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 Subjects -> ENERGY (Total: 239 journals)     - ELECTRICAL ENERGY (3 journals)    - ENERGY (157 journals)    - Energy: General (8 journals)    - NUCLEAR ENERGY (17 journals)    - PETROLEUM AND GAS (47 journals)    - WIND ENERGY (7 journals) ENERGY (157 journals)                  1 2 | Last
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Hybrid journal (It can contain Open Access articles)
ISSN (Print) 1573-8205 - ISSN (Online) 1063-4258
• Probabilistic Strength Analysis of the Main Joint of a VVER-1000 Reactor
• Abstract: A method of calculating the probability of a leak occurring in the main joint of the reactor and the probability of the head detaching from the vessel body of VVER-TOI as a result of stud-bolt failure and the computational results are presented. The stresses in the stud bolts are calculated taking account of their redistribution in intact stud bolts for different numbers of failed stud bolts. In the calculations of the stud bolt failure probability, the statistical characteristics of the mechanical and strength properties of the material, the characteristics of the means of nondestructive flaw detection in the material, and the probability that defects are missed during checks are taken into account.
PubDate: 2013-12-20

• Investigation of the Hydrodynamic Structure of Throttled Fluid Flow
• Abstract: The objectives of this work are to investigate stream flow in smooth and intensified flow sections and to determine the numerical values of the flow characteristics. The hydrodynamic structure of throttled flow, observed stream flows, vortex and stagnant zones, which depend on the geometric shapes of the flow sections, are presented and described. The numerical values of some flow parameters and optimal geometric dimensions of the throttle channels with different methods of flow throttling are determined. The data obtained will make it possible to develop flow regulators for NPP for high coolant parameters, which ensure stable and reliable operation in startup, normal and emergency regimes of a nuclear reactor.
PubDate: 2013-12-20

• Thermodynamic Analysis of a Space Nuclear Power Plant with a Gas-Turbine Energy Conversion System
• Abstract: The results of a thermodynamic analysis of a space nuclear power plant with a gas-turbine energy conversion system are presented. Questions concerning the choice of optimal efficiency and maximum surface area of the radiant cooler are examined. The effect of losses in individual elements of the loop on the main plant performance indices is investigated.
PubDate: 2013-12-20

• Accelerator-Blanket System as Np, Am, Cm Incinerator in Different NFC Closure Scenarios
• Abstract: An accelerator-blanket system with a proton accelerator and lead-bismuth coolant for transmuting Np, Am, and Cm is examined. The proton accelerator power is 10 MW, the proton energy 1 GeV and the blanket power 330 MW with blanket subcriticality ΔK = 0.05. It is shown that the use of an accelerator-blanket system in symbiosis with operating VVER-1000 reactors makes it possible to lower the radioactivity of the wastes about 20-fold and to satisfy the principle of radiation-migration balance of activity over a ~500-yr cool-down period with subterranean disposal. In terms of radiation and the technological characteristics of the spent fuel and wastes, this system does not have any special advantages for incinerating Np, Am, and Cm with fast reactors in a closed fuel cycle with U, Pu, Np, Am, and Cm recirculated and natural uranium as the makeup fuel. The accelerator-blanket system presented here can be regarded as an effective specialized setup for incinerating Np, Am, and Cm accumulated in the thermal reactors of present-day nuclear power.
PubDate: 2013-12-20

• Ruthenium Capture from the Gas Phase during Reprocessing of Spent Uranium-Plutonium Nitride Fuel from Fast Reactors
• Abstract: Information on methods for capturing ruthenium tetroxide from the gas phase are examined, analyzed and generalized in application to the reprocessing of spent nitride fuel from fast reactors. It is found that when the fuel is dissolved in nitric acid or oxidized by oxygen in air the yield of RuO4 in the gas phase does not exceed 1.5% of the total mass of ruthenium. The most efficient method of capture on γ-Al2O3 at temperatures above 110°C is chosen.
PubDate: 2013-12-20

• Purification of Natural-Uranium Hexafluoride in a Cascade with an Intermediate Product Stream
• Abstract: A scheme is proposed for purification of natural-uranium hexafluoride in an intermediate product stream of a cascade in which low-enrichment uranium is obtained in the main product stream. It is shown that effective purification to remove the isotope 234U can be accomplished in one or two stages with purified stock with the natural 235U concentration or purified depleted uranium obtained in the intermediate product. A diluent for high-enrichment uranium with a several-fold lower separative work compared with its production from depleted wastes from separative production can be produced from these products. In addition, these products make it possible to obtain high-quality low-enrichment uranium with low 234U content.
PubDate: 2013-12-20

• Flow Particulars of Some Transient Regimes with Load Shedding on VVER-1000
• Abstract: The results of an investigation of the operating regime of a nuclear power plant with VVER-1000 with actuation of accelerated preventative protection at power 100% N nom with one of two turbo pumps switched off are presented. The modeling was performed using the improved accuracy RELAPSCDAPSIM/Mod3.4 code and a corresponding model for the No. 2 unit of the Khmelnitsky NPP. It is shown that the actuation of emergency protection based on the fact that the three main circulation pumps are switched off because of a drop in the feed water in the steam generators cannot be avoided. On the basis of the results obtained, it is proposed that for the second half of the fuel run an emergency protection signal instead of an accelerated preventative protection be immediate generated when one of the turbo pumps is switched off at power level >95% N nom; this will make it possible to secure more forgiving temperature regimes for fuel and equipment, avoid additional thermal cycling loads, and prevent violation of the safe operating limits on the basis of the feed water level in the steam generators.
PubDate: 2013-12-20

• Estimation of the Radiation Dose to the Public Due to Atmospheric Emissions from the Rostov NPP
• Abstract: The radiation dose to the public due to atmospheric emissions from the Rostov NPP is calculated using a point conservative approach and a complex of migration and dosimetric models. The radiation exposure pathways and the individual radionuclides in the NPP emissions are ranked according to their contribution to the total dose.
PubDate: 2013-12-19

• Determination of the Kerma in Biological Tissue with Gadolinium Irradiated by the Epithermal Neutron Beam in VVR–SM Reactor at the Institute of Nuclear Physics of the Academy of Sciences of Uzbekistan
• Abstract: The kerma in biological tissue with gadolinium under irradiation by epithermal neutrons in a special channel of the VVR-SM reactor at the Institute of Nuclear Physics of the Academy of Sciences of the Republic of Uzbekistan is determined. The neutron kerma rate is found to be $K_n^{\mathrm{b}.\mathrm{t}}$ = 1.35 · 10–4 Gy/sec for biological tissue and $K_n^{\mathrm{Gd}}$ = 3.1 · 10–7 Gy/sec for 1 μg of natural gadolinium in 1 g of biological tissue.
PubDate: 2013-12-19

• Particulars of Risk Determination for Investments in NPP Construction Projects
• Abstract: An important element in making decisions about choosing a preferred NPP project is the evaluation of the economic risk associated with macroeconomic uncertainty. Different parameters can be used to classify the risks that must be taken into account when calculating the efficacy of building a NPP. They must be viewed as the quintessence of the general, investment, and project risks considered in conventional power generation projects as well as specialized risks inherent in nuclear power. A method of cumulative quantitative determination of the risks of such projects based on global experience is presented here. It can improve the existing approaches to the calculation of the main economic indices of NPP construction projects.
PubDate: 2013-12-19

• Increasing Identification Reliability for Technogenic Low-Activity Radionuclides by Means of the ASKRO Spectrometric Channel
• Abstract: The use of spectrometric information from the ASKRO automated station to increase the reliability of identification of the low-activity technogenic radionuclides 131I, 137Cs, and 140La in the atmospheric boundary layer is examined. The Matros statistical algorithm for processing data with the spectrometer operating in the radiometric mode makes it possible to classify in 45 min the minimum activity 5–10 Bq/m3 with probability ~0.7; false detection comprises ≤0.01 over 100 h. The low identification reliability for lowactivity radionuclides, the relatively long time required for obtaining results, and the impossibility of processing the data obtained during periods of precipitation limit the use of the algorithm. It is shown that spectral processing by the method of the minimum makes it possible to identify in 15–30 min with probability ~1 the minimum activity of 137Cs and 140La – 11 and 6 Bq/m3, respectively – with false detection <10–4.
PubDate: 2013-12-19

• Assimilation of a Closed Uranium-Plutonium Nuclear Fuel Cycle Based on Fast Reactors With Liquid-Metal Coolant
• Abstract: The advantages of fast reactors are presented and a sequence of actions for solving the important problem of assimilating a closed NFC with uranium-plutonium fuel based on fast reactors with liquid-metal coolant is examined taking account of the problems of modern nuclear power based on thermal reactors.
PubDate: 2013-12-01

• Serviceability of the Fuel Elements in a VK-50 Boiling-Water Vessel Reactor
• Abstract: The results of physical-metallurgical studies of fuel-element cladding in a nuclear power plant with a boiling-water vessel reactor are presented. It is shown that the fuel materials are highly reliable under the operating conditions.
PubDate: 2013-12-01

• Determination of the Frequency of Exceedance Above the Critical Power of RBMK-1000 Fuel Channels in Stationary Operating Regimes
• Abstract: A method is proposed for calculating the frequency of exceedance above the critical power of fuel assemblies in stationary operating regimes of RBMK-1000 on the basis of information about errors in regulation and monitoring of fuel-channel parameters.
PubDate: 2013-12-01

• Experience in Operating Accessory Parts Made of Alloy E-635 in VVER-1000 Fuel Assemblies
• Abstract: Post-reactor studies of structural elements made of E-635 alloy in VVER-1000 TVSA fuel assemblies have shown that with regard to the operating characteristics their service life was not exhausted during a six-year run and burnup to 72 MW⋅days/kg. It was confirmed that the performance of alloy E-635 in fuel-element cladding and accessory components of fuel assemblies is highly reliable. The geometric parameters, corrosion state and mechanical properties of parts made from this alloy did not reach values precluding further service.
PubDate: 2013-12-01

• Radiation Protection During Decommissioning of the MRT and RFT Material-Research Multi-Loop Reactors at the National Research Center – Kurchatov Institute
• Abstract: Stopped and prepared-for-decommissioning MR and RFT multi-loop materials-research reactors are sources of radiation danger. The radiation protection was optimized to secure radiation safety for workers and the public during decommissioning of the reactors. This lowered significantly the individual and collective effective radiation dose to workers and reduced the number of workers required for radiation-hazardous work.
PubDate: 2013-12-01

• Optimization of a Centrifuge Cascade for Separating a Multicomponent Mixture of Isotopes
• Abstract: A method is developed for calculating the optimal parameters of a cascade of gas centrifuges for separating a multicomponent mixture of gases. A universal computational scheme for optimizing a cascade using different criteria is proposed. The particulars of minimizing the total flow of a cascade with prescribed external flows and product isotope concentration are studied by means of a computational experiment. It is shown that the concentration of the non-product isotopes in the product and waste flows of a cascade can be changed considerably by shifting the feed input of the cascade relative to optimum minimizing the possible number of centrifuges. This feature of the optimization procedure can be used effectively to purify reprocessed uranium from 232U.
PubDate: 2013-12-01

• Experimental Investigation of the Abrasive-Blowout Decontamination of the Inner Surface of Pipelines in a Pulsed Pneumatic Conveyer System for Transporting Solid Wastes
• PubDate: 2013-12-01

• Use of High-Duty Cast Iron With Spheroidal Graphite for TUK-146 Shipment Casks
• PubDate: 2013-12-01

• Beryllium Fluoride – Starting Material for the Production of Metallic Beryllium and the Salt Components for Nuclear Reactors
• Abstract: The use of beryllium fluoride in nuclear power is studied: in melt with lithium fluoride as coolant and solvent for uranium, plutonium and thorium salts in high-temperature molten-salt nuclear reactors (ZhSR, MSR) as well as for making fluoroberyllate glass for regulating low neutron fluxes and welding special purpose articles. The existing methods of obtaining beryllium fluoride are described. A new method is proposed for obtaining high-purity fused beryllium fluoride from beryllium wastes by evaporating a saturated solution with fluorine-to-beryllium molar ratio 2.06–2.18.
PubDate: 2013-12-01

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