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Paper Titles
Preface
Uranium Diffusion in Metals Used in Nuclear Facilities - A New Approach
p.3
Relating Diffusion Couple Experiment Results to Observed As-Fabricated Microstructures in Low-Enriched U-10wt.% Mo Monolithic Fuel Plates
p.18
Correlations for Interaction Layer Growth in U-Mo/Al Dispersion Fuels
p.29
Fast Anion Defect Recovery through Superionic-Type Hopping Displacements in UO2 Following Radiation
p.43
Defect Chemistry and Basic Properties of Non-Stoichiometric PuO2
p.57
MFPR Model Parameters of the Athermal Irradiation-Induced Transport in Nuclear Fuels
p.71
Oxygen Chemical Diffusion Coefficients of (U, Pu)O2-x
p.84
Irradiation Creep of Uranium-Plutonium Nitride Fuel and Serviceability of Fuel Element
p.91

Preface

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Periodical:

Defect and Diffusion Forum (Volume 375)

Online since:

May 2017

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