Irradiation stability and thermo-mechanical properties of NITE-SiC irradiated to 10 dpa

Kurt A. Terrani, Caen Ang, Lance L. Snead, Yutai Katoh

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31 Scopus citations

Abstract

Five variants of nano-infiltration transient eutectic (NITE) SiC were prepared using nanopowder feedstock and sintering additive contents of <10 wt%. The dense monolithic materials were subsequently irradiated to 2 and 10 dpa in a mixed spectrum fission reactor at nominally 400 and 700 °C. The evolution in swelling, strength, and thermal conductivity of these materials were examined after irradiation, where in all cases properties saturated at < 2dpa, without appreciable change for further irradiation to 10 dpa. Swelling behavior appeared similar to high-purity chemical vapor deposition (CVD) SiC within measurement uncertainty. The strength roughly doubled after irradiation. Thermal resistivity increase as a result of irradiation was ∼20% higher when compared to CVD-SiC.

Original languageEnglish
Pages (from-to)242-247
Number of pages6
JournalJournal of Nuclear Materials
Volume499
DOIs
StatePublished - Feb 2018

Funding

This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). James Kiggans, Fred Montgomery, and Chung-Hao Shih assisted in material processing and capsule assembly. Michael McAlister and Wallace Porter contributed to the post-irradiation examination data collection. Anne Campbell provided valuable comments on the manuscript. The work presented in this paper was supported by the Advanced Fuels Campaign of the Nuclear Technology R&D Program of the Office of Nuclear Energy . A portion of this research used resources at the High Flux Isotope Reactor, a DOE Office of Science User Facility operated by the Oak Ridge National Laboratory.

FundersFunder number
U.S. Department of Energy
Office of Nuclear Energy

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