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  Subjects -> ENERGY (Total: 246 journals)
    - ENERGY (162 journals)
    - ENERGY: GENERAL (8 journals)
    - NUCLEAR ENERGY (21 journals)
    - PETROLEUM AND GAS (47 journals)
    - WIND ENERGY (8 journals)

ENERGY (162 journals)                  1 2 | Last

Advances in Building Energy Research     Hybrid Journal   (Followers: 11)
Advances in High Energy Physics     Open Access   (Followers: 12)
Advances in Natural Sciences: Nanoscience and Nanotechnology     Open Access   (Followers: 14)
American Journal of Energy Research     Open Access   (Followers: 5)
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: 10)
Archives of Thermodynamics     Open Access   (Followers: 4)
Atomic Energy     Hybrid Journal   (Followers: 5)
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: 12)
Canadian Water Resources Journal     Hybrid Journal   (Followers: 19)
Carbon Management     Hybrid Journal   (Followers: 5)
Catalysis for Sustainable Energy     Open Access   (Followers: 2)
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: 9)
Current Sustainable/Renewable Energy Reports     Hybrid Journal   (Followers: 2)
Dams and Reservoirs     Hybrid Journal   (Followers: 2)
Development of Energy Science     Open Access   (Followers: 2)
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: 7)
Electronic Journal of Energy & Environment     Open Access   (Followers: 8)
Energy     Partially Free   (Followers: 21)
Energy & Fuels     Full-text available via subscription   (Followers: 22)
Energy and Buildings     Hybrid Journal   (Followers: 6)
Energy and Environment Research     Open Access   (Followers: 8)
Energy and Power Engineering     Open Access   (Followers: 7)
Energy Conversion and Management     Hybrid Journal   (Followers: 6)
Energy Efficiency     Hybrid Journal   (Followers: 10)
Energy Policy     Partially Free   (Followers: 37)
Energy Prices and Taxes     Full-text available via subscription   (Followers: 4)
Energy Procedia     Open Access   (Followers: 2)
Energy Science & Engineering     Open Access   (Followers: 3)
Energy Science and Technology     Open Access   (Followers: 9)
Energy Strategy Reviews     Partially Free   (Followers: 4)
Energy Studies Review     Open Access   (Followers: 3)
Energy Systems     Hybrid Journal   (Followers: 8)
Energy Technology     Partially Free   (Followers: 2)
Energy, Sustainability and Society     Open Access   (Followers: 15)
Environmental Progress & Sustainable Energy     Hybrid Journal   (Followers: 3)
EPJ Photovoltaics     Open Access  
Frontiers in Energy     Hybrid Journal   (Followers: 2)
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: 2)
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: 8)
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: 9)
IET Power Electronics     Hybrid Journal   (Followers: 7)
IngenierĂ­a EnergĂ©tica     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: 1)
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: 3)
International Journal of Emerging Electric Power Systems     Full-text available via subscription   (Followers: 4)
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: 4)
International Journal of Energy Engineering     Open Access   (Followers: 11)
International Journal of Energy Research     Hybrid Journal   (Followers: 9)
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: 1)
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: 2)
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)
International Journal of Sustainable Energy     Hybrid Journal   (Followers: 9)
International Journal of Sustainable Energy Planning and Management     Open Access  
International Journal of Sustainable Engineering     Hybrid Journal   (Followers: 7)
International Journal of Thermodynamics     Open Access   (Followers: 1)
ISRN Power Engineering     Open Access   (Followers: 1)
ISRN Renewable Energy     Open Access  
Journal of Alternate Energy Sources & Technologies     Full-text available via subscription   (Followers: 1)
Journal of Building Performance Simulation     Hybrid Journal   (Followers: 3)

        1 2 | Last

Journal Cover Atomic Energy
   [7 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]
  • Neutron-Physical Characteristics of a Neutron Source for the Production of
           Radioactive Isotopes Based on the Interaction of Electrons with Liquid
    • Abstract: The nuclear-physical characteristics obtained for a gallium target in a series of experiments using the time-of-flight method, the method of threshold indicators and a spectrometer based on a 3He proportional counter on the IREN setup (JINR, Dubna) are presented. The absolute values of the energy spectra of leakage neutrons in the energy range from 10 keV to 15 MeV were measured. The activation method was used to measure the neutron flux density on the surface of a gallium target: (2.882 ± 0.098) · 108 sec–1 · cm–2. The integral yield of neutrons obtained from the gallium target on the basis of these data was 1.54 · 1014 sec–1 with average current 4 mA. The time dependence of the activation level of the gallium target was measured. It was shown as a result of the analysis that the background level is reached on the surface of the irradiated gallium target in 5 days.
      PubDate: 2014-08-01
  • Experimental Research on Thermophysical Processes for Safety Validation of
           new-Generation Vver
    • PubDate: 2014-07-27
  • High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast
           Reactors for Hydrogen Production
    • Abstract: Studies show that in principle it is possible by relying on the BN-600 design to secure the required parameters of a reactor setup with a fast reactor with high-temperature sodium coolant (BN-VT) for hydrogen production. The calculations for 600 MW(t) BN-VT for electricity and hydrogen production based on solid-oxide electrolysis of water taking account of a fundamentally different method of purification – removal of hydrogen and tritium from the sodium by vacuum pumping through special membranes – have shown that the efficiency of such a system is ~40 % and hydrogen production volume is 2.8 · 104 liters/sec. The purification of hydrogen by removing tritium to a concentration ensuring the maximum admissible hydrogen concentration in the hydrogen produced 3.26 Bq/liter, imposes additional requirements on the hydrogen removal system.
      PubDate: 2014-07-27
  • Russian Codes for Safety Analysis of Sodium-Cooled Fast Reactors
    • Abstract: An approach to validating the safety of sodium-cooled fast reactors which was devised in Russia as these reactors were developed is presented. The collection of computational codes used for validating safety is described. Attention is focused on a group of codes which are intended for systematic analysis of all phases of a serious beyond design-basis accident resulting in the destruction of the core. The domestic approach to the analysis of the consequences of serious accidents is compared to the methodology developed abroad. Up to now the code system under development has made it possible to perform the main tasks of design validation, but the chosen path of development, where a separate computational code was developed for each individual problem, is not exhausted. On the one hand the complexity of the mathematical models drawn into the analysis has increased significantly, while on the other hand significant advances have been made in the development of computational technologies. The answer to the present situation is the tendency observed in the world nuclear community toward developing integrated codes and multipurpose computational systems. In Russia, this tendency is realized in the program for the development of a new generation of code systems within the framework of a special federal program.
      PubDate: 2014-07-27
  • Analysis of the Present Status of Lead and Lead-Bismuth Coolant Technology
    • Abstract: Analysis has shown that the current research on the technology of heavy liquid-metal coolants includes scientific-research and experimental development work on the validation, design and development of methods and means as well as the direct preparation of the coolant, the startup of circulation loops with heavy liquid-metal coolants and routine operation and decommissioning. The current methods and means include hydrogen purification of the coolant and loop by removal of slag-forming impurities, regulation of dissolved oxygen in the coolant for anticorrosion protection of steel, filtration of the coolant and protective gas and monitoring of the coolant under reactor and non-reactor conditions. The current processes presuppose careful preparation of heavy liquid-metal coolants before and during loading of the circulation loop, a complex of measures in startup regimes and minimal worker diversion for maintenance during routine operation of the facility.
      PubDate: 2014-07-27
  • Computational and Experimental Validation of the Planned Emergency
           Heat-Removal System for BN-1200
    • Abstract: The results of computational and experimental validation of the design of the emergency heat-removal system for BN-1200 are presented. The results of experimental studies performed on a water model of the V-200 integrated stand are presented, and the planning of experiments on the TISEI stand for validation of the efficiency and operating regimes using the BURNA, GRIF, and Flow Vision computational design codes is discussed.
      PubDate: 2014-07-27
  • Nuclear Power as a Component of Innovative Development in a Globalized
           World Economy
    • Abstract: It is shown that it is not so much the internal problems as the macroeconomic situation that has a decisive effect on nuclear power in different countries. Analysis performed in the international project INPRO under the auspices of IAEA shows that many developing countries have big plans for growing nuclear capacities and they hope to expand the market for services in the nuclear-power sphere. The potential accumulated in Russia in technologies of sodium-cooled fast reactors with mixed uranium-plutonium oxide fuel should be used to solve the internal problems of the nuclear industry and to expand the package of services at the closing stage of the NFC when selling domestically produced reactors.
      PubDate: 2014-07-27
  • Development of Sodium Coolant Technology for Fast Reactors
    • Abstract: The results of investigations of the composition of sodium impurities and sodium coolant filtrate during prolonged operation of a fast reactor and the methods and means for monitoring impurities and removing them from sodium coolant are presented. Models of mass transfer of dissolved impurities and suspensions of the components of steel in sodium loops are described. The mass transfer of tritium formed in a fast reactor is analyzed.
      PubDate: 2014-07-27
  • Development of an Evaluated Nuclear Database for Modern Technologies
    • Abstract: The main phases in the development of the constants required for neutron-physical calculations of fast reactors, ranging from systems of BNAB group constants to modern national libraries of the BROND and ROSFOND evaluated nuclear data files, are examined. Problems for subsequent conversion of the libraries into licensed sets of standard data for nuclear technological projects are formulated.
      PubDate: 2014-07-27
  • 60th Anniversary of the Startup of the world’s First Nuclear Power
           Plant in Obninsk
    • PubDate: 2014-07-27
  • From the First npp to Large-Scale Nuclear Power
    • Abstract: The advancement of domestic research and development work on reactor technologies from the world’s first NPP built in Obninsk to modern fast reactors with liquid-metal coolants is analyzed. The contribution of the Physics and Energy Institute to the development of a strategy for the advancement of large-scale nuclear power based on a closed nuclear fuel cycle with fast reactors is examined. It is noted that a scientific and technical base now exists for implementing our country’s initiative for securing sufficient energy for stable development of the world and the global infrastructure for nuclear power based on a network of international nuclear fuel centers and expanded exports of new-generation nuclear power plants with thermal and fast reactors including an attractive package of NFC services. The basic problems are formulated within the framework of the future development of reactor technologies for improving the safety and cost-effectiveness of NPP with new-generation fast reactors which are now in operation or being designed.
      PubDate: 2014-07-27
  • Azimuthal Deformation Particulars of Single-Crystal Cladding of
           High-Temperature Fuel Elements
    • Abstract: The particulars of the azimuthal deformation and the reasons for the formation of faceting on single-crystal molybdenum cladding with the <111> axis oriented longitudinally in tests for structural creep at 1650°C under internal argon gas pressure are investigated. It is shown that the periodic local nonuniformity of the azimuthal deformation of <111> cladding and the appearance of faceting are associated with the difference of the maximum shear stress in the active slip planes for single crystals with a bcc lattice in the range of orientations of the stretch axis <110>–<112>. Cladding sections located at the center of the interval <110>–<112> possess weak resistance to high-temperature creep and sites of deformation localization.
      PubDate: 2014-07-01
  • Regularities in the Radiation Decomposition and Synthesis of Plutonium
    • Abstract: Different methods of stabilizing plutonium hexafluoride using trifluoromethylperfluorocyclohexane and high-valence inorganic fluorides whose physical and chemical properties differ very little from those of plutonium hexafluoride are examined. The interaction of plutonium tetrafluoride with solid krypton difluoride is studied and the kinetic regularities of this process are investigated.
      PubDate: 2014-07-01
  • Centrifuge Number Optimization of a Cascade with One or Several Types of
    • Abstract: The particulars of the calculation of the optimal parameters of a cascade with prescribed types of steps and total number of centrifuges are examined. Maximization of the separation power of the cascade is proposed as an optimization criterion. A numerical-analytical method is developed for calculating the optimal flows of the steps with the chosen number and point of feeding and a prescribed centrifuge distribution in the cascade. Examples showing the effectiveness of the new method and the properties of optimal cascades comprised of one and several types of steps are presented.
      PubDate: 2014-07-01
  • Corrosion Model for Zirconium-Niobium Alloys in Pressurized Water Reactors
    • Abstract: An engineering model of corrosion of zirconium-niobium alloys is described. It takes account of the alloying composition, the content of lithium and boron in the coolant, the heat flux on the surface of fuel elements and the intensity of the neutron irradiation. The parametric dependences used in the model are based on the results of tests performed in autoclaves and research reactors. The results of verification of the model on data from post-reactor studies of PWR and VVER fuel assemblies operating in nominal regimes are presented.
      PubDate: 2014-07-01
  • Optimization and Long-Life Validation Methods for EGC
    • Abstract: The methods and results of accelerated tests performed on fuel and structural materials, individual units and an entire EGC for computational and experimental validation of service-life–power characteristics are examined for long-life (≥7 yr) EGC operating regimes. The results of such studies provide the requisite initial data for the KIM software system used to model the service-life behavior of EGC taking account of the interaction of the main service-life-determining processes. It is shown on the basis of complex computational and experimental studies that the time required for reactor tests of EGC in order to validate a long service life, including for dual-regime operation as part of an NPP, can be reduced.
      PubDate: 2014-07-01
  • Stages for Reclassifying Globus-1 Peaceful Nuclear Explosion Object as a
           Site for Preserving Special Radwastes
    • Abstract: Data are presented on the radioecological state of the object Globus-1, which has contaminated sections, an unequipped surface repository for wastes and wells in a nuclear explosion zone with a wrecked waste isolation system. Recommendations are given for equipping the damaged peaceful nuclear explosion object using as a site for preserving special radioactive wastes.
      PubDate: 2014-07-01
  • Temperature Distribution in Connection Zones During Heat-Treatment of Weld
    • Abstract: Cracking of the weld joints in Du300 austenitic pipelines, which are part of multiple forced circulation loops, remains an urgent problem in spite of the compensatory measures adopted. The multiple forced circulation loop in RBMK-1000 is a complicated system of pipelines with different diameters, equipment and fixtures made of different materials. Its separate elements have different geometry and structural features in different power-generating units. High-temperature heat treatment makes it possible to adopt compensatory measures under cramped conditions in complex geometry without degrading the reliable results of ultrasonic monitoring. For safety in NPPs, it is necessary to meet the requirements specified in the normative-technical documentation. Calculations of the heat exchange in the structure elements were performed to meet them. The computational results are presented here.
      PubDate: 2014-07-01
  • Photon Dose Accumulation Factor in Concrete, Iron, and Lead for
           10–50 Mev Monoenergetic Sources
    • PubDate: 2014-07-01
  • Reconstruction of the North-West Radioactive Track During the Accident at
           the Fukushima-1 Npp (Japan) Using Sokrat/V3 and Prolog Software
    • Abstract: The radioactive track formed on March 15, 2011 during the accident at the Fukushima-1 nuclear power plant (Japan) is reconstructed using the PROLOG–SOKRAT/V3 software system. The emission of radionuclides into the atmosphere and the radiation conditions are estimated taking account of the complex relief of the location. Comparing the computed activity, radionuclide composition and fallout density showed satisfactory agreement with actual measurements.
      PubDate: 2014-07-01
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