for Journals by Title or ISSN
for Articles by Keywords
help
  Subjects -> ENERGY (Total: 247 journals)
    - ENERGY (162 journals)
    - ENERGY: GENERAL (8 journals)
    - NUCLEAR ENERGY (22 journals)
    - PETROLEUM AND GAS (47 journals)
    - WIND ENERGY (8 journals)

ENERGY (162 journals)                  1 2 | Last

Advances in Building Energy Research     Hybrid Journal   (Followers: 11)
Advances in High Energy Physics     Open Access   (Followers: 12)
Advances in Natural Sciences: Nanoscience and Nanotechnology     Open Access   (Followers: 14)
American Journal of Energy Research     Open Access   (Followers: 5)
Annals of Nuclear Energy     Hybrid Journal   (Followers: 7)
Annual Reports on NMR Spectroscopy     Full-text available via subscription   (Followers: 1)
Annual Review of Resource Economics     Full-text available via subscription   (Followers: 10)
Applied Nanoscience     Open Access   (Followers: 8)
Applied Solar Energy     Hybrid Journal   (Followers: 10)
Archives of Thermodynamics     Open Access   (Followers: 4)
Atomic Energy     Hybrid Journal   (Followers: 5)
Atoms for Peace: an International Journal     Hybrid Journal   (Followers: 3)
Biofuels     Hybrid Journal   (Followers: 7)
Biomass Conversion and Biorefinery     Partially Free   (Followers: 5)
Bulletin de droit nucleaire     Full-text available via subscription   (Followers: 1)
Canadian Journal of Remote Sensing     Full-text available via subscription   (Followers: 13)
Canadian Water Resources Journal     Hybrid Journal   (Followers: 20)
Carbon Management     Hybrid Journal   (Followers: 5)
Catalysis for Sustainable Energy     Open Access   (Followers: 2)
Chain Reaction     Full-text available via subscription  
Clefs CEA     Full-text available via subscription   (Followers: 1)
Computational Water, Energy, and Environmental Engineering     Open Access   (Followers: 2)
Continental Journal of Renewable Energy     Open Access   (Followers: 9)
Current Sustainable/Renewable Energy Reports     Hybrid Journal   (Followers: 2)
Dams and Reservoirs     Hybrid Journal   (Followers: 3)
Development of Energy Science     Open Access   (Followers: 2)
Distributed Generation & Alternative Energy Journal     Hybrid Journal   (Followers: 1)
E3S Web of Conferences     Open Access  
Economics and Policy of Energy and the Environment     Full-text available via subscription   (Followers: 1)
Electrical and Power Engineering Frontier     Open Access   (Followers: 7)
Electronic Journal of Energy & Environment     Open Access   (Followers: 9)
Energy     Partially Free   (Followers: 22)
Energy & Fuels     Full-text available via subscription   (Followers: 23)
Energy and Buildings     Hybrid Journal   (Followers: 7)
Energy and Environment Research     Open Access   (Followers: 8)
Energy and Power Engineering     Open Access   (Followers: 8)
Energy Conversion and Management     Hybrid Journal   (Followers: 7)
Energy Efficiency     Hybrid Journal   (Followers: 11)
Energy Policy     Partially Free   (Followers: 38)
Energy Prices and Taxes     Full-text available via subscription   (Followers: 5)
Energy Procedia     Open Access   (Followers: 2)
Energy Science & Engineering     Open Access   (Followers: 3)
Energy Science and Technology     Open Access   (Followers: 10)
Energy Strategy Reviews     Partially Free   (Followers: 5)
Energy Studies Review     Open Access   (Followers: 3)
Energy Systems     Hybrid Journal   (Followers: 9)
Energy Technology     Partially Free   (Followers: 3)
Energy, Sustainability and Society     Open Access   (Followers: 16)
Environmental Progress & Sustainable Energy     Hybrid Journal   (Followers: 4)
EPJ Photovoltaics     Open Access  
Frontiers in Energy     Hybrid Journal   (Followers: 3)
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: 9)
IEEE Transactions on Energy Conversion     Hybrid Journal   (Followers: 6)
IEEE Transactions on Nuclear Science     Hybrid Journal   (Followers: 7)
IEEE Transactions on Power Systems     Hybrid Journal   (Followers: 9)
IET Power Electronics     Hybrid Journal   (Followers: 7)
IngenierĂ­a EnergĂ©tica     Open Access  
Innovations : Technology, Governance, Globalization     Hybrid Journal   (Followers: 6)
International Journal of Alternative Propulsion     Hybrid Journal   (Followers: 1)
International Journal of Ambient Energy     Hybrid Journal   (Followers: 2)
International Journal of Applied Power Engineering     Open Access   (Followers: 1)
International Journal of Clean Coal and Energy     Open Access   (Followers: 4)
International Journal of Critical Infrastructure Protection     Hybrid Journal   (Followers: 5)
International Journal of Electric and Hybrid Vehicles     Hybrid Journal   (Followers: 3)
International Journal of Emerging Electric Power Systems     Full-text available via subscription   (Followers: 4)
International Journal of Emerging Multidisciplinary Fluid Sciences     Full-text available via subscription  
International Journal of Energy and Environmental Engineering     Open Access   (Followers: 2)
International Journal of Energy and Power     Open Access   (Followers: 5)
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)
International Journal of Regulation and Governance     Hybrid Journal   (Followers: 2)
International Journal of Sustainable Energy     Hybrid Journal   (Followers: 9)
International Journal of Sustainable Energy Planning and Management     Open Access  
International Journal of Sustainable Engineering     Hybrid Journal   (Followers: 7)
International Journal of Thermodynamics     Open Access   (Followers: 1)
ISRN Power Engineering     Open Access   (Followers: 1)
ISRN Renewable Energy     Open Access  
Journal of Alternate Energy Sources & Technologies     Full-text available via subscription   (Followers: 1)
Journal of Building Performance Simulation     Hybrid Journal   (Followers: 3)

        1 2 | Last

Journal Cover Atomic Energy
   Journal TOC RSS feeds Export to Zotero [7 followers]  Follow    
   Hybrid Journal Hybrid journal (It can contain Open Access articles)
     ISSN (Print) 1573-8205 - ISSN (Online) 1063-4258
     Published by Springer-Verlag Homepage  [2210 journals]   [SJR: 0.136]   [H-I: 8]
  • Analysis and Prediction of the Physico-Mechanical Properties of Reactor
           Steel by Means of Artificial Intelligence and Applied Statistics
    • PubDate: 2014-09-13
       
  • Evaluation of the Reduction in the Separative Power of the Steps in a
           Cascade of gas Centrifuges
    • Abstract: The particularities of the reduction in the separative power of centrifuges in time owing to the appearance of defects and changes in the state parameters are examined. A method of evaluating the losses of separative power of the steps in a cascade by measuring the parameters of the centrifuges, described by a continuous distribution, is developed. The basic models of the change in the distributions are determined on the basis of Markov diffusion processes. Examples of the evaluation of the losses of separative power are presented for typical distributions of the correlating parameters.
      PubDate: 2014-09-11
       
  • New Technologies and Equipment for Water Treatment Facilities at NPP
    • Abstract: The need to use new water treatment technology is substantiated and the principle of operation and design of membrane technologies for demineralization of natural water are described. The possibilities of membrane technologies for use in water treatment facilities at NPP are examined. It is shown that the use of reverse-osmosis technology for demineralization of water decreases many-fold the need for chemical reagents and the salinity of discharges. There is less need for production enclosures and the deliverable readiness of equipment is higher. The ion-exchange and reverse-osmosis water demineralization technologies are compared on the basis of the quality of the filtrate, salt discharges and degree of deliverable readiness of the process equipment.
      PubDate: 2014-09-11
       
  • Comparison of the Circulation Efficiency in gas Centrifuges with Different
           Geometric and Speed Characteristics for Uranium Enrichment
    • Abstract: The circulation efficiency of gas centrifuges for uranium enrichment is compared for domestically produced gas centrifuges, the TC-12 and TC-21 models from the European concern Urenco, the American AC-100 model, and the Iguasu model centrifuge in order to search for general physical mechanisms. It is found that for the domestic centrifuges the optimal gas pressure P a near the wall of the rotor is a linear function of the optimal temperature difference ΔT along the rotor. It is shown that the degree of optimality of the circulation flow in a gas centrifuge ha a maximum as a function of the dimensionless rotational speed of the rotor, which is associated with the difficulties of organizing the optimal circulation flow in a thin layer of viscous gas at the rotor wall at high rotational speeds.
      PubDate: 2014-09-11
       
  • Change in the Properties of Structural Materials Under Irradiation: Role
           of Radiation-Induced Segregation
    • PubDate: 2014-09-10
       
  • Experimental Research in bor-60 and Analysis of its Continuation in MBIR
    • Abstract: A large volume of experimental research is being done in BOR-60 to validate promising new nuclear materials and increase fuel burnup and neutron fluence. Service life tests in reactors are time-consuming. It is obvious that they cannot be done in BOR-60 over the time to its final shutdown. The continuation of the irradiation programs in MBIR will make it possible to start up new reactors and validate the possibility of extending the service life of operating reactors. Research has shown that the irradiation of materials started in BOR-60 can be continued in MBIR.
      PubDate: 2014-09-10
       
  • Development of Supercritical-Water Cooled Reactors in Russia and Abroad
    • Abstract: Analysis of foreign research on SCWR attests to their systemacy and consistency and, especially, the timely training of cadres. The knowledge accumulated in our country in the last 10 years makes it possible to refine the previously developed concept of the 1700 MW(e) VVER-SKD reactor, indicate a plan for top-priority research, formulate a technical mission and proceed to the design of an experimental 30 MW reactor.
      PubDate: 2014-09-10
       
  • Reflood Investigation of Model Fuel Assemblies of Light-Water Reactors for
           a Loss-of-Coolant Accident
    • Abstract: The results of a reflood investigation of model VVER and PWR fuel assemblies for maximum design-basis and beyond design-basis accidents performed on the RBHT, SVD, and PARAMETR stands are presented. The variation ranges of the regime parameters are: initial temperature of fuel element 460–600°C; mass velocity of water 47–160 kg/(m2·sec), underheating at the entry into the model fuel assembly 11–108°C; pressure 0.14–0.42 MPa; and, linear heat flux density simulating the residual heat release 0–2.3 kW/m. A colligating relation describing the experimental data to within 30% is obtained for the wetting front of model fuel assemblies, which makes it possible to calculate the cool-down time of model fuel assemblies with different designs and evaluate the reflooding time of VVER and PWR.
      PubDate: 2014-09-10
       
  • Neutron-Physical Validation of NP, AM, and CM Transmutation
    • PubDate: 2014-09-10
       
  • Comparative Analysis of Algorithms for Representing a Scattering
           Indicatrix in the Probabilistic Method of Discrete Ordinates
    • Abstract: The form of the collision integral in the equations of the probabilistic method of discrete ordinates is examined. Two algorithms for calculating double differential energy-angle sections based on evaluated nuclear data are described. In the first (physical) algorithm the sections are calculated, according to the law of elastic scattering, by the method of local integration of a δ function and in the second the sections are reconstructed according to the moments of the scattering matrix. The advantages of the algorithms in the calculation of different functionals in problems with an external neutron source are analyzed. The computational results for a system with a source of 14 MeV neutrons are presented. The algorithms are compared from the standpoint of the correct scattering description by means of a finite number of moments of transfer cross sections.
      PubDate: 2014-09-10
       
  • Neutron-Physical Characteristics of a Neutron Source for the Production of
           Radioactive Isotopes Based on the Interaction of Electrons with Liquid
           Gallium
    • Abstract: The nuclear-physical characteristics obtained for a gallium target in a series of experiments using the time-of-flight method, the method of threshold indicators and a spectrometer based on a 3He proportional counter on the IREN setup (JINR, Dubna) are presented. The absolute values of the energy spectra of leakage neutrons in the energy range from 10 keV to 15 MeV were measured. The activation method was used to measure the neutron flux density on the surface of a gallium target: (2.882 ± 0.098) · 108 sec–1 · cm–2. The integral yield of neutrons obtained from the gallium target on the basis of these data was 1.54 · 1014 sec–1 with average current 4 mA. The time dependence of the activation level of the gallium target was measured. It was shown as a result of the analysis that the background level is reached on the surface of the irradiated gallium target in 5 days.
      PubDate: 2014-08-01
       
  • High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast
           Reactors for Hydrogen Production
    • Abstract: Studies show that in principle it is possible by relying on the BN-600 design to secure the required parameters of a reactor setup with a fast reactor with high-temperature sodium coolant (BN-VT) for hydrogen production. The calculations for 600 MW(t) BN-VT for electricity and hydrogen production based on solid-oxide electrolysis of water taking account of a fundamentally different method of purification – removal of hydrogen and tritium from the sodium by vacuum pumping through special membranes – have shown that the efficiency of such a system is ~40 % and hydrogen production volume is 2.8 · 104 liters/sec. The purification of hydrogen by removing tritium to a concentration ensuring the maximum admissible hydrogen concentration in the hydrogen produced 3.26 Bq/liter, imposes additional requirements on the hydrogen removal system.
      PubDate: 2014-07-27
       
  • Russian Codes for Safety Analysis of Sodium-Cooled Fast Reactors
    • Abstract: An approach to validating the safety of sodium-cooled fast reactors which was devised in Russia as these reactors were developed is presented. The collection of computational codes used for validating safety is described. Attention is focused on a group of codes which are intended for systematic analysis of all phases of a serious beyond design-basis accident resulting in the destruction of the core. The domestic approach to the analysis of the consequences of serious accidents is compared to the methodology developed abroad. Up to now the code system under development has made it possible to perform the main tasks of design validation, but the chosen path of development, where a separate computational code was developed for each individual problem, is not exhausted. On the one hand the complexity of the mathematical models drawn into the analysis has increased significantly, while on the other hand significant advances have been made in the development of computational technologies. The answer to the present situation is the tendency observed in the world nuclear community toward developing integrated codes and multipurpose computational systems. In Russia, this tendency is realized in the program for the development of a new generation of code systems within the framework of a special federal program.
      PubDate: 2014-07-27
       
  • Analysis of the Present Status of Lead and Lead-Bismuth Coolant Technology
    • Abstract: Analysis has shown that the current research on the technology of heavy liquid-metal coolants includes scientific-research and experimental development work on the validation, design and development of methods and means as well as the direct preparation of the coolant, the startup of circulation loops with heavy liquid-metal coolants and routine operation and decommissioning. The current methods and means include hydrogen purification of the coolant and loop by removal of slag-forming impurities, regulation of dissolved oxygen in the coolant for anticorrosion protection of steel, filtration of the coolant and protective gas and monitoring of the coolant under reactor and non-reactor conditions. The current processes presuppose careful preparation of heavy liquid-metal coolants before and during loading of the circulation loop, a complex of measures in startup regimes and minimal worker diversion for maintenance during routine operation of the facility.
      PubDate: 2014-07-27
       
  • Computational and Experimental Validation of the Planned Emergency
           Heat-Removal System for BN-1200
    • Abstract: The results of computational and experimental validation of the design of the emergency heat-removal system for BN-1200 are presented. The results of experimental studies performed on a water model of the V-200 integrated stand are presented, and the planning of experiments on the TISEI stand for validation of the efficiency and operating regimes using the BURNA, GRIF, and Flow Vision computational design codes is discussed.
      PubDate: 2014-07-27
       
  • Nuclear Power as a Component of Innovative Development in a Globalized
           World Economy
    • Abstract: It is shown that it is not so much the internal problems as the macroeconomic situation that has a decisive effect on nuclear power in different countries. Analysis performed in the international project INPRO under the auspices of IAEA shows that many developing countries have big plans for growing nuclear capacities and they hope to expand the market for services in the nuclear-power sphere. The potential accumulated in Russia in technologies of sodium-cooled fast reactors with mixed uranium-plutonium oxide fuel should be used to solve the internal problems of the nuclear industry and to expand the package of services at the closing stage of the NFC when selling domestically produced reactors.
      PubDate: 2014-07-27
       
  • Development of Sodium Coolant Technology for Fast Reactors
    • Abstract: The results of investigations of the composition of sodium impurities and sodium coolant filtrate during prolonged operation of a fast reactor and the methods and means for monitoring impurities and removing them from sodium coolant are presented. Models of mass transfer of dissolved impurities and suspensions of the components of steel in sodium loops are described. The mass transfer of tritium formed in a fast reactor is analyzed.
      PubDate: 2014-07-27
       
  • Development of an Evaluated Nuclear Database for Modern Technologies
    • Abstract: The main phases in the development of the constants required for neutron-physical calculations of fast reactors, ranging from systems of BNAB group constants to modern national libraries of the BROND and ROSFOND evaluated nuclear data files, are examined. Problems for subsequent conversion of the libraries into licensed sets of standard data for nuclear technological projects are formulated.
      PubDate: 2014-07-27
       
  • 60th Anniversary of the Startup of the world’s First Nuclear Power
           Plant in Obninsk
    • PubDate: 2014-07-27
       
  • From the First npp to Large-Scale Nuclear Power
    • Abstract: The advancement of domestic research and development work on reactor technologies from the world’s first NPP built in Obninsk to modern fast reactors with liquid-metal coolants is analyzed. The contribution of the Physics and Energy Institute to the development of a strategy for the advancement of large-scale nuclear power based on a closed nuclear fuel cycle with fast reactors is examined. It is noted that a scientific and technical base now exists for implementing our country’s initiative for securing sufficient energy for stable development of the world and the global infrastructure for nuclear power based on a network of international nuclear fuel centers and expanded exports of new-generation nuclear power plants with thermal and fast reactors including an attractive package of NFC services. The basic problems are formulated within the framework of the future development of reactor technologies for improving the safety and cost-effectiveness of NPP with new-generation fast reactors which are now in operation or being designed.
      PubDate: 2014-07-27
       
 
 
JournalTOCs
School of Mathematical and Computer Sciences
Heriot-Watt University
Edinburgh, EH14 4AS, UK
Email: journaltocs@hw.ac.uk
Tel: +00 44 (0)131 4513762
Fax: +00 44 (0)131 4513327
 
About JournalTOCs
API
Help
News (blog, publications)
JournalTOCs on Twitter   JournalTOCs on Facebook

JournalTOCs © 2009-2014