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Daneshyari Nuclear Energy and Engineering Journas Latest Articles

Nuclear Energy and Engineering Research Articles

Structural study on uranyl ion in 1-butyl-3-methylimidazolium nonafluorobutanesulfonate ionic liquid
Fulltext Access 8 Pages 2005
Pressure wave propagation in air-water bubbly and slug flow
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Removal of polonium from stainless steel surface contaminated by neutron irradiated lead-bismuth eutectic
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Encapsulation of radioactive metals inside multilayered polyhedral shells of carbon as a barrier to radionuclide release
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Experimental studies on steel corrosion in Pb-Bi with steam injection
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Study on Pb-Bi-water direct contact boiling two-phase flow and heat transfer
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Corrosion studies in support of lead-bismuth cooled FBRs
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Study on Pb-Bi natural circulation phenomena
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Safety aspects of the combined HTTR/steam reforming complex for nuclear hyrogen production
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Synergistic hydrogen production by nuclear-heated steam reforming of fossil fuels
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Carbon dioxide zero-emission hydrogen system based on nuclear power
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Research and development on nuclear hydrogen production using HTGR at JAERI
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A novel chromatographic separation technique using tertiary pyridine resin for the partitioning of trivalent actinides and lanthanides
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Experimentaland numerical investigation of liquid metal boiling in fuel subassemblies under natural circulation conditions
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Using selective precipitant for uranyl ions - Fundamental studies for evaluating the precipitant performance
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Studies of laser induced cesium and rubidium hydride formation in vapor cells and their application for isotope separation
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A study on improvement of sodium cooled TRU burner design using burnable poison
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Nuclear waste burner for minor actinides elimination
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Simulation study on candle burnup applied to block-type high temperature gas cooled reactor
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Core concept of compound process fuel cycle
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Study on kinetics of fast subcritical assembly-Contribution of delayed neutrons to the transition after a reactivity insertion in a subcritical system-
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Small PWRs using coated particle fuel for district heating, PFPWR50
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Multi-dimensional analysis of two-phase flow inside subchannels of nuclear fuel assembly
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The feasibility study on perfect burning reactor system
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Core performance of new concept passive-safety reactor “kamado” - safety, burn-up and uranium resource problem -
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Pitting corrosion of the laser surface melted Alloy 600
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Environmental impact of advanced management of spent nuclear fuel on permanent disposal of high level waste in Korea
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Estimation of 222Rn release from the phosphogypsum board used in housing panels
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Application of activated charcoal radon collectors in high humidity environments
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Radon and thoron monitoring in the environment of Kumaun Himalayas: survey and outcomes
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137Cs concentration in meat of wild boars (Sus scrofa) in Croatia a decade and half after the Chernobyl accident
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Radioactivity concentration in liquid and solid phases of scale and sludge generated in the petroleum industry
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Cost assessment of ventilation and averted dose due to radon in dwellings
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Natural radiation exposure in the Campo Arañuelo region in the surroundings of Almaraz nuclear power station (Spain)
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Radon in the spas of Croatia
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Airborne 131I at a background monitoring site
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Application of the luminescence single-aliquot technique for dose estimation in the Marmara Sea
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Experimental studies of mechanical properties of solid zirconium hydrides
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Development of the package-reactor (2) -core characteristics-
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Effects of heat input on the microstructure and toughness of the 8 MnMoNi 5 5 shape-welded nuclear steel
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Enhanced diffusion under alpha self-irradiation in spent nuclear fuel: Theoretical approaches
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Radiolytic modelling of spent fuel oxidative dissolution mechanism. Calibration against UO2 dynamic leaching experiments
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Leaching behaviour of unirradiated high temperature reactor (HTR) UO2-ThO2 mixed oxides fuel particles
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Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure
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The inhibiting effects of hydrogen on the corrosion of uranium dioxide under nuclear waste disposal conditions
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Critical temperature of the lead-bismuth eutectic (LBE) alloy
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Natural sintering of carbonate powder for use as a carbon-14 immobilization matrix
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Improvement of plutonium proliferation resistance by doping minor actinides
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Radiation protection of mox-fuel by doping with 231Pa and 232U
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The pumping performances of the turbomoleculae pump simulated by direct simulation monte carlo method
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Release of fission tritium through Zircaloy-4 fuel cladding tubes
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LiSoR irradiation experiments and preliminary post-irradiation examinations
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The effect of 800 MeV proton irradiation on the mechanical properties of tungsten at room temperature and at 475 °C
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DPA calculation for Japanese spallation neutron source
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Optimized concept design of the target station of Chinese spallation neutron source
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Subject index
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A Knudsen cell-mass spectrometer facility to investigate oxidation and vaporisation processes in nuclear fuel
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Modelling thermal properties of actinide dioxide fuels
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Electrochemistry of nitrogen and nitrides in molten salts
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The concentration and pH dependent diffusion of 137Cs in compacted bentonite by using capillary method
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Hydrogen ion bombardment damage in stainless steel mirrors
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High temperature properties of an iron phosphate melt containing high chrome nuclear waste
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Point defects in uranium dioxide: Ab initio pseudopotential approach in the generalized gradient approximation
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Comparison of the corrosion behavior of austenitic and ferritic/martensitic steels exposed to static liquid Pb-Bi at 450 and 550 °C
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Inspection of brazed joints between cooling tube and heat sink of PFC for SST-1 tokamak by IR thermography technique
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Theoretical expressions for removing tritium from exhaust gas
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Real time control of fully non-inductive operation in Tore Supra leading to 6 min, 1 GJ plasma discharges
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An integral approach to plasma shape control
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Optimization of the IGNITOR operating scenario at 11 MA
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Matching to ELMy plasmas in the ICRF domain
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The Laser Mégajoule (LMJ) Project dedicated to inertial confinement fusion: Development and construction status
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WENDELSTEIN 7-X at the transition to assembly
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ITER towards the construction
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Pioneering superconducting magnets in large tokamaks: Evaluation after 16 years of operating experience in tore supra
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The European development of a full scale switching unit for the ITER switching and discharging networks
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Radiation swelling behavior and its dependence on temperature, dose rate, and dislocation structure evolution
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Development of the package-reactor (1) -reactor for pioneering new nuclear markets-
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Application of candle burnup strategy for future nuclear energy utilization
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Toward the 21st century nuclear-science technology
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A superposition method to calculate the interaction effect between bodies in diffusion theory
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Prediction of fission mass-yield distributions based on cross section calculations
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Evaluation of performance of a new gamma technique for assay of radioactive waste
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New results on the neutron-induced fission cross-section of 231Pa for incident neutron energies En = 0.8-3.5 MeV
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A practical method for calculation of mass-attenuation coefficients of β particles
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Characterization of defect clusters in ion-irradiated A533B steel
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Lead-bismuth eutectic recrystallization studies for the Megapie target
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Electrical behavior of platinum-group metals in glass-forming oxide melts
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Deformation microstructure of neutron-irradiated pure polycrystalline vanadium
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The ITER thermal shields for the magnet system: Design evolution and analysis
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Thermodynamic stabilities of SrCeO3 and Sr2CeO4 using the fluoride EMF technique
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Edge and divertor physics with reversed toroidal field in JET
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Experimental observations and modelling of carbon transport in the inner divertor of JET
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Mechanism of dynamic strain aging and characterization of its effect on the low-cycle fatigue behavior in type 316L stainless steel
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Self-reduction of dioxoplutonium VI: Characterization and modeling of radiolytic and disproportionation pathways
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The response of several luminescent materials to keV and MeV ions
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Environment and oxidation state of molybdenum in simulated high level nuclear waste glass compositions
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Electrical conductivity and non-stoichiometry in the (U,Gd)O2±x system
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Fabrication and microstructure characterization of inert matrix fuel based on yttria stabilized zirconia
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Master-equation for cascade damage modeling
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Expansion of solidified lead bismuth eutectic
Fulltext Access 8 Pages 2005
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