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  Subjects -> ENERGY (Total: 273 journals)
    - ENERGY (183 journals)
    - ENERGY: GENERAL (8 journals)
    - NUCLEAR ENERGY (23 journals)
    - PETROLEUM AND GAS (49 journals)
    - WIND ENERGY (10 journals)

ENERGY (183 journals)                  1 2 | Last

Advances in Building Energy Research     Hybrid Journal   (Followers: 11)
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: 3)
Biofuels     Hybrid Journal   (Followers: 8)
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: 9)
Energy     Partially Free   (Followers: 26)
Energy & Fuels     Full-text available via subscription   (Followers: 25)
Energy and Buildings     Hybrid Journal   (Followers: 7)
Energy and Environment Focus     Free  
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: 10)
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 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 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: 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: 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: 5)
International Journal of Electric and Hybrid Vehicles     Hybrid Journal   (Followers: 5)
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 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: 2)
International Journal of Global Energy Issues     Hybrid Journal   (Followers: 6)
International Journal of Green Energy     Hybrid Journal   (Followers: 6)
International Journal of Hydrogen Energy     Partially Free   (Followers: 13)
International Journal of Marine Energy     Full-text available via subscription   (Followers: 2)

        1 2 | Last

Journal Cover   Atomic Energy
  [SJR: 0.199]   [H-I: 9]   [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  [2302 journals]
  • 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
       
  • Salt-Free Reprocessing of Spent Carbide Fuel for the Example of AM-Reactor
           Fuel
    • Abstract: The dissolution and extractive reprocessing operations for AM-reactor spent fuel based on uranium carbide in a mixture with AM uranium-molybdenum fuel (9% molybdenum) and in combination with VVER-440 are studied and checked on model and real solutions. An approach combining catalytic oxidation of water-soluble organic compounds by nitric acid with their recomplexing by zirconium and/or molybdenum is proposed. The reprocessing of damaged AMB fuel and the possibility of reprocessing mixed uranium-plutonium fuel for fast reactors using autoclave oxidation instead of additional recomplexing are examined.
      PubDate: 2015-04-11
       
  • Supercomputer Mathematical Modeling of the Fluid Dynamics in Elements of
           Nuclear Power Facilities
    • Abstract: A three-dimensional CFD code CONV-3D is being developed for mathematical modeling of the fluid dynamics of elements of nuclear power facilities. The code is based on developed algorithms with low artificial diffusion, for which discrete approximations are constructed using finite-volume and staggered grid methods. A regularized nonlinear monotonic operator splitting scheme has been developed to solve advection problems. Richardson’s iteration method with a fast Fourier transform for the Laplace operator is used to solve the pressure equation. Compared with the conventional conjugate gradient method this approach to the solution of elliptic equations with variable coefficients gives multiple acceleration. Quasi-direct numerical modeling is used to model three-dimensional turbulent flows in single-phase streams. The CONV-3D code is completely parallelized and is effective on multiprocessor cluster computers, such as Chebyshev and Lomonosov (MGU).
      PubDate: 2015-04-11
       
  • 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
       
  • Technology for Obtaining Natural-Uranium Concentrates to ASTM C
           967–08 Specifications
    • Abstract: The process of separating high-purity chemical concentrates of uranium, which are an intermediate product in the general scheme of obtaining materials of the nuclear industry, is studied and the parameters of the sorption-desorption concentration of uranium using different regenerating solutions are determined. Variants and combinations of the processes of selective separation of chemical concentrates in the form of ammonium and sodium polyuranates and uranium peroxide from commercial desorbates and re-extracts in application to the reprocessing of raw materials from the Elkonskoe and Streltsovskoe deposits are proposed. It is shown that chemical concentrates of uranium meeting the ASTM C 967-08 standard specifications can be obtained. The results presented can be used to improve the technological schemes of uranium extraction during the reprocessing of ores and concentrates with the final product meeting all applicable regulatory requirements.
      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
       
  • Neutron Yield of the Reaction (α, n ) on Thick Targets Comprised of
           Light Elements
    • Abstract: Accurate data on the neutron yield from the interaction of α-particles with the nuclei of light elements ranging from lithium to potassium are required for solving the problems of nuclear power technologies: development of analytical means for controlling the technological processes of fabricating and reprocessing nuclear fuel, securing radiological protection for workers, improving the systems for managing and monitoring nuclear materials and radioactive wastes, measuring the burnup fraction of spent nuclear fuel, and others. The uncertainty of this information must be <10% for energies ranging from 4 to 9 MeV of α-particles emitted by naturally occurring and artificial radionuclides. The computational uncertainty of the neutron yield can be reduced on the basis of a combined analysis of (α, n) reactions, measured on α-particle accelerators with tunable energy and on compounds of actinides with light elements, using reliable data on the stopping power of α-particles for elements from hydrogen to californium. The results of such an analysis based on experimental and evaluated data for the light isotopes 6Li, 7Li, 9Be, 10B, 11B, 13C, 14N, 17O, 18O, 21Ne, 22Ne, 19F, 23Na, 25Mg, 26Mg, 27Al, 29Si, 30Si, 31P, 33S, 34S, 35Cl, 37Cl, and 41K in the α-particle energy range from 4 to 9 MeV are presented.
      PubDate: 2015-02-18
       
  • Modeling of Cesium and Iodine Transport in the FAL-ISP 1 Experiment
    • PubDate: 2015-02-17
       
  • Comparison of Methods of Enriching Intermediate Components in Cascades
           with the Same Number of Separative Elements
    • Abstract: A method is proposed for concentrating in different output flows in a square cascade with two additional extractions the components of the multicomponent isotopic mixture being separated. The parameters of the proposed cascade, a square cascade with additional extraction, and a cascade with flow expansion at internal steps on condition that the number of separative elements in them is the same are compared for the separation of a mixture of tungsten isotopes. It is shown that the proposed cascade expands the possibilities of previously known methods of concentrating intermediate-mass isotopes, since several target products can be obtained at the same time in the output flows.
      PubDate: 2015-02-15
       
  • Calculation of the Covariation Matrix of the Neutron Flux Density in the
           Multigroup Diffusion Model of a Subcritical Reactor
    • Abstract: The reconstruction of fields and adjustment of the parameters of reactor models are increasingly prioritized for reactor physics because the efficiency and safety of the control of a nuclear plant depend on solving them. The results of reconstruction and parameter adjustments are largely determined by the probability distributions of the computed and measured data. The probability distribution of the computed data in turn depends on the properties of the neutron-physical model and probabilistic characteristics of the parameters of this model. The present work is devoted to the search for and investigations of efficient algorithms for calculating the covariation functions of the neutron flux density. A model of a stationary subcritical reactor with an internal neutron source is studied. Linear perturbation theory, the theorem on the spectral decomposition of operators, and the theory of stochastic processes are the tools used for performing the analysis.
      PubDate: 2015-02-15
       
  • Metallic Uranium: Protective Material with Enhanced γ-Ray Absorption
    • Abstract: Research performed at the Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM) and the All-Russia Research Institute of Experimental Physics (VNIIEF) on the development of the TUK-117 multipurpose transport packaging is presented. The TUK-117 packaging possesses biological protection based on depleted uranium and intended for transporting and storing spent nuclear fuel. The higher capacity of the metallic uranium alloy for absorbing of γ-rays and the alloy’s high mechanical characteristics have made it possible to develop a design meeting IAEA specifications. The technology for fabricating safety-engineered articles from uranium and its alloys by pouring the alloy into a prepared mold made of corrosion-resistant steel is patented.
      PubDate: 2015-02-15
       
  • Reactimeter of the IBR-2M Periodic Pulse Reactor
    • Abstract: A reactimeter was developed for the IBR-2 periodic-pulse reactor. The reactor kinetics was described by difference equations, which relate the reactor’s parameters, corresponding to the instantaneous and preceding power pulses, and the nonlinear dependences of the energy of the power pulse and its amplitude on the reactivity. The fact that the regulated parameter of the reactor is the relative deviation of the amplitude of the power pulse from its base (prescribed average) value was taken into account. In studying transient processes, a statistically optimal filter was used to suppress the reactivity noise due to the reactor’s construction and principle of operation. The best location for inserting the filter in the block diagram of the reactimeter was chosen and the optimal smoothing coefficient determined.
      PubDate: 2015-02-15
       
  • High-Temperature Electric and Thermal Conductivity of the Aluminum Alloys
           SAV-1 and AMG-2
    • Abstract: The electric and thermal conductivity of the aluminum alloys AMG-2 and SAV-1, which are used to fabricate the fuel elements of the fuel assemblies of a nuclear reactor, was investigated in the range 290–490 K. The Debye temperature was calculated and the contribution of the electronic and lattice components to the thermal conductivity of the alloys was determined. It is shown on the basis of an analysis of the mechanisms of electron and phonon scattering and the experimental data that one possible reason for the observed changes of the thermal conductivity in aluminum alloys are the scattering of electrons by phonons and the deviation of the Lorenz number from the theoretical values as a result of inelastic scattering of the electrons.
      PubDate: 2015-02-15
       
  • Modeling of Proton Beam Dynamics in an Accelerator-Driver at
           600–1000 MeV and Investigation of the Electrodynamic Characteristics
           of Accelerating Cavities
    • Abstract: The results of an investigation of the beam dynamics in a high-power proton accelerator-driver intended for operation as part of a subcritical electronuclear facility are presented. The initial normally conducting part of the accelerator at current 10 mA with current-passage ratio >95% has been developed. A channel with current-passage ratio 100% has been developed for the superconducting part of the accelerator. Modeling of the accelerating cavities for all velocity ranges has been done. High electrodynamic performance has been attained as a result of optimization.
      PubDate: 2015-02-15
       
  • Heat-Exchange Models in the SOKRAT-BN Code for Calculating Sodium Boiling
           in Geometrically Different Channels
    • Abstract: Heat-exchanger models in the SOKRAT-BN code which are used to calculate problems with boiling sodium in channels with different geometry are presented. The results of modeling of different experiments on boiling of liquid-metal coolant are presented. Good agreement is obtained between the SOKRAT-BN calculations and experiments performed with stationary and nonstationary boiling of sodium. It is shown that the thermohydraulic processes occurring in reactor facilities during design-basis and beyond design basis accidents can be calculated correctly using the thermohydraulic module of the SOKRAT-BN computer code.
      PubDate: 2015-02-15
       
 
 
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