybrid Vehicles     Hybrid Journal   (Followers: 9)
International Journal of Emerging Electric Power Systems     Hybrid Journal   (Followers: 6)
International Journal of Energy and Environmental Engineering     Open Access   (Followers: 4)
International Journal of Energy and Power     Open Access   (Followers: 10)
International Journal of Energy and Statistics     Hybrid Journal   (Followers: 2)
International Journal of Energy Engineering     Open Access   (Followers: 10)
International Journal of Energy Research     Hybrid Journal   (Followers: 9)
International Journal of Energy Science     Open Access   (Followers: 1)
International Journal of Global Energy Issues     Hybrid Journal   (Followers: 8)
International Journal of Green Energy     Hybrid Journal   (Followers: 10)
International Journal of Hydrogen Energy     Partially Free   (Followers: 15)
International Journal of Marine Energy     Full-text available via subscription   (Followers: 1)
International Journal of Nuclear Desalination     Hybrid Journal  
International Journal of Nuclear Energy Science and Technology     Hybrid Journal   (Followers: 4)
International Journal of Nuclear Governance, Economy and Ecology     Hybrid Journal   (Followers: 2)
International Journal of Nuclear Hydrogen Production and Applications     Hybrid Journal   (Followers: 1)
International Journal of Nuclear Knowledge Management     Hybrid Journal   (Followers: 1)
International Journal of Ocean and Climate Systems     Open Access   (Followers: 7)
International Journal of Power and Energy Conversion     Hybrid Journal   (Followers: 3)
International Journal of Smart Grid and Green Communications     Hybrid Journal  
International Journal of Sustainable Energy     Hybrid Journal   (Followers: 12)
International Journal of Sustainable Energy Planning and Management     Open Access   (Followers: 3)
International Journal of Sustainable Engineering     Hybrid Journal   (Followers: 7)
International Journal of Thermodynamics     Open Access   (Followers: 8)
International Journal of Turbomachinery, Propulsion and Power     Open Access  
Journal of Alternate Energy Sources & Technologies     Full-text available via subscription  
Journal of Building Performance Simulation     Hybrid Journal   (Followers: 6)
Journal of China Coal Society     Open Access  
Journal of Computational Multiphase Flows     Open Access  
Journal of Energy     Open Access   (Followers: 1)
Journal of Energy & Natural Resources Law     Hybrid Journal   (Followers: 3)
Journal of Energy Chemistry     Full-text available via subscription   (Followers: 2)
Journal of Energy in Southern Africa     Open Access   (Followers: 2)
Journal of Energy Storage     Full-text available via subscription   (Followers: 2)
Journal of Energy Technologies and Policy     Open Access   (Followers: 5)
Journal of Energy, Environment & Carbon Credits     Full-text available via subscription   (Followers: 2)
Journal of Fusion Energy     Hybrid Journal   (Followers: 3)
Journal of International Energy Policy     Open Access   (Followers: 3)
Journal of Modern Power Systems and Clean Energy     Open Access   (Followers: 9)
Journal of Nano Energy and Power Research     Full-text available via subscription   (Followers: 5)
Journal of Nuclear Energy Science & Power Generation Technology     Hybrid Journal   (Followers: 3)
Journal of Ocean Engineering and Marine Energy     Hybrid Journal   (Followers: 2)
Journal of Physical Chemistry C     Full-text available via subscription   (Followers: 30)
Journal of Power Electronics & Power Systems     Full-text available via subscription   (Followers: 9)
Journal of Radiological Protection     Full-text available via subscription   (Followers: 4)
Journal of Renewable Energy     Open Access   (Followers: 8)
Journal of Semiconductors     Full-text available via subscription   (Followers: 4)
Journal of Solar Energy     Open Access   (Followers: 10)
Journal of Solar Energy Engineering     Full-text available via subscription   (Followers: 19)
Journal of Sustainable Bioenergy Systems     Full-text available via subscription   (Followers: 1)
Journal of Sustainable Energy Engineering     Full-text available via subscription   (Followers: 1)
Journal of Technology Innovations in Renewable Energy     Hybrid Journal  
Materials for Renewable and Sustainable Energy     Open Access   (Followers: 8)
Materials Today Energy     Hybrid Journal  
Natural Resources     Open Access   (Followers: 2)
Nature Energy     Hybrid Journal   (Followers: 9)
Nigerian Journal of Technological Research     Full-text available via subscription   (Followers: 1)
Nuclear Data Sheets     Full-text available via subscription  
Nuclear Engineering and Design     Hybrid Journal   (Followers: 13)
Nuclear Law Bulletin     Full-text available via subscription   (Followers: 2)
Oil and Gas Journal     Full-text available via subscription   (Followers: 11)
Oil, Gas, Coal and Electricity - Quarterly Statistics - Electricite, charbon, gaz et petrole - Statistiques trimestrielles     Full-text available via subscription   (Followers: 9)
Open Journal of Energy Efficiency     Open Access   (Followers: 2)
Power Technology and Engineering     Hybrid Journal   (Followers: 3)
Proceedings of the Institution of Civil Engineers - Energy     Hybrid Journal   (Followers: 3)
Progress in Nuclear Energy     Hybrid Journal   (Followers: 1)
Protection and Control of Modern Power Systems     Open Access   (Followers: 1)
Radiochimica Acta     Hybrid Journal   (Followers: 5)
Radioprotection     Hybrid Journal   (Followers: 1)
Science and Technology of Nuclear Installations     Open Access   (Followers: 2)
Smart Grid and Renewable Energy     Open Access   (Followers: 8)
Solar Energy     Hybrid Journal   (Followers: 22)
Solar Energy Materials and Solar Cells     Hybrid Journal   (Followers: 37)
SourceOCDE Energie nucleaire     Full-text available via subscription  
SourceOECD Nuclear Energy     Full-text available via subscription   (Followers: 1)
South Pacific Journal of Natural and Applied Sciences     Hybrid Journal  
Strategic Planning for Energy and the Environment     Hybrid Journal   (Followers: 4)
Structural Control and Health Monitoring     Hybrid Journal   (Followers: 9)
Surface Science Reports     Full-text available via subscription   (Followers: 20)
Sustainable Energy     Open Access   (Followers: 3)
Sustainable Energy Technologies and Assessments     Full-text available via subscription  
Sustainable Energy, Grids and Networks     Hybrid Journal   (Followers: 4)
Technology Audit and Production Reserves     Open Access  
Universal Journal of Applied Science     Open Access   (Followers: 2)
Washington and Lee Journal of Energy, Climate, and the Environment     Open Access   (Followers: 3)
Waste Management     Hybrid Journal   (Followers: 12)
Water International     Hybrid Journal   (Followers: 15)
Wiley Interdisciplinary Reviews : Energy and Environment     Hybrid Journal   (Followers: 5)
Wind Energy     Hybrid Journal   (Followers: 4)
Wind Engineering     Hybrid Journal   (Followers: 3)

       | Last

Journal Cover Atomic Energy
  [SJR: 0.216]   [H-I: 12]   [4 followers]  Follow
   Hybrid Journal Hybrid journal (It can contain Open Access articles)
   ISSN (Print) 1573-8205 - ISSN (Online) 1063-4258
   Published by Springer-Verlag Homepage  [2353 journals]
  • Neutron-Physical Model Impact on the Calculation of a Serious Accident
           with Sodium Boiling in a Fast Reactor
    • Authors: Yu. M. Ashurko; A. V. Volkov; K. F. Raskach; N. V. Solomonova
      Pages: 217 - 225
      Abstract: A comparative analysis is made of calculations of a loss-of-coolant accident in a 1500 MW(t) fast reactor. The COREMELT code with different neutron-physical modules RADAR3D and RAKAR2D and the same thermohydraulic module COREMELT are used. The computational results are used as a basis for comparing the self-protection of a reactor with a sodium cavity at the top of the core for the case of a serious accident with coolant boiling. The effect of the diffusion and transport modules of the spatial neutron-physics models on the calculation is analyzed.
      PubDate: 2017-08-01
      DOI: 10.1007/s10512-017-0259-3
      Issue No: Vol. 122, No. 4 (2017)
  • Measurement of the Power Coefficient of Reactivity of VVR-Ts in a Wide
           Power Range
    • Authors: V. V. Kolesov; D. S. Samokhin; O. Yu. Kochnov
      Pages: 226 - 229
      Abstract: The power coefficient of reactivity of VVR-Ts was previously determined only in the range 10–11 MW. The aim of the present work was to determine the power coefficient of reactivity in the range 1–10 MW. The experiment was performed on a completely depoisoned reactor. The change in the reactivity excess was determined according to the position of the control rods. It was shown experimentally that the power coefficient of reactivity is not constant and is negative for the given power range. Thus, the VVR-Ts reactor can operate safely in different operating regimes.
      PubDate: 2017-08-01
      DOI: 10.1007/s10512-017-0260-x
      Issue No: Vol. 122, No. 4 (2017)
  • Magnetic Flowmeter for Fast Sodium Reactors
    • Authors: I. D. Vel’t; E. A. D’yakonova; Yu. V. Mikhailova; N. V. Terekhina
      Pages: 243 - 251
      Abstract: A magnetic flowmeter for liquid sodium is described. The inductor in this device consists of an electromagnet generating a pulsed, low-frequency, magnetic field. The use of a pulsed magnetic field made it possible to separate the informative component of the signal from all electromagnetic interference whose time variation is not a multiple of the frequency of the excitation magnetic field. Thus, all interferences at the industrial frequency and the thermo-emf are eliminated. This increases the accuracy of flow rate measurements significantly and makes it possible to reduce the magnetic field in the channel. The power of the inductor does not exceed 0.5 W. There is no need to adjust the zero point, and it is possible to measure low flow rates and the reverse flow. The physical principles of the method of measurement, the design particulars and technical characteristics of the device, and the results of tests are examined.
      PubDate: 2017-08-01
      DOI: 10.1007/s10512-017-0262-8
      Issue No: Vol. 122, No. 4 (2017)
  • Technology and Facility for Incinerating Irradiated Reactor Graphite
    • Authors: V. A. Kashcheev; O. A. Ustinov; S. A. Yakunin; V. S. Zagumennov; A. O. Pavlyuk; S. G. Kotlyarevskii; E. V. Bespala
      Pages: 252 - 256
      Abstract: The USG-1 facility was developed to incinerate spent reactor graphite. It is equipped with a monitoring and control system; its maximum capacity is 10 kg/h. Trial combustion of a batch of unirradiated graphite was conducted. The tests showed that the units in the facility are serviceable and irradiated reactor graphite can be incinerated directly in an air flow. For a 1.5 kg load of graphite, the burn rate at 900°C was equal to 0.3 kg/h. The burn rate increases with increasing load. The incineration of irradiated graphite bushings of the EI-2 reactor in the USG-1 incinerator was studied at PDC UGR. The completeness of incineration was 95% and the 137Cs catching efficiency was 95%. With modification of the gas purification unit, the USG-1 incinerator can be used to burn irradiated graphite contaminated by traces of nuclear fuel and in monitoring the atmospheric emissions of 14CO2.
      PubDate: 2017-08-01
      DOI: 10.1007/s10512-017-0263-7
      Issue No: Vol. 122, No. 4 (2017)
  • Mobile Systems for Fluoride Reprocessing of Spent Nuclear Fuel
    • Authors: N. M. Trotsenko; O. G. Lebedev; D. Yu. Chuvilin
      Pages: 257 - 262
      Abstract: Experts at the National Research Center – Kurchatov Institute have proposed compact reprocessing of spent nuclear fuel from the naval fleet as well as NPPs close to the Arctic coast, directly at the site of offloading, on the basis of an innovative, experimentally verified, fluoride-distillation technology. They propose developing a mobile system consisting of a seagoing carrier (vessel with small displacement) or terrestrial carrier (railroad platform) on which is mounted a compact process line consisting of fluorination and purification apparatus as well as auxiliary setups. There are no liquid wastes in the fluoride processes; solid wastes are to be removed, as they are formed, from the mobile system into special sites in waste locations of the Arctic coast for long-term dry storage in concrete containers.
      PubDate: 2017-08-01
      DOI: 10.1007/s10512-017-0264-6
      Issue No: Vol. 122, No. 4 (2017)
  • Possibilities of Increasing Logging Efficiency with Simultaneous Analysis
           of Neutron and Gamma Fields Formed in Oil Wells
    • Authors: B. Yu. Bogdanovich; K. I. Kozlovskii; A. V. Nesterovich; A. E. Shikanov; A. V. Il’inskii; E. G. Urmanov
      Pages: 271 - 277
      Abstract: The increase in the efficacy of studying well saturation in simultaneous analysis of radiation fields by means of pulsed neutron, activation, and spectrometric logging is examined. It is shown that neutron activation logging can in principle be realized in experimental testing of an operating model of apparatus in producing geophysical objects. Technical solutions using neutron well radiators based on sealed accelerator tubes with a laser source of deuterons and magnetic insulation, as a result of a large neutron yield combined with high pulse stability, as well as a thermally stabilized γ spectrometer, are proposed and validated.
      PubDate: 2017-08-01
      DOI: 10.1007/s10512-017-0266-4
      Issue No: Vol. 122, No. 4 (2017)
  • Hot Particles and Radionuclide Transport in Water Media
    • Authors: N. L. Kuchin; A. I. Laikin; Yu. A. Platovskikh
      Pages: 278 - 283
      Abstract: The characteristics of hot particles in the ambient environment are presented: activity, propagation, size, and density as well as contribution to the total activity of contaminants, distribution factor, leach rate, and deposition rate. The differences of suspensions, bottom deposits, and hot particles are shown. The equations governing the transport of radionuclides are formulated for systems, consisting of hot particles and suspensions, in water and bottom deposits. The coefficients in the equations are determined and the possibility of radionuclides being removed from bays by tides is taken into account. Solutions are obtained for the transport equations and the average sizes of the activity spots owing to hot particles and ordinary suspensions are determined. The possibility of transport of hot particles over large distances in a river floodplain is examined. The water circulation rate at which hot particles are carried out of flooded objects is determined.
      PubDate: 2017-08-01
      DOI: 10.1007/s10512-017-0267-3
      Issue No: Vol. 122, No. 4 (2017)
  • Diagnostics Indicators in Monitoring the Technical State of Direct Charge
           Sensors in Nuclear Reactors
    • Authors: A. M. Pankin; N. V. Korovkin
      Pages: 284 - 289
      PubDate: 2017-08-01
      DOI: 10.1007/s10512-017-0268-2
      Issue No: Vol. 122, No. 4 (2017)
  • Space-Time Characteristics of Relativistic Electrons Moderated in Matter
    • Authors: V. A. Akat’ev; E. V. Metelkin; A. M. Savinov
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0280-6
  • Neutron Flux Density Effect on Vessel Steel Embrittlement
    • Authors: V. A. Nikolaenko; E. A. Krasikov
      Abstract: The effect of the neutron flux density on the embrittlement of the reactor vessel materials is analyzed in an investigation of the impact of neutron irradiation on their properties. The evaluation of the dependence of radiation embrittlement of the vessel steel on the neutron flux density is made to a fi rst approximation for conventional virtual material by averaging the radiation embrittlement coefficient, taking account of the chemical composition, AF = 800(P + 0.07Cu). The actual radiation embrittlement coefficient was determined experimentally on the basis of the normative dependence ΔTF = AF(F·10–18)1/3. It was found as a result that the dependence of the radiation embrittlement coefficient of virtual steel on the neutron flux density has the form AF = 17.8 + 9.5/φ, where φ is the neutron flux density in the units 1011 sec–1·cm–2. As the neutron irradiation intensity decreases, embrittlement increases; the highest sensitivity to the neutron flux density is observed in the range (0.1–1)·1011 sec–1·cm–2. This dependence makes it possible to evaluate the impact of the intensity of neutron irradiation of vessel steel on embrittlement.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0275-3
  • Molten Salt Reactor for 99 Mo Production
    • Authors: A. L. Tataurov; O. S. Feinberg
      Abstract: 99Mo production in a molten salt reactor with fuel salt based on metal fl uorides (LiF–BeF2–UF4) is examined. The proposed method of production is based on a particularity of the behavior of gaseous fission products in salt melts. Molybdenum, together with some other metals, does not form stable compounds in fluoride melt. At least 50% of fragment molybdenum in a molten salt nuclear-physical facility will be in a gas-aerosol phase above the surface of the molten salt. Neutron-physical and thermohydraulic calculations were performed taking into account the specific features of a molten salt reactor. The optimal configuration of the reactor, the materials used, the fuel salt composition, and the fuel cycle are described.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0270-8
  • Enrichment of Regenerated Uranium in a Gas Centrifuge Cascade with
           Simultaneous Dilution of 232,236 U by Waste and Low-Enrichment Uranium
    • Authors: A. Yu. Smirnov; G. A Sulaberidze; A. A. Dudnikov; V. A. Nevinitsa
      Abstract: It is shown that regenerated uranium can be enriched in a gas centrifuge cascade with three feed streams (waste uranium, low-enrichment uranium, regenerated uranium) and simultaneous dilution of the isotopes 232,234,236U. Computational experiments were performed for different 235U content in the low-enrichment feed. The chosen combination of diluents makes it possible simultaneously to lower the separative work expenditure and reduce the consumption of native raw material with respect to not only previously used multi-stream cascades but also a standard cascade for enrichment of native uranium.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0278-0
  • Particulars of Uranium-Plutonium Nitride Fuel Swelling During
           Low-Temperature Irradiation in Fast Reactor to Burnup 5.5% h.a.
    • Authors: A. V. Belyaeva; I. F. Gil’mutdinov; I. Yu. Zhemkov; F. N. Kryukov; S. V. Kuz’min; O. N. Nikitin; Yu. A. Ivanov; Y. A. Kostyukov
      Abstract: Electron-microscopic and electron-probe x-ray spectral studies of nitride fuel microstructure in thin sections and fractures of pellets in correlation with the xenon distribution were conducted in order to obtain data on the particulars of porosity formation and mechanisms of swelling of nitride fuel during low-temperature irradiation. The results attest indications of restructuring of nitride fuel irradiated to burn up 5.5% h.a. at temperature below 880°C. The formation of some grain structure in the restructuring process, accompanied by emission of gaseous fission products from the fuel matrix into pores, affects the swelling rate of uranium-plutonium nitride fuel.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0273-5
  • Computational and Experimental Analysis of Pu, Np, Am, Cm Reaction Rates
           on BFS Critical Benches
    • Authors: O. N. Andrianova; V. A. Dulin; I. V. Mikhailova; A. A. Andrianov
      Abstract: A computational and experimental analysis is presented of a systematized and reconsidered series of experimental studies of the absolute fission rate of Pu, Np, Am, and Cm performed on the critical benches BFS-1, -2 in the period from 1990 to 2013. Twenty seven critical configurations are examined – models of the reactor core with different types of fuel and coolant. Previously obtained experimental values are re-examined according to more accurate methods of processing the results taking account of residual deformations of chambers and with the introduction of corrections for the efficiency of fragment detection (acts of fission in chambers). The computational models of the assemblies are supplemented by models for evaluating the ratio of the fission rates using non-analogical modeling algorithms. The matched set of experimental data and computational models can be used in diverse applied and fundamental problems.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0269-1
  • Dependence of the Determined Value of the Elastic Modulus of a Material on
           the Ratio of the Distance Between the Supports to the Height of the
           Cross-Section of the Bent Sample
    • Authors: V. Yu. Gol’tsev; A. V. Osintsev; A. S. Plotnikov
      Abstract: A method is proposed for determining the elastic modulus of a material from the results of bending tests performed on a prismatic sample using simultaneously the method of digital correlation of images for precise measurement of the displacements of points in the sample. This procedure was tested in three-point bending of steel and graphite samples. The effect of the ratio of the distance between the supports to the height of the cross-section of the sample on the reliability of the determined elastic modulus of the material is evaluated. The values obtained for the modulus of elasticity of steel and graphite agree with the characteristic values for the investigated materials when the ratio of the distance between the supports to the height of the cross-section of the sample is greater than 7.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0276-2
  • Model Studies of Coolant Flow Hydrodynamics in VVER-1000 In-Reactor
           Pressure Channel
    • Authors: V. G. Krapivtsev
      Abstract: The results of the development, construction, and testing of a small-scale model of a pressure channel of coolant motion inside the VVER-1000 vessel from the entry connections to the coolant flow entry into the core are presented. A hydrodynamic bench, a model of in-reactor pressure channel in the VVER-1000, and methods for studying the coolant flow hydrodynamics in the channel model are described. The results of experimental studies and a comparative analysis of the coolant flow velocity distribution along the annular pressure channel from the entry into the channel through the pressure connections to the entry section in the elliptical bottom of the cavity of the model are presented. The experimental results obtained for different flow regimes of the coolant through the pressure connections are presented.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0271-7
  • Effect of Operating Parameters on RBMK-1000 Fuel-Element Cladding
    • Authors: A. V. Sukhikh; S. S. Sagalov; S. V. Pavlov
      Abstract: The results of research on the corrosion state of the fuel elements of sixteen RBMK-1000 fuel assemblies operating at the Leningrad NPP to burnup 6.1–35.7 MW·days/kg are presented. The dependences of the oxide thickness on the outer surface of cladding on the operating time, fuel burnup, and average power release of FA are presented. It is determined that increasing the power output from 0.9 up to 2.1 MW approximately halves the oxidation rate on the sections between the spacing lattices. For close FA operating parameters, larger oxide thickness was recorded on sections of fuel elements beneath the steel spacing lattices than beneath the zirconium lattices. It is shown that in terms of the conditions for its manifestation and external indicators the additional oxidation arising beneath the steel lattices has the characteristic features of shadow corrosion.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0274-4
  • Use of Radioactive Beams of 7 Be Nuclei to Study the Wear Resistance of
    • Authors: A. A. Ogloblin; V. N. Unezhev; V. I. Novikov; T. Yu. Malamut
      Abstract: This work is devoted to the use of beams of radioactive nuclei for applied purposes – to study the wearresistance of materials used in different industries. The crux of the method is that the radioactive nuclei obtained in the nuclear reactions 1H(7Li, 7Be) and 1H(10B, 7Be) are implanted in the experimental sample. After implantation of the nuclei, the sample undergoes wear tests. The γ-radiation of the implanted nuclei is high-energy; the spectrum is comparatively simple and does not produce appreciable radiation damage in the test samples. The method has been successfully tested in determining the wear-resistance of machine parts and mechanisms.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0279-z
  • Solid-Phase Conversion of Depleted Uranium Tetrafluoride into Oxides Using
           Mechanoactivated Quartz with the Addition of Sodium Fluoride
    • Authors: G. D. Polenov; S. V. Chizhevskaya; A. V. Zhukov; E. P. Magomedbekov
      Abstract: The role of sodium fluoride, added to quartz before the latter is mechanically activated, in the solid-phase conversion of depleted uranium tetrafluoride into uranium oxides without mixing of the components of the mixture is determined.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0277-1
  • HYDRA-IBRAE/LM/V1 Thermohydraulic Code Verification Based on BN-600
    • Authors: I. A. Klimonov; E. V. Usov; G. A. Dugarov; A. A. Butov; I. G. Kudashov; E. N. Ivanov; N. A. Mosunova; V. F. Strizhov; A. M. Anfimov; V. S. Gorbunov; D. V. Kuznetsov; S. L. Osipov; A. I. Bel’tyukov
      Abstract: The results of thermohydraulic code HYDRA-IBRAE/LM/V1 verification on experimental data obtained using the BN-600 reactor in different years are described. The particulars of the computational scheme of the reactor using HYDRA-IBRAE/LM/V1 for modeling the BN-600 operating regime are presented. In preparing the scheme, special attention was devoted to accurate modeling of the reactor cool-down regimes on natural circulation as being most important from the safety validation standpoint. The computational results obtained with the uncertainty of the initial data taken into account are presented for such a cool-down regime.
      PubDate: 2017-09-12
      DOI: 10.1007/s10512-017-0272-6
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