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Daneshyari Nuclear Energy and Engineering Journas Latest Articles

Nuclear Energy and Engineering Research Articles

Calculations on fission gas behaviour in the high burnup structure
Fulltext Access 8 Pages 2006
Hydrogen permeability through a mixed molten salt of LiF, NaF and KF (Flinak) as a heat-transfer fluid
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Corrosion of ferritic–martensitic steel HT9 in supercritical water
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Molecular dynamics simulation study of primary damage in UO2 produced by cascade overlaps
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Strain-rate effects on microstructural deformation in irradiated 316 SS
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Microstructural analysis of deformation in neutron-irradiated fcc materials
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Characterization of precipitates in MA/ODS ferritic alloys
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Interaction of helium atoms with edge dislocations in α-Fe
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Diffusion of He interstitials in grain boundaries in α-Fe
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Effect of displacement cascade structure and defect mobility on the growth of point defect clusters under irradiation
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Two-band second moment model for transition metals and alloys
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Recrystallisation of amorphous natural brannerite through annealing: The effect of radiation damage on the chemical durability of brannerite
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Study on behavior of tritium in concrete wall
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Displacement cascade initiated with the realistic energy of the recoil nucleus in UO2 matrix by molecular dynamics simulation
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Tensile tests and TEM investigations on LiSoR-2 to -4
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A study of the neutron irradiation effects on the susceptibility to embrittlement of A316L and T91 steels in lead–bismuth eutectic
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The role of deformation mechanisms in flow localization of 316L stainless steel
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The effects of fast reactor irradiation conditions on the tensile properties of two ferritic/martensitic steels
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Influence of hydrogen on the toughness of irradiated reactor pressure vessel steels
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Dysprosium hafnate as absorbing material for control rods
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Density changes in plutonium observed from accelerated aging using Pu-238 enrichment
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Dynamic strain ageing in prior cold worked 15Cr–15Ni titanium modified stainless steel (Alloy D9)
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An analytical model for the Amoeba effect in UO2 fuel pellets
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A NRA study of temperature and heavy ion irradiation effects on helium migration in sintered uranium dioxide
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Preparation, characterization and thermodynamic stability of Rh3Te2O10
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Enhancing cerium and plutonium solubility by reduction in borosilicate glass
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Radiobiological monitoring of striped field mouse populations in the Moscow recreation forest “Kuzminki”
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Soil radioactivity and incidence of cancer in Nigeria
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Modelling of thermally enhanced erosion of beryllium
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Interaction between borosilicate melt and Inconel
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On stability of spatial distributions of crystal structure defects in irradiated high burnup UO2 fuel
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Thoria, a quasi-inert matrix for actinides dispositions
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Yttrium stabilised zirconia inert matrix fuel irradiation at an international research reactor
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Sintering behaviour and microstructures of carbides and nitrides for the inert matrix fuel by spark plasma sintering
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Neutronics calculations on the impact of burnable poisons to safety and non-proliferation aspects of inert matrix fuel
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Specific outcomes of the research on the spent fuel long-term evolution in interim dry storage and deep geological disposal
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Plutonium incorporation in phosphate and titanate ceramics for minor actinide containment
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Improvement of the preparation of sintered pellets of thorium phosphate-diphosphate and associated solid solutions from crystallized precursors
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Study on control of oxygen concentration in lead–bismuth flow using lead oxide particles
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Role of proton irradiation and relative air humidity on iron corrosion
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Fuel behavior comparison for a research reactor
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A study of xenon aggregates in uranium dioxide using X-ray absorption spectroscopy
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Resistivity recovery simulations of electron-irradiated iron: Kinetic Monte Carlo versus cluster dynamics
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Influence of the crack-tip hydride concentration on the fracture toughness of Zircaloy-4
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Phase diagram of the ZrO2–FeO system
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Determination of elastic modulus and residual stress of plasma-sprayed tungsten coating on steel substrate
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Oxidation of Zircaloy-4 by oxygen and the production of water
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Heat and mass transfer calculations in heavy liquid metal loops under forced convection flow conditions
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Deposition behaviour of corrosion products on the Zircaloy heat transfer surface
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Strain hardening and long-range internal stress in the localized deformation of irradiated polycrystalline metals
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Status of HELIAS reactor studies
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Design study of fusion DEMO plant at JAERI
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DEMO and fusion power plant conceptual studies in Europe
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Mechanical properties of small size specimens of F82H steel
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Property tailorability for advanced CVI silicon carbide composites for fusion
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Ferritic steel-blanket systems integration R&D—Compatibility assessment
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Liquid metal compatibility issues for test blanket modules
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Structural materials development and databases
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Tasks and structure of the WENDELSTEIN 7-X control system
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18.1 T cryocooled superconducting magnet with a Bi2223 high-TcTc insert
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Analysis of stability and quench in HTS devices—New approaches
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Superconducting magnet and conductor research activities in the US fusion program
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Towards steady state operation in large tokamaks: The experience of TORE SUPRA superconducting magnet system
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Overview of recent progress in IFMIF neutronics
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Study of Ohmic loss of high power polarizers at 170 GHz for ITER
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Parametric neutronic analysis of HCLL blanket for DEMO fusion reactor utilizing vacuum vessel ITER FDR design
Fulltext Access 8 Pages 2006
RF antenna analysis with the ICANT code
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Numerical analysis of MHD flow structure behind a square rod
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Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant
Fulltext Access 8 Pages 2006
RF TBMs for ITER tests
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The European test blanket module systems: Design and integration in ITER
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Direct numerical simulation of MHD flow with electrically conducting wall
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Experimental examination of heat removal limitation of screw cooling tube at high pressure and temperature conditions
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EU activities in preparation of the procurement of the ITER divertor
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Russian Federation contribution to the ITER project
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The AREVA HTR fuel cycle: An analysis of technical issues and potential industrial solutions
Fulltext Access 8 Pages 2006
Oxygen potential of (Pu0.91Am0.09)O2−x
Fulltext Access 8 Pages 2006
H, He, Ne, Ar-bombardment of amorphous hydrocarbon structures
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Mechanical energy losses due to the movement of dislocations in molybdenum at high temperatures (0.3Tm)
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Investigation of plutonium allotropic phase transformations through differential scanning calorimetry
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Near-threshold fatigue crack behaviour in EUROFER 97 at different temperatures
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The EPR: A clear step forward in dose reduction and radiation protection
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REMOVED: The EPR—a comprehensive design concept against external events
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Single rod experiments on transient void behavior during low-pressure reactivity-initiated accidents in light water reactors
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CANDU technology for Generation III+ and IV reactors
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CFD and DNS methodologies development for fuel bundle simulations
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EPR, spearhead of the European nuclear renaissance
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Investigation of bounds on particle packing in pebble-bed high temperature reactors
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Overview of the European Union fusion nuclear technologies development and essential elements on the way to DEMO
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ANTARES: The HTR/VHTR project at Framatome ANP
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Advanced modularity design for the MIT pebble bed reactor
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Detection of embedded fatigue cracks in Inconel weld overlay and the evaluation of the minimum thickness of the weld overlay using eddy current testing
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Hazard and operability study using approximate reasoning in light-water reactors passive systems
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Melt quenching and coolability by water injection from below: Co-injection of water and non-condensable gas
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A study on concrete degradation during molten core/concrete interactions
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Effects of oxide and hydrogen on the behavior of Zircaloy-4 cladding during the loss of the coolant accident (LOCA)
Fulltext Access 8 Pages 2006
Optimization of the number of spacers in a nuclear fuel bundle with respect to flow-induced vibration
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Containment pressure and temperature envelopes for a CANDU reactor equipment environmental qualification
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Concept of core and divertor plasma for fusion DEMO plant at JAERI
Fulltext Access 8 Pages 2006
Conceptual study of ECH/ECCD system for fusion DEMO plant
Fulltext Access 8 Pages 2006
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