Defects and Diffusion Phenomena in Materials for Nuclear Technologies

Erscheinungsjahr 2017
ISBN: 978-3-0357-1206-3
Verlag: Trans Tech Publications

Buch, Englisch, 194 Seiten, Format (B × H): 170 mm x 240 mm, Gewicht: 470 g

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.

Autoren/Hrsg.

Starikov, Sergey

Smirnova, Daria

Lunev, Artem

Fachgebiete

• Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Materialwissenschaft: Elektronik, Optik
• Technische Wissenschaften Energietechnik | Elektrotechnik Atomenergietechnik

Inhaltsverzeichnis

Preface
Chapter 1: Uranium Alloys and Uranium in Metals
Uranium Diffusion in Metals Used in Nuclear Facilities - A New Approach
Relating Diffusion Couple Experiment Results to Observed As-Fabricated Microstructures in Low-Enriched U-10wt.% Mo Monolithic Fuel Plates
Correlations for Interaction Layer Growth in U-Mo/Al Dispersion Fuels
Chapter 2: Oxide and Nitride Nuclear Fuels
Fast Anion Defect Recovery through Superionic-Type Hopping Displacements in UO2 Following Radiation
Defect Chemistry and Basic Properties of Non-Stoichiometric PuO2
MFPR Model Parameters of the Athermal Irradiation-Induced Transport in Nuclear Fuels
Oxygen Chemical Diffusion Coefficients of (U, Pu)O2-x
Irradiation Creep of Uranium-Plutonium Nitride Fuel and Serviceability of Fuel Element
Multiscale Modeling of Uranium Mononitride: Point Defects Diffusion, Self-Diffusion, Phase Composition
On Morphological and Microstructural Changes in Uranium Dioxide Powder during Binder-Free Hot Pressing
Chapter 3: Changes in Properties of Steels at Thermal and Radiation Impacts
Kinetics of Phosphorus Segregation in the Grain Boundaries of VVER-1000 Pressure Vessel Steels
Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor
Effective Atomic Displacements in Fe-9at.%Cr Alloy
Chapter 4: Properties of Defects in Non-Ferrous Metals
Molecular Dynamics Simulations of the Excess Vacancy Evolution in V and V-4Ti
Study of Niobium Diffusion and Clusterization in hcp Zr-Nb Dilute Alloys
The Investigation of Dislocation Behaviour in Molybdenum Using Molecular Dynamics

Über Autor(innen)

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