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  Subjects -> ENERGY (Total: 293 journals)
    - ENERGY (180 journals)
    - ENERGY: GENERAL (8 journals)
    - NUCLEAR ENERGY (26 journals)
    - PETROLEUM AND GAS (52 journals)
    - RENEWABLE ENERGY (27 journals)

ENERGY (180 journals)                  1 2 | Last

Advances in Building Energy Research     Hybrid Journal   (Followers: 14)
Advances in Energy and Power     Open Access   (Followers: 4)
Advances in High Energy Physics     Open Access   (Followers: 14)
Advances in Natural Sciences: Nanoscience and Nanotechnology     Open Access   (Followers: 17)
AIMS Energy     Open Access  
American Journal of Energy Research     Open Access   (Followers: 8)
Annals of Nuclear Energy     Hybrid Journal   (Followers: 8)
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: 8)
Applied Solar Energy     Hybrid Journal   (Followers: 13)
Archives of Thermodynamics     Open Access   (Followers: 6)
Artificial Photosynthesis     Open Access  
Atomic Energy     Hybrid Journal   (Followers: 5)
Atoms for Peace: an International Journal     Hybrid Journal   (Followers: 3)
Batteries     Open Access   (Followers: 1)
Biofuel Research Journal     Open Access   (Followers: 3)
Biofuels     Hybrid Journal   (Followers: 11)
Biomass Conversion and Biorefinery     Partially Free   (Followers: 7)
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: 8)
Catalysis for Sustainable Energy     Open Access   (Followers: 4)
CERN courier. International journal of high energy physics     Free   (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: 3)
Dams and Reservoirs     Hybrid Journal   (Followers: 4)
Development of Energy Science     Open Access   (Followers: 5)
Distributed Generation & Alternative Energy Journal     Hybrid Journal   (Followers: 3)
E3S Web of Conferences     Open Access  
Economics and Policy of Energy and the Environment     Full-text available via subscription   (Followers: 5)
Electrical and Power Engineering Frontier     Open Access   (Followers: 11)
Energy     Partially Free   (Followers: 27)
Energy & Fuels     Full-text available via subscription   (Followers: 26)
Energy and Buildings     Hybrid Journal   (Followers: 10)
Energy and Emission Control Technologies     Open Access   (Followers: 2)
Energy and Environment Focus     Free   (Followers: 1)
Energy and Environment Research     Open Access   (Followers: 12)
Energy and Environmental Engineering     Open Access   (Followers: 2)
Energy and Power     Open Access   (Followers: 4)
Energy and Power Engineering     Open Access   (Followers: 11)
Energy Conversion and Management     Hybrid Journal   (Followers: 11)
Energy Efficiency     Hybrid Journal   (Followers: 14)
Energy Harvesting and Systems : Materials, Mechanisms, Circuits and Storage     Hybrid Journal   (Followers: 3)
Energy Journal The     Full-text available via subscription   (Followers: 2)
Energy Law Journal     Full-text available via subscription   (Followers: 3)
Energy Materials : Materials Science and Engineering for Energy Systems     Hybrid Journal   (Followers: 17)
Energy Policy     Partially Free   (Followers: 49)
Energy Prices and Taxes     Full-text available via subscription   (Followers: 6)
Energy Procedia     Open Access   (Followers: 4)
Energy Reports     Open Access   (Followers: 2)
Energy Research & Social Science     Full-text available via subscription   (Followers: 2)
Energy Science & Engineering     Open Access   (Followers: 5)
Energy Science and Technology     Open Access   (Followers: 13)
Energy Strategy Reviews     Partially Free   (Followers: 8)
Energy Studies Review     Open Access   (Followers: 5)
Energy Systems     Hybrid Journal   (Followers: 12)
Energy Technology     Partially Free   (Followers: 4)
Energy Technology & Policy     Open Access   (Followers: 1)
Energy, Sustainability and Society     Open Access   (Followers: 19)
Environmental Progress & Sustainable Energy     Hybrid Journal   (Followers: 6)
EPJ Photovoltaics     Open Access   (Followers: 2)
Facta Universitatis, Series : Electronics and Energetics     Open Access  
Frontiers in Energy     Hybrid Journal   (Followers: 4)
Frontiers in Energy Research     Open Access   (Followers: 2)
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     Hybrid Journal   (Followers: 2)
IEA Electricity Information     Full-text available via subscription   (Followers: 6)
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: 12)
IET Power Electronics     Hybrid Journal   (Followers: 14)
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: 1)
International Journal of Applied Power Engineering     Open Access   (Followers: 2)
International Journal of Clean Coal and Energy     Open Access   (Followers: 6)
International Journal of Coal Science & Technology     Open Access   (Followers: 2)
International Journal of Critical Infrastructure Protection     Hybrid Journal   (Followers: 6)
International Journal of Electric and Hybrid Vehicles     Hybrid Journal   (Followers: 7)
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: 11)
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: 4)
International Journal of Global Energy Issues     Hybrid Journal   (Followers: 7)
International Journal of Green Energy     Hybrid Journal   (Followers: 7)

        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  [2276 journals]
  • Effect of Atomic-Molecular and Isotopic Composition of an Ion Beam on the
           Neutron Yield from Tamped Targets in Sealed Tubes
    • Abstract: A neutron generator with a sealed tube is a controlled electrophysical source of fast neutrons which is safe in the off state. A tritium- and deuterium-saturated target is bombarded by a beam of deuterium and tritium ions in order to obtain neutrons. The neutrons are formed in the reactions 3H(d, n)4He and 2H(d, n)3He. Generators are used in nuclear geophysics, inspection systems for detecting dangerous substances, thermonuclear research, and other fields of industry and science. A method is presented for calculating the neutron yield from the targets in sealed tubes in generators, taking account of the accelerating voltage, the atomic-molecular and isotopic composition of the ion beam, and the properties of the target. The computational method presented makes it possible to obtain the dependences of the neutron yield on the operating parameters of gas-filled sealed tubes. The expressions obtained can be used for almost all solid-state targets currently used in generators.
      PubDate: 2015-10-20
  • Sodium Fires and Fast Reactor Safety
    • Abstract: Fifteen experiments with instantaneous opening of apertures of different size from pipes without thermal insulation and nine experiments with instantaneous opening of apertures beneath thermal insulation are analyzed. Analysis shows that in the first case droplet burning of sodium is due to dispersion of sodium, which results in rapid growth of the air pressure in a box up to an inadmissible level. In the second case (with a leak beneath the thermal insulation) the sodium flows out of the insulated volume without being dispersed and burns up on the floor of the box, which does not give rise to pressure growth in the box. This comports with an analysis given here of 60 years of experience with leaks in sodium systems.
      PubDate: 2015-10-15
  • Dismantling of MR-Reactor IN-Vessel Setups
    • Abstract: The results of dismantling performed on the in-vessel structures of the MR research reactor at National Research Center Kurchatov Institute are presented. Remote-controlled mechanisms and remote methods of diagnostics of the radiation conditions were used to perform the operations. These methods and technologies made it possible to provide radiation protection for the staff performing radiation-hazardous work and meet the dose-load requirements established in the regulatory documents. The results of dose-rate measurements in the work zones and the irradiation doses to personnel performing this type of work are presented.
      PubDate: 2015-10-15
  • GEFEST800 Software System for On-Line Calculations of BN-800
           Neutron-Physical Characteristics in a Nonstationary Regime
    • Abstract: The GEFEST800 software system developed for performing on-line calculations of the BN-800 reactor contains moduli for performing nonstationary neutron-physical calculations of a reactor, calculations of feedbacks via calculations of the temperature, burnup, residual heat release, evaluations of the activity of spent fuel assemblies, and so forth. The error of most computational parameters is determined. Moreover, the software can process experimental data while nonstationary processes are calculated and the energy releases of fuel assemblies measured. The GEFEST800 software-hardware system is implemented in the Winmod system shell, which makes it convenient for the user to organize pre- and post-processing as well as to perform analysis and enter corrections directly in the course of the computational process itself. The system shell makes it possible to analyze, via the windows construction procedure, the quality of a solution and perform calculations using a different module in a definite window space in order to compare the results of solutions performed by different methods at the indicated problem location.
      PubDate: 2015-10-15
  • Sensitivity of Optimal Design Problem Solutions for Nuclear Reactors to a
           Change in the Input Parameters
    • Abstract: Methods for analyzing the sensitivity of the optimal values of target functionals and controlling parameters to small changes in the initial data in optimization problems for nuclear reactors are examined. The computational aspects and particularities of the methods are discussed. As an example the sensitivity of the solution to the problem of minimizing the specific mass of nuclear fuel present in the fuel cycle of a gas-cooled fast reactor to a change in the coolant density is investigated.
      PubDate: 2015-10-15
  • Potential Problems of MBIR in Validating New-Generation Nuclear Power
           Facilities and its Experimental Possibilities
    • Abstract: Potential problems of the MBIR multipurpose, research, fast reactor, currently under construction, in the validation of new nuclear-power projects with fast reactors and a closed nuclear fuel cycle are discussed. The basic characteristics and experimental possibilities of the reactor are described. Considerable attention is given to the primary directions of research on nuclear safety, reactor and structural materials science, and NFC closure. Proposals for the development of an MBIR-based international research center are given.
      PubDate: 2015-10-15
  • Digital Technology in Nondestructive Monitoring of Nuclear Materials
    • Abstract: The use of scintillation detectors in combination with digital technology for obtaining separate responses of neutrons and photons in the field of mixed radioactive radiation is examined. An experimental arrangement and algorithms of a program for separating neutron and photon responses, according to their form, and a program for calculating the rates of real coincidences of different multiplicity are presented. Data on measurements of the differential rates of real coincidences of neutrons and photons in the field of a californium source are presented.
      PubDate: 2015-10-15
  • Reflood Investigation of Fuel Assemblies Based on Analysis of
           High-Temperature Integral Experiments
    • Abstract: A series of high-temperature experiments with an electrically heated fuel assembly in a steam–argon mixture followed by rapid cooling of the assembly with water or saturated steam is analyzed. The possibility of efficiently cooling a water-heated and water-moderated reactor core, heated to high temperature during a serious accident, by flooding the core with water from the bottom is studied. The oxidation of fuel-element cladding, hydrogen release upon heating and reflooding and heat-transfer processes, characteristic for a serious accident in a reactor and determining the effectiveness of flooding as a measure to control the accident, are analyzed in detail for a single experiment. The analysis is performed using the SOKRAT/V2 software code developed for modeling measures taken to control serious accidents in VVER. Analysis of experiments shows that reflooding the core, heated in a steam medium to temperature not exceeding 2100–2200 K, can be an effective measure to stop catastrophic development of a serious accident at NPP with VVER.
      PubDate: 2015-10-15
  • Possibilities of Transmission Radiation Tomography and Tomography Based on
           Backscattered Radiation
    • PubDate: 2015-10-15
  • Modeling Transport of Radioactive Products of Corrosion in Loops with
           Sodium Coolant
    • Abstract: A phenomenological model is proposed for finding the relationship between the observed behavior of corrosion radionuclides in liquid sodium and the experimental conditions. Reactor and extra-reactor experimental data are used to find the temperature and rate dependences of the model parameters so that the model reflects a wide range of experimental conditions. Most of the experimental data were obtained using domestic fast reactors and, to a lesser extent, foreign reactors. The design code Al’fa-M, which is based on the proposed model, is described. The code was tested on the BN-600 reactor. It was shown that the proposed modeling approach makes it possible to solve the problem of calculating the removal from the core and the distribution in the tank of a power reactor of activated products of corrosion with satisfactory accuracy within the framework of the problem at hand. In addition, discrepancies between the calculations and experiments, requiring further improvements to the model are found.
      PubDate: 2015-10-15
  • NG-24 Neutron Generator for Nuclear Medicine and Thermonuclear Research
    • PubDate: 2015-10-15
  • Nonmonotonic Embrittlement of Vessel Steel
    • Abstract: The possible reasons for the significant variance of the experimental data in the investigation of the influence of neutron irradiation on the properties of the vessel materials of nuclear reactors are analyzed. It is shown on the basis of our own experimental data and an analysis of foreign experimental data that the dependence of the degree of radiation embrittlement on the neutron fluence can be nonstandard (nonmonotonic). It is noted that the conventionally studied parameters, viz. the intensity of irradiation and the technological factor, can play only a secondary role when nonmonotonicity is taken into account. It is supposed that the defect structure resulting from neutron bombardment undergoes transformation once or periodically in the direction of loss or restoration of the initial properties. The defective material can be restored, specifically, at low dose of irradiation by corpuscular particles, i.e., at some point the degradation by irradiation in a certain dose range even acts as a healing factor.
      PubDate: 2015-10-15
  • Generalized Approach to Comparative Assessment of the Effect of Radiation
           from Nuclear Fuel Cycles on Biota
    • Abstract: An approach to evaluating a generalized index of the radiation effect of NFC objects on biota is proposed. The effect of the radiation factor on the collection of representative natural organisms belonging to difference taxonomic groups is taken into account. The change in the proposed index for individual actinides flowing with activity 1 MBq into the environment and their decay products is calculated. The actinides present in spent fuel are considered in the calculations: 241,242m,242,243Am, 242–248Cm, 237Np, 238–242,244Pu, and 235,236,238U. The index developed is suitable for radioecological assessment of the objects of open and closed fuel cycles. The results of such assessment are an important element of the environmental validation of new nuclear power technologies.
      PubDate: 2015-10-12
  • Results of Investigations of BN-600 Fuel Elements Irradiated in a Type-1
    • Abstract: The results of materials science studies of spent BN-600 fuel assemblies from a core with a type-1 load are presented. The fuel assemblies studied had depressurized and damaged fuel elements. It was determined that most of the fuel elements failed because of the thermomechanical fuel–cladding interaction under conditions where the cladding was subjected to increased corrosion damage, which was caused by fuel assemblies being rearranged in a direction toward core center and simultaneously turning by 180°.
      PubDate: 2015-10-12
  • Selecting Concrete for Radiation Protection for New-Generation NPP
    • Abstract: Computational studies of the activation of a radiological protection structure made with widely used compositions of concrete are presented. The calculations were performed for a one-dimensional reactor–radiological-thermal and biological protection geometry typical for NPP with VVER. The investigations showed that the induced activity and therefore the volume of radioactive wastes can be reduced by picking a low-activation composition for the protective concrete used for the shaft of a VVER reactor.
      PubDate: 2015-10-12
  • GEFEST800 Software Complex for Performing Real-Time Neutron-Physical
           Calculations of the BN-800 Reactor in a Stationary Regime
    • Abstract: The GEFEST800 software-hardware system was developed for performing real-time neutron-physical calculations of the BN-800 sodium-cooled fast reactor, viz. calculations of the effective breeding ratio, maximum reactivity excess, efficiency of single and groups of control rods, total, specific, and linear density of power release in fuel assemblies, coefficients of nonuniformity of energy release in fuel assemblies and the reactor, damaging dose of irradiation of fuel assemblies, fuel burnup, reactivity coefficients (temperature, power, density) and void effect of reactivity, effective delayed-neutron fraction, characteristics of transient processes for normal operating regimes, residual energy release, activity of spent fuel assemblies, and others. The software-hardware system provides for calculations of normal operating regimes (stationary and nonstationary regimes at the lowest controllable power level and at power while controlling transient processes with rods, fuel burnup).
      PubDate: 2015-10-12
  • Production of Radionuclides for Cyclotron Positron-Emission Tomography
    • Abstract: The characteristics of 7.5–80 MeV proton cyclotrons for the production of short-lived and generator radionuclides for positron-emission tomography are presented. A classification of cyclotrons by proton energy is given. Recommendations are made for choosing compact 7.5–12 MeV cyclotrons for producing short-lived 18F, 15O, 13N, and 11C and cyclotrons with proton energy tens of MeV for producing the generators 68Ge/68Ga and 82Sr/82Rb.
      PubDate: 2015-10-12
  • A Step in the Verification of the Hydra-Ibrae/LM/V1 Thermohydraulic Code
           for Calculating Sodium Coolant Flow in Fuel-Rod Assemblies
    • Abstract: The basic relations used in the HYDRA-IBRAE/LM/V1 code for calculating the flow and heat-exchange of sodium coolant in fuel-rod assemblies in regimes with and without boiling and in the presence of a crisis of heat exchange are presented. The experimental data suitable for verifying the thermohydraulic code for calculating friction in one- and two-phase regimes as well as heat exchange in regimes with and without boiling are picked on the basis of a review of the literature. The computational error of different parameters is obtained on the basis of the verification results. It is shown that the thermohydraulic code HYDRA-IBRAE/LV/V1 can be used to calculate correctly the primary processes in design basis and beyond-design basis accidents in sodium-cooled reactor facilities.
      PubDate: 2015-10-12
  • Monitoring of 214 Pb AND 214 Bi Activity with the Askro Spectrometric
    • Abstract: The possibility of using the ASKRO spectrometric channel for monitoring the volumetric activity of the products of decay of radon 214Pb and 214Bi in the atmospheric boundary layer during precipitation is examined. The sensitivity of the spectrometer with respect to 214Pb and 214Bi in a measurement geometry determined using as the standard 1 mg 226Ra was equal to 0.015 ± 0.005 and 0.018 ± 0.006 m3/(Bq·sec), respectively, for confidence probability P = 0.95. According to the spectrometric measurements the total washout coefficient for 214Pb and 214Bi from clouds was equal to (1.1–5)·105. The role of radon and its decay products in the formation of rain drops is found to be very small.
      PubDate: 2015-10-12
  • Particularities of Vanadium Microstructure Development During Irradiation
           by 7.5 MeV Ni 2+ Ions at 650°C
    • Abstract: The results of an investigation of vacancy porosity and swelling development in the vanadium low-alloy V–0.3%Ti irradiated with 7.5 MeV Ni2+ ions at 650°C to damaging dose 100 dpa and with 40 keV He+ ions to fluence 5·1020 m−2 at 650°C and additionally with Ni2+ ions are presented. It is shown that at the maximum damage depth ~1.75 μm under irradiation with nickel ions the swelling equals 0.5%, which corresponds to the existing data and attests to the desirability of using the EPG-15 accelerator in simulation studies of the relative radiation resistance of the structural reactor materials at their pre-selection stage. Under irradiation of a sample in the sequence He+ + Ni2+ gas-filled pores form at depth considerably greater than the free-path of helium ions and swelling increases to 1.2% in the zone of maximum structural damage. Once the solubility limit is reached in vanadium the implanted nickel ions form 5–20 nm clusters.
      PubDate: 2015-10-12
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