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  Subjects -> ENERGY (Total: 261 journals)
    - ENERGY (173 journals)
    - ENERGY: GENERAL (8 journals)
    - NUCLEAR ENERGY (23 journals)
    - PETROLEUM AND GAS (47 journals)
    - WIND ENERGY (10 journals)

ENERGY (173 journals)                  1 2 | Last

Advances in Building Energy Research     Hybrid Journal   (Followers: 11)
Advances in Energy and Power     Open Access   (Followers: 1)
Advances in High Energy Physics     Open Access   (Followers: 12)
Advances in Natural Sciences: Nanoscience and Nanotechnology     Open Access   (Followers: 15)
American Journal of Energy Research     Open Access   (Followers: 6)
Annals of Nuclear Energy     Hybrid Journal   (Followers: 7)
Annual Reports on NMR Spectroscopy     Full-text available via subscription   (Followers: 1)
Annual Review of Resource Economics     Full-text available via subscription   (Followers: 10)
Applied Nanoscience     Open Access   (Followers: 8)
Applied Solar Energy     Hybrid Journal   (Followers: 12)
Archives of Thermodynamics     Open Access   (Followers: 4)
Artificial Photosynthesis     Open Access  
Atomic Energy     Hybrid Journal   (Followers: 6)
Atoms for Peace: an International Journal     Hybrid Journal   (Followers: 3)
Biofuels     Hybrid Journal   (Followers: 7)
Biomass Conversion and Biorefinery     Partially Free   (Followers: 5)
Bulletin de droit nucleaire     Full-text available via subscription   (Followers: 1)
Canadian Journal of Remote Sensing     Full-text available via subscription   (Followers: 13)
Canadian Water Resources Journal     Hybrid Journal   (Followers: 20)
Carbon Management     Hybrid Journal   (Followers: 7)
Catalysis for Sustainable Energy     Open Access   (Followers: 2)
CERN courier. International journal of high energy physics     Free  
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: 2)
Continental Journal of Renewable Energy     Open Access   (Followers: 10)
Current Sustainable/Renewable Energy Reports     Hybrid Journal   (Followers: 4)
Dams and Reservoirs     Hybrid Journal   (Followers: 3)
Development of Energy Science     Open Access   (Followers: 3)
Distributed Generation & Alternative Energy Journal     Hybrid Journal   (Followers: 1)
E3S Web of Conferences     Open Access  
Economics and Policy of Energy and the Environment     Full-text available via subscription   (Followers: 1)
Electrical and Power Engineering Frontier     Open Access   (Followers: 8)
Electronic Journal of Energy & Environment     Open Access   (Followers: 9)
Energy     Partially Free   (Followers: 23)
Energy & Fuels     Full-text available via subscription   (Followers: 25)
Energy and Buildings     Hybrid Journal   (Followers: 7)
Energy and Environment Research     Open Access   (Followers: 9)
Energy and Environmental Engineering     Open Access  
Energy and Power     Open Access   (Followers: 3)
Energy and Power Engineering     Open Access   (Followers: 9)
Energy Conversion and Management     Hybrid Journal   (Followers: 8)
Energy Efficiency     Hybrid Journal   (Followers: 11)
Energy Harvesting and Systems : Materials, Mechanisms, Circuits and Storage     Hybrid Journal   (Followers: 1)
Energy Policy     Partially Free   (Followers: 46)
Energy Prices and Taxes     Full-text available via subscription   (Followers: 5)
Energy Procedia     Open Access   (Followers: 3)
Energy Science & Engineering     Open Access   (Followers: 4)
Energy Science and Technology     Open Access   (Followers: 12)
Energy Strategy Reviews     Partially Free   (Followers: 5)
Energy Studies Review     Open Access   (Followers: 3)
Energy Systems     Hybrid Journal   (Followers: 10)
Energy Technology     Partially Free   (Followers: 3)
Energy, Sustainability and Society     Open Access   (Followers: 17)
Environmental Progress & Sustainable Energy     Hybrid Journal   (Followers: 4)
EPJ Photovoltaics     Open Access   (Followers: 1)
Facta Universitatis, Series : Electronics and Energetics     Open Access  
Foundations and Trends® in Renewable Energy     Full-text available via subscription  
Frontiers in Energy     Hybrid Journal   (Followers: 4)
Frontiers in Energy Research     Open Access   (Followers: 1)
Fuel and Energy Abstracts     Full-text available via subscription   (Followers: 5)
Functional Materials Letters     Hybrid Journal   (Followers: 1)
Gcb Bioenergy     Hybrid Journal   (Followers: 3)
Geothermal Energy     Open Access   (Followers: 1)
GeoWorld     Full-text available via subscription   (Followers: 2)
Green     Full-text available via subscription   (Followers: 1)
IEA Electricity Information     Full-text available via subscription   (Followers: 5)
IEA Natural Gas Information     Full-text available via subscription   (Followers: 4)
IEEE Power and Energy     Full-text available via subscription   (Followers: 11)
IEEE Transactions on Energy Conversion     Hybrid Journal   (Followers: 6)
IEEE Transactions on Nuclear Science     Hybrid Journal   (Followers: 7)
IEEE Transactions on Power Systems     Hybrid Journal   (Followers: 10)
IET Power Electronics     Hybrid Journal   (Followers: 8)
Ingeniería Energética     Open Access  
Innovations : Technology, Governance, Globalization     Hybrid Journal   (Followers: 6)
International Journal of Alternative Propulsion     Hybrid Journal   (Followers: 1)
International Journal of Ambient Energy     Hybrid Journal   (Followers: 2)
International Journal of Applied Power Engineering     Open Access   (Followers: 2)
International Journal of Clean Coal and Energy     Open Access   (Followers: 4)
International Journal of Critical Infrastructure Protection     Hybrid Journal   (Followers: 5)
International Journal of Electric and Hybrid Vehicles     Hybrid Journal   (Followers: 4)
International Journal of Emerging Electric Power Systems     Full-text available via subscription   (Followers: 5)
International Journal of Emerging Multidisciplinary Fluid Sciences     Full-text available via subscription  
International Journal of Energy and Environmental Engineering     Open Access   (Followers: 2)
International Journal of Energy and Power     Open Access   (Followers: 7)
International Journal of Energy Engineering     Open Access   (Followers: 12)
International Journal of Energy Research     Hybrid Journal   (Followers: 10)
International Journal of Energy Science     Open Access   (Followers: 1)
International Journal of Flow Control     Full-text available via subscription   (Followers: 2)
International Journal of Global Energy Issues     Hybrid Journal   (Followers: 7)
International Journal of Green Energy     Hybrid Journal   (Followers: 5)
International Journal of Hydrogen Energy     Partially Free   (Followers: 9)
International Journal of Marine Energy     Full-text available via subscription   (Followers: 2)
International Journal of Nuclear Desalination     Hybrid Journal   (Followers: 2)
International Journal of Nuclear Energy Science and Technology     Hybrid Journal   (Followers: 2)
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: 2)
International Journal of Power and Energy Conversion     Hybrid Journal   (Followers: 3)
International Journal of Regulation and Governance     Hybrid Journal   (Followers: 2)

        1 2 | Last

Journal Cover Atomic Energy
   [8 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  [2210 journals]   [SJR: 0.136]   [H-I: 8]
  • Water in Molybdate Melts and Reactions with its Participation
    • Abstract: It is confirmed experimentally that water is soluble in sodium molybdate metal, and the solubility at 800°C is 0.018 wt.%. On the basis of this phenomenon, a technology is proposed for dewatering zirconium articles, which are subjected to heating in sodium molybdate, by introducing 1–4 wt.% NiMoO4. As a result, the hydrogen content in the article decreases from 10–2 to 0.4·10–3%. It is confirmed experimentally that metallic nickel, with which dissolved water reacts with hydrogen being released, introduced into the melt reduces U3O8 to UO2 in sodium molybdate melt.
      PubDate: 2014-10-14
  • Fracture of the Alloy E-110 in Different Loading Regimes
    • PubDate: 2014-10-14
  • Nuclear-Physical Characteristics of the Reaction 158 Gd( N , G) 159 Gd
    • PubDate: 2014-10-14
  • Analysis of the Possibilities of Developing a Molten-Salt Blanket for a
           Subcritical Demonstration Reactor
    • Abstract: The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency.
      PubDate: 2014-10-14
  • Method of Determining the Detection Efficiency of the MKS-AT1117M
           Radiometer FOR Uranium Deposits
    • PubDate: 2014-10-14
  • Enrichment of Regenerated Uranium with Simultaneous Dilution of
           232–236 U by Raw and Waste Uranium
    • Abstract: A scheme is proposed for a five-flow (three feed, product and waste flows) gas-centrifuge cascade for enriching regenerated uranium simultaneously diluted by natural raw material and waste uranium. Computational experiments show the advantages of such a cascade in terms of the consumption of natural uranium with respect to the previously proposed multiflow cascades. In contrast to previously proposed cascades for enriching regenerated uranium, this cascade makes it possible to vary the consumption of natural uranium in obtaining products of equivalent quality, which makes it possible to seek and pick the optimal way to enrich the regenerated material in order to obtain VVER fuel.
      PubDate: 2014-10-14
  • Methodological Foundations and Development of Computational Optimization
           Complexes for Designing Fast Reactors
    • Abstract: A formulation of the optimal design problem for fast reactors is given and the main difficulties in solving it are examined. The computational software complexes developed at different times and making it possible to find the best reactor characteristics without resorting to variant calculations are reviewed. The particularities of problems, methods of solution and methods of organizing the computational process so as to reduce the computing time are discussed. Ways to improve and develop computational optimization complexes are proposed taking account of current requirements for new-generation fast power reactors and the increased possibilities of computational technology.
      PubDate: 2014-10-14
  • Comprehensive Radiometric Investigation of Mr Reactor Pool Water
    • Abstract: The MR multiloop research reactor is now being disassembled at the National Research Center Kurchatov Institute. A complex α-, β- and γ-spectrometric investigation of the water in the reactor’s pool and fuel-storage pool has been conducted. It was found that the main dose-forming radionuclide is 137Cs. 234U, 235U, 236U, 238U, 238Pu, 239–240Pu, and 241Pu have been found in the pool water, which indicates that the fuel matrix is present in its components. A reduction of the water level in the pool by 1 m increases the equivalent dose rate at a distance of 1 m from the edge of the pool by a factor of 2, which can be explained by the contribution of 137Cs settled on the wall of the storage pool. The efficiency with which the walls of the MR reactor’s storage pool are cleaned by a high-pressure jet of water and by mechanical means was investigated. The mechanical method of removing the deposits from the pool walls is most effective.
      PubDate: 2014-10-14
  • Mathematical Modeling and Computational Determination Using the MCU-PTR
           Code of the Irradiation Conditions for Structural Materials in the Ampoule
           Setups of the IR-8 Reactor
    • Abstract: A large amount of materials science research in which the vertical channels of the core and reflector are used is being conducted in the IR-8 reactor. To develop experimental programs for reactor research it is of fundamental importance to know not only these parameters but also how they change. The present article validates the possibility of using the computational data obtained with the MCU-PTR code to analyze the neutron-physical parameters and determine the conditions of irradiation of the experimental samples. A comparative analysis of the experimental and computational data shows that it is possible to use this method. The method is now used for tracking the operation of the reactor computationally, pre-reactor determination of the conditions of irradiation of the experimental samples, tracking computationally the conditions of irradiation of the experimental samples of the vessel materials used in nuclear-power facilities and other experiments in IR-8.
      PubDate: 2014-10-14
  • Prospects for Nuclear District Heating Based on Power-Generating Units
           with Capacity up to 100 MW
    • Abstract: The main objective of this research is to make a preliminary evaluation of the effective scales of application of nuclear district heating based on units with capacity to 100 MW for supplying energy to cities in the unified power system of Russia. The regions where nuclear district heating is economically efficient but the strong dependence of the results on changes in multiple factors still does not permit significant scales of adoption before 2030 are shown.
      PubDate: 2014-10-14
  • Analysis of the Parameters of the Target Unit of a Molten-Salt Subcritical
           Electronuclear Facility
    • Abstract: A variant of the target unit based on tungsten rods cooled by molten-salt coolant (alkali-metal fluorides) in a subcritical electronuclear facility is examined. The results of calculations of its main parameters are presented: the neutron yield, neutron spectrum on the lateral surface, top and bottom ends of the target, total energy release, specific energy release and induced activity. The calculations are performed using the three codes MCNPX 2.6B, SHIELD and KATRIN-2.5 and the codes ORIHET3 and DCHAIN-SP for calculating the changes in the radioactivity of the main units. The discrepancies in the parameters of the target unit of a subcritical electronuclear facility were determined by calculating the standard deviation factors. Apparently, the uncertainties in the computational results for the differential and integral parameters are due to the nuclear models and libraries in the programs used.
      PubDate: 2014-10-14
  • Catching RuO 4 on Solid Sorbents
    • Abstract: New kinds of fuel for fast reactors are being developed. Uranium-plutonium nitride fuel has good neutronphysical indices, but there are peculiarities to handling it after irradiation in a reactor. At the stage of dissolution of the irradiated uranium-plutonium nitride fuel in nitric acid, a significant quantity of volatile radioactive fission products, including ruthenium, is released into the gas phase. In the present work, the possibility of catching ruthenium tetroxide on sorbents was evaluated experimentally. The catching of ruthenium tetroxide by granules of pyrolusite, γ-Al2O3, and γ-Al2O3 permeated by a 10% solution of carbamide or nitric acid was investigated. The results can be used in the development of a technology and apparatus for catching volatile product of ruthenium fission.
      PubDate: 2014-10-14
  • Dewatering of Salt Melts of Radioactive Wastes from NPP by Induction
    • Abstract: An experimental setup for dewatering melts of salts of radioactive wastes has been developed at the Moscow Engineering Physics Institute (MIFI). Induction heating of the working chamber with the material being processed and vacuum pumping of water vapor were used. An evaporation rate of free water 11.25 liters/h was achieved in the course of the experiments. Experiments on dewatering of a simulator of a melt of liquid radioactive wastes from NPP with initial moisture content 31.9 wt.% were performed. The content of bound water in the final sample was 5%. There was no free water. The setup can process liquid radioactive wastes in the form of melt and bottom residues in batch and continuous regimes.
      PubDate: 2014-10-14
  • Distribution of the Fission Reactionrate in a Weakly Coupled System for
           Testing the Checkerboard Model
    • Abstract: The distributions of the fission reaction rate in a weakly coupled system of the Kef of the World class are analyzed. The distribution of the fission reaction rate for different working parameters and initial neutron distribution is presented. The MCU-FREE and MCNP5 computer codes are used to perform the calculations. The working parameters for obtaining the correct fission reaction rate distribution are recommended. The problem of the sensitivity of the main neutron-physical characteristics to small perturbations in weakly coupled systems requires further study.
      PubDate: 2014-10-09
  • Investigation of (U, Th)O 2 Fuel
    • Abstract: The properties of (U, Th)O2 fuel prepared with UO2 mass fraction 1–30% by different methods is investigated. It is shown that the fabrication method significantly influences the density, crystal lattice parameter, O/U ratio and thermal conductivity of fuel pellets. The ammonium oxylate technology for coprecipitation of uranium and thorium with a precipitate containing simultaneously particles of different fractional composition, including nanosize particles, makes it possible to obtain sintered (U, Th)O2 pellets with UO2 mass fraction 1–13%, density 93–96% of the theoretical value and O/Me ratio <2.0. It is shown how the thermal conductivity of the fuel depends on the O/Me ratio.
      PubDate: 2014-10-08
  • In Memory of Academician Ivan Ivanovich Novikov – First
           Editor-in-Chief of Atomnaya Énergiya
    • PubDate: 2014-10-08
  • Critical Regions of a Radiation Monitor
    • Abstract: The critical regions (parts of space surveyed by a monitor) where it is expedient to use different combinations of detector counts (criteria) are determined. Variants with one, two, and four detectors – to which cases with a large number of detectors reduce – are examined. It is shown that there exist regions, comprising half the controlled space, where the use of additional detectors and criteria is inexpedient. The form and size of these regions depend on the relative arrangement of the detectors. The results obtained can be used to optimize the arrangement of detectors and to reduce the detection thresholds of stationary radiation monitors.
      PubDate: 2014-10-08
  • Mathematical Modeling of the Operation of a Directed Bremsstrahlung
           Formation Line
    • PubDate: 2014-10-01
  • Determination of the Yield and Isobaric Composition of Heavy Products of
           the Reaction 235U( n , ƒ)
    • Abstract: The heavy thermal-fission products of 235U in the mass range 125–155, kinetic energy range 42–78 MeV, and effective ionic charge states 18–29 were measured in the nuclear research reactor VVR-SM at the Institute of Nuclear Physics of the Academy of Sciences of the Republic of Uzbekistan. Fission products with mass Ai in the range from 1 to 5 isobars were found. In all, more than 100 isobars were identified for the measured fission products.
      PubDate: 2014-10-01
  • Evaluation of the Radiation Resistance and Thermal Stability of
           15KH2MFA-A, Modifications a and B, Steel and Weld-Seam Metal
    • Abstract: A comparative evaluation is made of the thermal stability and radiation resistance of VVER-1000 vessel materials and new compositions of 15Kh2MFA-A steel of modifications A and B with low nickel content 0.2–0.8%. For this, complex structural studies and mechanical tests were performed on samples of materials in the following states: the initial state; after isothermal soaking at 330°C up to 7500 h, provoking grainboundary embrittlement of heat treatment in the interval of maximum development of reversible temper brittleness; and, accelerated irradiation to fluence corresponding to the service life of a reactor vessel to 60 or more years. The advantages of reducing the nickel content of steel with the new compositions, which is expressed in their improved radiation resistance and thermal stability, are shown.
      PubDate: 2014-10-01
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