Location
University of Nevada, Las Vegas
Start Date
16-4-2011 10:50 AM
End Date
16-4-2011 11:10 AM
Description
Zirconium carbide has been proposed as a coating layer for next generation (“TRISO”) nuclear fuel, and is intended as a diffusion barrier to contain fission products (e.g., Pd). To study the chemical interaction between Pd and ZrC, their interface was investigated using X-ray Photoelectron Spectroscopy (XPS). Pd was step-wise deposited onto ZrC in ultra-high vacuum, and the chemical interaction at the interface was monitored, also as a function of temperature (up to 1000 C). In the presentation, details of the chemical interaction and changes in the chemical environment of Pd and their relevance for TRISO fuel will be discussed.
Keywords
Chemical reactions; Diffusion coatings; Nuclear fuels; Palladium; Zirconium carbide
Disciplines
Atomic, Molecular and Optical Physics | Nuclear | Oil, Gas, and Energy | Physics
Language
English
Included in
Atomic, Molecular and Optical Physics Commons, Nuclear Commons, Oil, Gas, and Energy Commons
Oral presentation: Next generation nuclear fuels
University of Nevada, Las Vegas
Zirconium carbide has been proposed as a coating layer for next generation (“TRISO”) nuclear fuel, and is intended as a diffusion barrier to contain fission products (e.g., Pd). To study the chemical interaction between Pd and ZrC, their interface was investigated using X-ray Photoelectron Spectroscopy (XPS). Pd was step-wise deposited onto ZrC in ultra-high vacuum, and the chemical interaction at the interface was monitored, also as a function of temperature (up to 1000 C). In the presentation, details of the chemical interaction and changes in the chemical environment of Pd and their relevance for TRISO fuel will be discussed.
Comments
Poster co-authors: D. Hanks, S. Krause, T. Hofmann, M. Weir, Y. Zhang, C. Heske, University of Nevada, Las Vegas
Presentation not available