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

Uranium Diffusion in Metals Used in Nuclear Facilities - A New Approach

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Abstract:

Diffusion at infinite dilution of U in metals, with particular emphasis in those used in nuclear facilities, is revisited. Early works present some particularities such as activation enthalpies lower than the vacancy formation enthalpy in the matrix, large differences with self-diffusion in the base material, up to four orders of magnitude differences between measurements performed by different authors in similar temperature ranges, etc. In particular U self-diffusion was qualified as abnormal when compared with other metals. Recent studies by means of α-spectrometry reveal a normal behaviour: activation enthalpies and pre-exponential factors similar to the self-diffusion one and diffusion coefficient values in the same order of magnitude than self-diffusion. The possible influence of short circuits, impurities and/or uncertainties in the techniques used in the early works is discussed in order to explain the differences obtained.

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Periodical:

Defect and Diffusion Forum (Volume 375)

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3-17

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https://doi.org/10.4028/www.scientific.net/DDF.375.3

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May 2017

Authors:

Rodolfo A. Pérez*

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Diffusion, Nuclear Materials, Uranium, α-Spectrometry

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