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Daneshyari Nuclear Energy and Engineering Journas Latest Articles

Nuclear Energy and Engineering Research Articles

Thermodynamic modeling of the U–Mn and U–Nb systems
Fulltext Access 6 Pages 2008
Interaction of 〈1 0 0〉 and ½〈1 1 1〉 dislocation loops with point defects in ferritic alloys
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Tensile properties of EC316LN irradiated in SINQ to 20 dpa
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Thermal stability of nano-structured ferritic alloy
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The present status of R&D for the muon target at J-PARC: The development of silver-brazing method for graphite
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Existence states of deuterium irradiated into LiAlO2
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Grain boundary influence on displacement cascades in UO2: A molecular dynamics study
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Structural investigation of re-deposited layers in JET
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Pyrochlore-structured titanate ceramics for immobilisation of actinides: Hot isostatic pressing (HIPing) and stainless steel/waste form interactions
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Atomistic modeling of the vibrational and thermodynamic properties of uranium dioxide, UO2
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Low-temperature thermally-activated deformation and irradiation softening in neutron-irradiated molybdenum
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Cadmium leaching from thermal treated and gamma irradiated Mexican aluminosilicates
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Thermodynamic calculation of phase equilibria of the U–Ga and U–W systems
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Effect of wettability on bubble formation at gas nozzle under stagnant condition
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Structural modifications in pyrochlores caused by ions in the electronic stopping regime
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Strain evolution of zirconium hydride embedded in a Zircaloy-2 matrix
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Mechanical properties of V-4Cr-4Ti strengthened by precipitation and cold rolling
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Change of properties after oxidation of IG-11 graphite by air and CO2 gas
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Ab-initio approach to the effect of Fe on the diffusion in hcp Zr
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One-step brazing process to join CFC composites to copper and copper alloy
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Determination of UO2(s) dissolution rates in a hydrogen peroxide medium as a function of pressure and temperature
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The influence of relative humidity on iron corrosion under proton irradiation
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Identification of ultra-fine Ti-rich precipitates in V-Cr-Ti alloys irradiated below 300 °C by using positron CDB technique
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Material parameters of copper and CuCrZr alloy for cyclic plasticity at elevated temperatures
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Optimization of a wet chemistry method for fabrication of Li2TiO3 pebbles
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Analysis of the emissions of volatile organic compounds from the compression ignition engine fueled by diesel–biodiesel blend and diesel oil using gas chromatography
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Estimating the amount and distribution of radon flux density from the soil surface in China
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Short- versus long-term radon detectors: a comparative study in Galicia, NW Spain
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Measurements of radiation level in petroleum products and wastes in Riyadh City Refinery
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Windscale and Kyshtym: a double anniversary
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Studies on the distribution of 210Po and 210Pb in the ecosystem of Point Calimere Coast (Palk Strait), India
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Nuclides.net: a computational environment for nuclear data and applications in radioprotection and radioecology
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Nationwide survey on the natural radionuclides in industrial raw minerals in South Korea
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Spatial distribution of natural radioactivity levels in topsoil around the high-uranium mineralization zone of Kylleng-Pyndensohiong (Mawthabah) areas, West Khasi Hills District, Meghalaya, India
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Fate of 60Co at a sludge land application site
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Energy efficiency, security of supply and the environment in South Africa: Moving beyond the strategy documents
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Global oil peaking: Responding to the case for ‘abundant supplies of oil’
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Practical ways of evaluating wind speed persistence
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Studies on the dissolution kinetics of ceramic uranium dioxide particles in nitric acid by microwave heating
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Two-step water-splitting at 1273–1623 K using yttria-stabilized zirconia-iron oxide solid solution via co-precipitation and solid-state reaction
Fulltext Access 6 Pages 2008
Experimental investigation of integrated refrigeration system (IRS) with gas engine, compression chiller and absorption chiller
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Root causes of intergranular attack in an operating nuclear steam generator tube
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Neutron-induced swelling and embrittlement of pure iron and pure nickel irradiated in the BN-350 and BOR-60 fast reactors
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Sintering behavior of U–80 at.%Zr powder compacts in a vacuum environment
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Simulation of displacement cascades in Fe90Cr10 using a two band model potential
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Simulation of diffusion of oxygen and uranium in uranium dioxide nanocrystals
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Computer simulation of point defects in plutonium using MEAM potentials
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Liquid Pb–Bi embrittlement effects on the T91 steel after different heat treatments
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SIMS investigation of the spallation and transmutation products production in lead
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Numerical study on pressure wave propagation in a mercury loop
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Microstructural scale strain localisation in nuclear graphite
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Methodology to make a robust estimation of the carbon steel overpack lifetime with respect to the Belgian Supercontainer design
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A mathematical model for crevice corrosion under porous deposits
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Stress corrosion cracking of stainless-steel canister for concrete cask storage of spent fuel
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Influence of δ phase precipitation on the stress corrosion cracking resistance of alloy 718 in PWR primary water
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Tomographic atom probe characterization of the microstructure of a cold worked 316 austenitic stainless steel after neutron irradiation
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Formation of austenite in high Cr ferritic/martensitic steels by high fluence neutron irradiation
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Static strain aging and dislocation–impurity interactions in irradiated mild steel
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Microstructural development in a model austenitic alloy following electron and ion irradiation
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Influence of alloying elements on grain-growth in Zr(Fe) and Cu(Fe) thin-films under in situ ion-irradiation
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Microstructures of beta-silicon carbide after irradiation creep deformation at elevated temperatures
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Microstructural evolution under high flux irradiation of dilute Fe–CuNiMnSi alloys studied by an atomic kinetic Monte Carlo model accounting for both vacancies and self interstitials
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Development of non-destructive evaluation methods for degradation of HTGR graphite components
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Long term stability of iron for more than 1500 years indicated by archaeological samples from the Yamato 6th tumulus
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Non-destructive evaluation methods for degradation of IG-110 and IG-430 graphite
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Microstructural characterisation of nuclear grade graphite
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Effects of ion irradiation on the hardness properties of graphites and C/C composites by indentation tests
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Dimensional and material property changes to irradiated Gilsocarbon graphite irradiated between 650 and 750 °C
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Comparison of the oxidation rate and degree of graphitization of selected IG and NBG nuclear graphite grades
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High temperature reactors
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Ageing of zirconium alloy components
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Blind prediction exercise on modeling of PHWR fuel at extended burnup
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Behaviour of irradiated PHWR fuel pins during high temperature heating
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Flow accelerated corrosion and its control measures for the secondary circuit pipelines in Indian nuclear power plants
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The transformation behaviour of the β-phase in Zr–2.5Nb pressure tubes
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Very high swelling and embrittlement observed in a Fe–18Cr–10Ni–Ti hexagonal fuel wrapper irradiated in the BOR-60 fast reactor
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Irradiation creep and precipitation in a ferritic ODS steel under helium implantation
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Effect of sulphur on the strengthening of a Zr–Nb alloy
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An elastoplastic phase-field model for the evolution of hydride precipitation in zirconium. Part II: Specimen with flaws
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Texture, residual strain, and plastic deformation around scratches in alloy 600 using synchrotron X-ray Laue micro-diffraction
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Two-step two-stage fission gas release model
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The ‘granite encapsulation’ route to the safe disposal of Pu and other actinides
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Sensitivity of the magnetization curves of different austenitic stainless tube and pipe steels to mechanical fatigue
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Glass matrices for immobilizing nuclear waste containing molybdenum and phosphorus
Fulltext Access 6 Pages 2008
Interpretation of (Pu,U) matrix effect on atomization of analytes during GF-AAS analysis
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Transformation of Al2O3 to LiAlO2 in Pb–17Li at 800 °C
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Isotope effects in thermal neutron transmission and backscattering processes for ε-phase zirconium hydrides and deuterides
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The effect of an external electric field on radiation transmission and Compton scattering in plexiglass
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In-reactor performance of pressure tubes in CANDU reactors
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Dissolution of uranium metal without hydride formation or hydrogen gas generation
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Processing of uranium oxide and silicon carbide based fuel using polymer infiltration and pyrolysis
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M2N nitride phases of 9% chromium steels for nuclear applications
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LBE–water interaction in sub-critical reactors: First experimental and modelling results
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Natural circulation in a liquid metal one-dimensional loop
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ENEA experience in oxygen measurements
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Effect of the presence of In and Sn in the oxygen chemistry in molten 44.5% lead–55.5% bismuth alloy
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Heat treatment effect of T91 martensitic steel on liquid metal embrittlement
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Synthesis of rare earth phosphates in molten LiCl–KCl eutectic: Application to preliminary treatment of chlorinated waste streams containing fission products
Fulltext Access 6 Pages 2008
Recognition of uranium oxides in soil particulate matter by means of μ-Raman spectrometry
Fulltext Access 6 Pages 2008
Long-term corrosion behaviour of low-carbon steel in anoxic environment: Characterisation of archaeological artefacts
Fulltext Access 6 Pages 2008
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