Post irradiation examination of a uranium-zirconium hydride TRIGA fuel element

Post irradiation examination of a uranium-zirconium hydride TRIGA fuel element

Low-enriched (LEU) U-ZrH fuel, with a235U content less than 20% of the total uranium, is being evaluated for possible use in different types of reactors, including space nuclear systems, light water reactors (LWRs) and micro-reactors. As a result, it is beneficial to better understand the macrostruc...

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Bibliographic Details
Main Authors: Dennis Keiser, Jan-Fong Jue, Francine Rice, Eric Woolstenhulme
Format: Article
Language:English
Published: Frontiers Media S.A. 2023-03-01
Series:Frontiers in Energy Research
Subjects:
TRIGA reactor
U-ZrH
micro-reactors
characterization
post irradiation examination
Online Access:https://www.frontiersin.org/articles/10.3389/fenrg.2023.1106601/full

Internet

https://www.frontiersin.org/articles/10.3389/fenrg.2023.1106601/full

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