Irradiation - High heat flux synergism in silicon carbide-based fuel claddings for light water reactors

Yutai Katoh, Kurt A. Terrani, Takaaki Koyanagi, Christian M. Petrie, Gyanender Singh, Lance L. Snead, Christian Deck

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

2 Scopus citations

Abstract

Silicon carbide-based fuel cladding for light water reactors is anticipated to develop a unique stress state as a combined result from the high radial heat flux and irradiation-induced swelling assisted by thermal conductivity decrease. In order to verify the multi-physics analysis of this unique stress state, a novel experiment capturing the synergism of a high radiation field and a high radial heat flux in tubular silicon carbide specimens had been designed and implemented in the High Flux Isotope Reactor, Oak Ridge National Laboratory. In this experiment, small diameter tube test specimens made of monolithic or composite silicon carbide were irradiated to a dose of ∼2x1025 n/m2 (E > 0.1 MeV) under a radial heat flux of ∼0.6 MW/m2 while the outer surface temperature was maintained at a target temperature of ∼300°C achieving a steep temperature gradient through the cladding wall thickness. In this paper, the technical planning and execution of the experiment are discussed.

Original languageEnglish
Title of host publicationTop Fuel 2016
Subtitle of host publicationLWR Fuels with Enhanced Safety and Performance
PublisherAmerican Nuclear Society
Pages823-831
Number of pages9
ISBN (Electronic)9780894487309
StatePublished - 2016
EventTop Fuel 2016: LWR Fuels with Enhanced Safety and Performance - Boise, United States
Duration: Sep 11 2016Sep 15 2016

Publication series

NameTop Fuel 2016: LWR Fuels with Enhanced Safety and Performance

Conference

ConferenceTop Fuel 2016: LWR Fuels with Enhanced Safety and Performance
Country/TerritoryUnited States
CityBoise
Period09/11/1609/15/16

Funding

This work is supported by the U.S. Department of Energy (DOE), Office of Nuclear Energy for the Fuel Cycle Research & Development program under contact DE-AC05-00OR22725 with Oak Ridge National Laboratories managed by UT-Battelle, LLC. Research is also supported in part by High Flux Isotope Reactor, which is sponsored by the Office of Basic Energy Sciences, U.S. DOE. The authors are grateful to C. Ang for his valuable comments.

FundersFunder number
U.S. DOE
UT-Battelle
U.S. Department of Energy
Office of Nuclear EnergyDE-AC05-00OR22725
Basic Energy Sciences
Oak Ridge National Laboratory

    Keywords

    • Accident tolerant fuels
    • Ceramic matrix composites
    • High heat flux
    • Irradiation effects
    • Silicon carbide

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