Starikov / Smirnova / Lunev | Defects and Diffusion Phenomena in Materials for Nuclear Technologies | Sonstiges | 978-3-0357-2206-2 | sack.de

Sonstiges, Englisch, Band Volume 375, 194 Seiten, Format (B × H): 125 mm x 142 mm, Gewicht: 200 g

Reihe: Defect and Diffusion Forum

Starikov / Smirnova / Lunev

Defects and Diffusion Phenomena in Materials for Nuclear Technologies


Erscheinungsjahr 2017
ISBN: 978-3-0357-2206-2
Verlag: Trans Tech Publications

Sonstiges, Englisch, Band Volume 375, 194 Seiten, Format (B × H): 125 mm x 142 mm, Gewicht: 200 g

Reihe: Defect and Diffusion Forum

ISBN: 978-3-0357-2206-2
Verlag: Trans Tech Publications


Defects and diffusion are key concepts at the description of nuclear materials behavior at thermal and radiation impacts. The evolution of various defects (such as point defects, dislocations, grain boundaries) determines changes of the materials properties under operating conditions. The present issue contains new and relevant data about the diffusion and defects in nuclear fuel (uranium alloys, oxide and nitride fuel) and structural materials (steel and non-ferrous metals). We hope that this special issue will be useful for researchers and engineers working in the field of material science and nuclear engineering. We wish to thank the authors for their contributions to this special issue and reviewers for their cooperation and efforts to prepare and evaluate the manuscripts.
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Weitere Infos & Material


Uranium Diffusion in Metals Used in Nuclear Facilities - A New ApproachRelating Diffusion Couple Experiment Results to Observed As-Fabricated Microstructures in Low-Enriched U-10wt.% Mo Monolithic Fuel PlatesCorrelations for Interaction Layer Growth in U-Mo/Al Dispersion FuelsFast Anion Defect Recovery through Superionic-Type Hopping Displacements in UO2 Following RadiationDefect Chemistry and Basic Properties of Non-Stoichiometric PuO2MFPR Model Parameters of the Athermal Irradiation-Induced Transport in Nuclear FuelsOxygen Chemical Diffusion Coefficients of (U, Pu)O2-xIrradiation Creep of Uranium-Plutonium Nitride Fuel and Serviceability of Fuel ElementMultiscale Modeling of Uranium Mononitride: Point Defects Diffusion, Self-Diffusion, Phase CompositionOn Morphological and Microstructural Changes in Uranium Dioxide Powder during Binder-Free Hot PressingKinetics of Phosphorus Segregation in the Grain Boundaries of VVER-1000 Pressure Vessel SteelsEffect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 ReactorEffective Atomic Displacements in Fe-9at.%Cr AlloyMolecular Dynamics Simulations of the Excess Vacancy Evolution in V and V-4TiStudy of Niobium Diffusion and Clusterization in hcp Zr-Nb Dilute AlloysThe Investigation of Dislocation Behaviour in Molybdenum Using Molecular Dynamics


Eds. Dr. Sergey Starikov, Dr. Daria Smirnova and Dr. Artem Lunev


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