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Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux

  • Takaaki Koyanagi
  • , Xunxiang Hu
  • , Christian M. Petrie
  • , Gyanender Singh
  • , Caen Ang
  • , Christian P. Deck
  • , Weon Ju Kim
  • , Daejong Kim
  • , Cédric Sauder
  • , James Braun
  • , Yutai Katoh

Research output: Contribution to journalArticlepeer-review

23 Scopus citations

Abstract

Demonstration of hermetic SiC fiber–reinforced SiC matrix composite cladding under normal operating environments has been identified as one of the most critical feasibility issues for accident-tolerant fuel cladding in light-water reactors. This study provides critical experimental data needed for understanding the effects of irradiation on hermeticity. SiC composite and monolithic tubes were neutron-irradiated to 2 displacements per atom with and without a nominal radial heat flux of 0.6 MW/m2 to produce a simulated in-pile stress state for the normal operation of a light-water reactor. The through-thickness temperature gradient under irradiation results in a gradient in swelling, which causes a significant stress buildup. Such irradiation-induced stress was modeled using a commercial finite element analysis code. The radial heat flux–irradiation synergism was experimentally investigated by constructing a special irradiation capsule and evaluating the helium hermeticity of the specimens. The simulated stress state exhibited a near equi-biaxial tensile axial and hoop stress of ∼150 MPa at the inner surface of the SiC composite tube. This stress level is potentially beyond the matrix cracking stress. Degradation of hermeticity of the SiC composite tubes was observed after irradiation, indicating irradiation-induced cracking, whereas the irradiated monolithic SiC tubes remained hermetic. The results indicate that loss of hermeticity caused by radiation-induced microcracking is a potential issue for SiC composite cladding, depending on the magnitude of the temperature gradients. Coating the outer surface of the cladding was identified as a mitigation strategy that might overcome the cracking issue.

Original languageEnglish
Article number154784
JournalJournal of Nuclear Materials
Volume588
Early online dateOct 15 2023
DOIs
StatePublished - Jan 2024
Externally publishedYes

Keywords

  • Accident tolerant fuel
  • Composite
  • Hermeticity
  • Neutron irradiation
  • SiC

INL Publication Number

  • NA

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