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  Subjects -> ENERGY (Total: 262 journals)
    - ENERGY (174 journals)
    - ENERGY: GENERAL (8 journals)
    - NUCLEAR ENERGY (23 journals)
    - PETROLEUM AND GAS (47 journals)
    - WIND ENERGY (10 journals)

ENERGY (174 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: 14)
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: 9)
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: 6)
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: 11)
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: 3)
Electrical and Power Engineering Frontier     Open Access   (Followers: 8)
Electronic Journal of Energy & Environment     Open Access   (Followers: 9)
Energy     Partially Free   (Followers: 24)
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 Journal The     Full-text available via subscription  
Energy Policy     Partially Free   (Followers: 48)
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: 6)
Energy Studies Review     Open Access   (Followers: 4)
Energy Systems     Hybrid Journal   (Followers: 10)
Energy Technology     Partially Free   (Followers: 3)
Energy, Sustainability and Society     Open Access   (Followers: 18)
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   (Followers: 1)
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: 7)
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)

        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]
  • Cross-Border Transport During Small Discharges of Radioactive Substances
           into the Atmosphere
    • Abstract: The results of modeling of cross-border transport during small discharges of radioactive substances into the atmosphere are presented. The modeling is performed for the example of the April 2013 radiation incident in Elektrostal. It is shown that aerosol particles containing 137Cs did not significantly affect the radiation conditions on the territory of the European part of our country and the Scandinavian countries.
      PubDate: 2014-12-09
       
  • Centrifugal Extractors with Magnetic Coupling for Radiochemical and
           Chemical Production
    • Abstract: Variants of designs of hermetic centrifugal extractors whose drive contains a cylindrical magnetic coupling are presented. A frequency converter (inverter) with the standard torque-limiting function was used for reliable startup of centrifugal extractors with an asynchronous electric motor. The proposed centrifugal extractors have been tested successfully on a production stand. No failures attributable to the magnetic coupling were recorded.
      PubDate: 2014-12-09
       
  • Prediction of Self-Decontamination of Contaminated Territory Near the
           Fukushima-1 NPP (Japan)
    • Abstract: A method is proposed for analyzing and evaluating the dynamics of self-decontamination of the region of the Fukushima-1 NPP contaminated by radioactive substances. The activity flux into the sea and average self-decontamination time of the territory due to decay and wash-off of the radionuclides 137Cs and 134Cs in the region of the NPP are obtained. The wash-off time constant of 137Cs for the contaminated territory is determined from the experimental data. It is significantly greater than for the basins of the other rivers studied. This is due to the hydrological particularities of the rivers in Japan. It is shown that the maximum dose rate in the region of contamination will decrease to the background level in approximately 200 years. It is determined that the 137Cs concentration in suspension does not depend on the water flow rate in the river; the 137Cs flux is proportional to this flow rate, including in floods.
      PubDate: 2014-12-09
       
  • Radionuclide Ratios in Precipitation on the Territory of Belarus After the
           Chernobyl Accident: Calculation from Gamma-Spectrometric Measurements on
           Soil in May–July 1986
    • Abstract: The correlations between the fallout density and ratio of radionuclides in different regions of Belarus after the accident at the Chernobyl NPP are investigated using data obtained by means of gamma-spectrometric measurements performed on soil in May–July 1986. It is shown that the isotopes of cesium and/or ruthenium are most suitable for reconstructing the activity of 131I in the fallout. Charts showing the isolines of the activity ratios 131I/137Cs and 134Cs/137Cs in the fallout are constructed. The geometric averages obtained for the log-normal distribution of the ratios 134Cs/137Cs and 131I/137Cs in terms of May 10, 1986 equal 0.47 and 5.4, respectively. The distribution of the activity ratio 131I/137Cs in the fallout and the correlation coefficients show that on the whole there is no consistent interrelation between the fallout indices of these radionuclides over the territory.
      PubDate: 2014-12-09
       
  • Mathematical Modeling and Computational Analysis of the Neutron-Physical
           Parameters of the IR-8 Reactor with Conversion to Low-Enrichment Uranium
           Fuel
    • Abstract: A comparative computational analysis of the neutron-physical parameters is made for the IR-8 reactor using core fuel assemblies containing fuel based on low-enrichment uranium: IRT-3M (in development), IRT-4M (in use), and IRT-4M-290 (proposed) with increased (to 290 g) 235U content in six-tube fuel assemblies. The neutron-physical parameters for equilibrium loads of a reactor with conversion to different types of low-enrichment uranium fuel are obtained by means of a computational analysis using the MCU-PTR Monte-Carlo code verified for IR-8. The neutron flux density, estimated fuel costs, and neutron irradiation when using these fuel assemblies are presented relative to the IRT-3M operating fuel assemblies with high-enrichment uranium are presented. It is shown that a load 290 g load (increased from 264 g) in the six-tube IRT-4M fuel assemblies is expedient.
      PubDate: 2014-12-02
       
  • Production of Medical 99 Mo and Molybdenum-Technetium Generators at the
           karpov Research Institute of Physical Chemistry
    • Abstract: This article is devoted to the development of the production of 99Mo used in nuclear medicine. The stages in the development of the production of 99Mo and molybdenum-technetium generators are shown. Production has increased several-fold over the period 2009–2013 and meets the demand of domestic nuclear medicine. The problem of recycling the uranium from an irradiated target after 99Mo is extracted from the target is important and strongly influences the price of 99Mo. A technology for reprocessing uranium-containing tailings with the uranium obtained being returned into the 99Mo production cycle has been developed at the Scientific-Research Institute for Physical Chemistry. This has eliminated the need to purchase expensive high-enrichment uranium for targets and has made it possible to use the uranium remaining from the reprocessing of irradiated targets.
      PubDate: 2014-12-02
       
  • Prospects for Using Nitride Fuel in Fast Reactors with a Closed Nuclear
           Fuel Cycle
    • Abstract: The present status of research on dense nitride fuel for liquid-metal cooled fast reactors is examined. It is noted that within the framework of project Proryv nitride fuel is to be used in reactors with sodium (BN-1200) as well as lead coolant (BREST). Carbothermal synthesis of nitride from oxide powders has been chosen to fabricate the experimental fuel elements. Several experimental assemblies with mixed uranium-plutonium nitride fuel have been fabricated for tests in BOR-60 and BN-600. It is shown that the existing global experience in studying nitride fuel is insufficient for validating such fuel for use in BN-1200 and BREST. A complex program for computational-experimental validation of fuel elements is being implemented for validating the serviceability of fuel elements.
      PubDate: 2014-11-30
       
  • Effect of Bellows on the Separation of Uranium Isotopes in a Supercritical
           Gas Centrifuge
    • Abstract: The effect of bellows in a supercritical gas centrifuge on the separative power is studied experimentally. It is found that the separative power of a gas centrifuge with bellows placed in the rotor is lower than that of a centrifuge with a smooth rotor and the difference increases with increasing number of bellows in the rotor. It is shown that the reduction of the separative power can be compensated to a large extent by increasing the temperature component of the circulation flow.
      PubDate: 2014-11-30
       
  • Evaluation of the Possibility of Recycling Metal Radwastes in the Nuclear
           Industry
    • Abstract: The possibility of using partially decontaminated metal as a material for fabricating building bars and containers for handling wastes is examined. The specific activity of radionuclides in metal at which such parts can be used safely in the nuclear industry is evaluated. A methodological approach is proposed for evaluating the maximum admissible specific activity of recycled metal. Examples of calculations showing that it is possible to proceed to the evaluation of the economic efficiency of handling wastes in this manner are presented.
      PubDate: 2014-11-30
       
  • Calculation of Reactivity Accidents for the IRT Reactor at Mephi to
           Validate Conversion to Low-Enrichment Fuel
    • Abstract: The results of emergency-incident calculations for the IRT reactor at MEPhI with high-enrichment uranium fuel and with conversion to IRT-3M fuel assemblies with fuel kernels based on the alloy U–9% Mo in an aluminum matrix with 19.7% enrichment are presented. Transient processes due to unauthorized positive reactivity insertion during the fulfillment of safety functions are examined. The PARET 7.5 software was used to calculate the transient processes.
      PubDate: 2014-11-30
       
  • Optimization of a Cascade by Partial Flow Sections with Prescribed Target
           Concentration
    • Abstract: The problem of calculating a cascade with several feed flows is examined. Relations are proposed for calculating a cascade by partial-flow sections. A procedure is developed for optimizing the parameters of a cascade for the separation of a multicomponent mixture of isotopes. Minimization of the total flow with a prescribed target component concentration at the waste and product of the cascade is taken as the criterion of optimization. A computational experiment is performed. A characteristic example of the optimization of a three-flow cascade is presented.
      PubDate: 2014-11-30
       
  • 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
           Heating
    • 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
       
 
 
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