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  Subjects -> ENERGY (Total: 284 journals)
    - ENERGY (188 journals)
    - ENERGY: GENERAL (8 journals)
    - NUCLEAR ENERGY (25 journals)
    - PETROLEUM AND GAS (53 journals)
    - WIND ENERGY (10 journals)

ENERGY (188 journals)                  1 2 | Last

Advances in Building Energy Research     Hybrid Journal   (Followers: 12)
Advances in Energy and Power     Open Access   (Followers: 3)
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: 7)
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: 11)
Applied Nanoscience     Open Access   (Followers: 10)
Applied Solar Energy     Hybrid Journal   (Followers: 12)
Archives of Thermodynamics     Open Access   (Followers: 4)
Artificial Photosynthesis     Open Access  
Atomic Energy     Hybrid Journal   (Followers: 5)
Atoms for Peace: an International Journal     Hybrid Journal   (Followers: 4)
Batteries     Open Access  
Biofuels     Hybrid Journal   (Followers: 9)
Biomass Conversion and Biorefinery     Partially Free   (Followers: 6)
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: 9)
Energy     Partially Free   (Followers: 26)
Energy & Fuels     Full-text available via subscription   (Followers: 25)
Energy and Buildings     Hybrid Journal   (Followers: 7)
Energy and Emission Control Technologies     Open Access  
Energy and Environment Focus     Free  
Energy and Environment Research     Open Access   (Followers: 10)
Energy and Environmental Engineering     Open Access   (Followers: 1)
Energy and Power     Open Access   (Followers: 3)
Energy and Power Engineering     Open Access   (Followers: 10)
Energy Conversion and Management     Hybrid Journal   (Followers: 8)
Energy Efficiency     Hybrid Journal   (Followers: 12)
Energy Harvesting and Systems : Materials, Mechanisms, Circuits and Storage     Hybrid Journal   (Followers: 1)
Energy Journal The     Full-text available via subscription  
Energy Law Journal     Full-text available via subscription   (Followers: 2)
Energy Materials : Materials Science and Engineering for Energy Systems     Hybrid Journal   (Followers: 19)
Energy Policy     Partially Free   (Followers: 47)
Energy Prices and Taxes     Full-text available via subscription   (Followers: 5)
Energy Procedia     Open Access   (Followers: 4)
Energy Reports     Open Access  
Energy Research & Social Science     Full-text available via subscription  
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: 11)
Energy Technology     Partially Free   (Followers: 3)
Energy Technology & Policy     Open Access  
Energy, Sustainability and Society     Open Access   (Followers: 19)
Environmental Progress & Sustainable Energy     Hybrid Journal   (Followers: 5)
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     Hybrid Journal   (Followers: 2)
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: 12)
IEEE Transactions on Energy Conversion     Hybrid Journal   (Followers: 7)
IEEE Transactions on Nuclear Science     Hybrid Journal   (Followers: 7)
IEEE Transactions on Power Systems     Hybrid Journal   (Followers: 11)
IET Power Electronics     Hybrid Journal   (Followers: 13)
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 Coal Science & Technology     Open Access  
International Journal of Critical Infrastructure Protection     Hybrid Journal   (Followers: 6)
International Journal of Electric and Hybrid Vehicles     Hybrid Journal   (Followers: 5)
International Journal of Emerging Electric Power Systems     Hybrid Journal   (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 and Statistics     Hybrid Journal  
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: 3)
International Journal of Global Energy Issues     Hybrid Journal   (Followers: 6)

        1 2 | Last

Journal Cover   Atomic Energy
  [SJR: 0.199]   [H-I: 9]   [5 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  [2302 journals]
  • Standard Designs of Magnetic Systems and Magnetic Clutches for Hermetic
           Equipment
    • Abstract: The standard designs of magnetic systems and magnetic clutches with different high-coercivity permanent magnets (barium ferrite and from alloys of rare-earth elements), which are used in hermetic equipment for radiochemical and chemical production processes, are described. The basic dimensions and transmitting tractive forces and torques are presented.
      PubDate: 2015-04-18
       
  • Dose Factors for Photon Accumulation in Uranium Oxides and Hexafluoride
    • Abstract: The first results of a calculation of the dose factors of photon accumulation in uranium oxide UO2, triuranium octoxide U3O8, and uranium hexafluoride UF6 for a point isotropic monoenergetic source of photons with energy from 0.01 to 5 MeV for material thickness ranging from 0.5 to 25 μd are presented. The calculations are performed in infinite and barrier geometry taking account of all interactions of photons with matter. The possibilities of determining the accumulation factors of these mixtures on the basis of the accumulation factors of the individual elements are examined. Corrections for the barrier effect of the material are determined; it is noted that they are independent of the thickness, material, and energy of the source photons. The information obtained will make it possible to lower the computational error of the radiation dose when working with these materials, which are widely used in the nuclear fuel cycle.
      PubDate: 2015-04-18
       
  • Integral Indices of the Radiological Effect of Open and Closed Fuel Cycle
           Objects on the General Population
    • Abstract: The collective dose is examined as an integral characteristic of the radiological effect of nuclear fuel cycle enterprises on the general population. A relation is obtained for evaluating the ecological factor, which takes account of the specifics of radionuclides from the standpoint of their migration capacity and the particularities of dose load formation. The ecological factors are calculated for 241Am, 242mAm, 242Am, 243Am, 242Cm, 243Cm, 244Cm, 245Cm, 246Cm, 247Cm, 248Cm, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 244Pu, 235U, 236U, and 238U. Links where the activity of the daughter radionuclides was taken as equal to the activity of long-lived precursors are singled out in the decay chains of the actinides. The dynamics of the yearly collective dose for the general population, formed by individual actinides with activity 1 Bq in the emissions and their decay products, for a long period of time is calculated. The results are suitable for performing comparative radioecological assessments of enterprises in open and closed nuclear fuel cycles.
      PubDate: 2015-04-18
       
  • Comparative Analysis of Methods for Testing Materials for Fatigue Cracking
           Resistance
    • Abstract: The conventional methods of testing for fatigue cracking resistance (compact samples) are compared with testing with a constant amplitude of the stress intensity factor (DCB samples). Examples are presented of the effect of the ambient environment on the growth rate of a crack in a DCB sample and constant growth rate of a crack in a double beam sample with constant amplitude of the stress intensity factor. The advantages and limitations of the testing methods studied are discussed. It is noted that DCB samples and double-beam samples with crack length independent stress intensity factor hold promise for studying the regularities of crack growth not only under cyclic but also under prolonged static loading.
      PubDate: 2015-04-18
       
  • Determination of the Parameters of Plutonium Blocks Placed Inside
           Containers
    • Abstract: Measurements were performed with 1.05 and 3.15 kg plutonium blocks with known (nominal) 239Pu fractions 88.7, 91.0, 93.2, and 95.2% in order to check the possibility of determining their mass and enrichment by using a neutron detector – an active well coincidence counter (AWCC). Analysis of double and triple neutron-neutron coincidences was performed taking spatial effects into account. The intensity of the source of spontaneous fissions in the block and thereby the effective mass of 240Pu were determined on the basis of the requirement that the neutron multiplicities obtained from double and triple coincidences are the same. The 239Pu content was determined to within 0.003–0.004 (1σ), which makes it possible to reliably determine the 239Pu content in the blocks, equal to 91% (power-grade) and 93% (weapons-grade). The plutonium mass in a block is determined to within ±2–3% from the obtained effective neutron multiplication factor.
      PubDate: 2015-04-18
       
  • Thermodynamic Modeling of the Phase Composition of Mixed Uranium-Plutonium
           Mononitride with Impurity Oxygen Under Irradiation to Burnup 140
           GW·days/ton and Temperature 900–1400 K
    • Abstract: Thermodynamic modeling of the phase composition of mixed uranium-plutonium mononitride with impurity oxygen as a function of burnup and temperature under irradiation by fast neutrons has shown that the accumulation of fission products results in the formation of heterogeneous fuel: a multicomponent solid solution based on uranium-plutonium oxynitride that contains yttrium, zirconium, and lanthanides and separate nitride, oxide, metal, and intermetallides phases as well as alkaline-metal iodides and, apparently, bromides. The change in the content of these phases as a function of burnup to 140 GW·days/ton and temperature 900–1400 K is calculated. The effect of the individual phases formed in the course of irradiation on the effective thermal conductivity of the fuel is evaluated together with the diffusion coefficient of xenon atoms in the fuel kernel.
      PubDate: 2015-04-18
       
  • Analytical Possibilities of Detecting Trace Quantities of Beryllium by
           ERIAD Mass-Spectrometry
    • Abstract: The possibility of mass-spectrometric determination of the beryllium concentration in the air in work rooms is examined. Experiments have shown that the ERIAD ion source (electro-sprayng with controlled atomization in the source) gives the required rapid-analysis of the beryllium content, including at a level 10 times lower than the maximum admissible concentration. Evaluations show that such analysis takes no more than 30 min, including sample preparation; one mass-spectrometer can service 10–12 sampling points.
      PubDate: 2015-04-18
       
  • Neutron-Physical Calculations of a Nuclear Reactor: Computing Time
           Reduction by Digital Filtration
    • Abstract: An algorithm is proposed for performing neutron-physical calculations of a reactor using digital signal processing methods. It is shown that the algorithm’s combined use of the classical methods of numerical analysis and high-frequency digital filters makes it possible to calculate accurately and rapidly the neutron macrofield on a coarse grid and to organize the neutron-physical calculations in a new way, greatly reducing the number of iterations on a fine grid. Computer modeling shows that even for a one-dimensional reactor the proposed rational combination of the computational results on coarse and fine grids gives a several-fold reduction of the computing time.
      PubDate: 2015-04-18
       
  • Modernization of Diagnostics Methods for Local Boiling of Coolant in a
           VVER Core
    • Abstract: A method is proposed for modernizing the method currently used in power-generating units with VVER-1000 to perform diagnostics of the local boiling of the coolant in a reactor core. The method is based on analysis of the neutron flux noise recorded by neutron flux sensors. A new diagnostics parameter, related with the axial profile of the neutron flux beam at the level of the top sensors, is proposed. The results of an analysis of the efficacy of the modernized method are presented.
      PubDate: 2015-04-18
       
  • Improvement of the Thermohydraulic Operating Regimes of Deaerators in the
           Makeup and Boron Regulation System with Packed Columns
    • Abstract: One of the main pieces of equipment in the makeup and boron regulation system for the first loop of an NPP is the deaerator, whose functions is to degas the coolant removed from the first loop of a nuclear reactor in different operating regimes. Operating experience has shown that a deaerator design with packing columns does not give the requisite margin to flooding. Deaerator calculations suggesting further ways to solve the problem are presented.
      PubDate: 2015-04-18
       
  • Effect of the Degree of Perfection of Reactor Graphite on Performance
    • Abstract: Experimental data on the density changes occurring in graphite blocks of RBMK masonry in the course of operation of the reactor are presented. They show significant variance due to the nonuniformity of the radiation-induced change in the properties which is associated with the difference in the degree of perfection of the initial graphite. Experimental data on the dependence of the radiation-induced deformation at the shrinkage stage versus the size of the graphite crystallites are presented. An attempt is made to explain the mechanisms giving rise to this dependence. Experimental data showing that for temperature changes within certain limits from T1 to T2 the graphite transforms under irradiation into a state that would be observed under irradiation at T2 at the outset. A relation for determining the difference between the maximum depth of shrinkage of the graphite samples irradiated at temperatures T1 and T2 is proposed on the basis of an analysis of the experimental data.
      PubDate: 2015-04-18
       
  • Health Risk of Radon: Assessment Methods and Practical Applications
    • Abstract: Models of the dose–effect relation for the effect of radon on human health are analyzed. It is concluded that these models must be improved. A new and improved dose–effect relation is developed. An assessment of the health risk of radon, including an assessment of the radon exposure dose and a new dose–effect relation for risk assessment proper, is described. A method is proposed for use on the territory of our country. This method is used to calculate the risk for two hypothetical variants of the effect of radon on humans.
      PubDate: 2015-04-18
       
  • Libraries with Expanded Representation of Fission Product Yields for
           Calculations of the Nuclide Composition of Fuel in a Fast Spectrum
    • Abstract: The calculation of the spent-fuel composition is the baseline problem of the analysis of the nuclear and radiological safety of objects with spent fuel assemblies. The use of fission product libraries formed on the basis of evaluated nuclear data with an enlarged number of energy points is especially important for high-precision calculations of the nuclide composition of fuel irradiated in a fast spectrum. The results of an analysis of the nuclide composition of mixed oxide and uranium-plutonium-zirconium metal fuel with burnup ~10% h.a. in a fast spectrum, which were obtained in high-precision calculations based on data from different fission product yield libraries, are presented.
      PubDate: 2015-04-14
       
  • Reactor Reactivity Excess Optimization for Xenon Poisoning Compensation
           Taking Account of Force-Majeure Circumstances
    • Abstract: The energy-production losses versus the reserved reactivity excess as a function of the probability of accidental shutdown of the reactor are presented. A formulation of the optimization problem of power control during the period of threat under force-majeure circumstances is examined. The efficacy of optimization and the character of the optimal regimes as a function of the duration of the period of threat are presented.
      PubDate: 2015-04-11
       
  • Sputtering of Neutron-Generator Targets
    • PubDate: 2015-04-11
       
  • Status of and Prospects for Using Carbide Fuel
    • Abstract: Carbide nuclear fuel is most attractive for use in fast reactors. A general problem of hydrometallurgical reprocessing of spent carbide fuel is the formation of plutonium complexes with water-soluble organic compounds of an acidic nature, which are formed when such fuel dissolves in nitric acid. The drawbacks of the proposed methods of decomposing organic compounds include the possibility of secondary precipitation and reduction of the extractability of multivalent actinides, long-time limitations in choosing the structural materials of the equipment, and incomplete decomposition of organic compounds. Often, the solutions obtained are unsuitable for direct extractive reprocessing because of the need to remove corrosive reagents or their inorganic residues, which increases the volume of secondary wastes.
      PubDate: 2015-04-11
       
  • NG-14 Sealed-Tube High-Power Neutron Generator for Nuclear Technologies
    • PubDate: 2015-04-11
       
  • Release of Nitrogen Oxides into the Gas Phase Accompanying the Dissolution
           of Uranium Nitride in Nitric Acid
    • Abstract: The release of nitrogen oxides (N2O, NO, NO2) accompanying the dissolution of UN in HNO3 with concentration 3–16 mol/liter and the ratio S:L = 1:7.5 and in 7.2 mol/liter HNO3 with S:L varying from 3 to 30 in atmospheric air or argon is studied. In the indicated HNO3 concentration range N2O is formed mainly as a result of the oxidation of UN and secondarily as a result of the reduction of HNO3. The presence or absence of oxygen in the atmosphere has no effect on the amount of N2O formed. The formation of NO2 is due to the reduction of HNO3. The presence of oxygen increases the amount of NO2 formed as a result of the oxidation of NO. The amount of nitrogen monoxide NO released into atmospheric air is higher than the amount released into an argon atmosphere. The amount of NO formed increases with increasing nitric acid concentration. The release of nitrogen oxides from UN as well as from nitric acid results in considerable dilution of nitride nitrogen, which casts doubt on the possibility of recycling 15N in the case where U15N is used as fuel.
      PubDate: 2015-04-11
       
  • Obtaining a Diluent for High-Enrichment Uranium in a Double Cascade
    • Abstract: A scheme for producing a diluent for high-enrichment uranium in a double cascade is examined. The marketable product, viz., low-enrichment uranium, is obtained in the product flow of the first cascade; the diluent is obtained in the product flow of the second cascade from the waste flow of the first cascade. To reduce the cost of the separative work performed on the production of all products it is proposed that the feed point for the first cascade be displaced in the direction of the product flow relative to the optimum, calculated from the condition of optimization of the cascade for the production of 235U. A computational experiment shows this scheme to be efficient and the particularities associated with the use of natural uranium and depleted wastes as initial materials.
      PubDate: 2015-04-11
       
  • Effect of γ-Radiation on the Crystal Structure of Cubic Titanium
           Carbohydride TiC x H y
    • PubDate: 2015-04-11
       
 
 
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