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In-pile tensile creep of chemical vapor deposited silicon carbide at 300 °C

  • Takaaki Koyanagi
  • , Kurt Terrani
  • , Torill Karlsen
  • , Vendi Andersson
  • , David Sprouster
  • , Lynne Ecker
  • , Yutai Katoh

Research output: Contribution to journalArticlepeer-review

4 Scopus citations

Abstract

Irradiation-induced creep is one of the key material properties considered in designing structural components for nuclear reactors. This paper presents results for in situ irradiation-induced creep of chemical vapor–deposited 3C silicon carbide studied by instrumented irradiation in the Halden reactor in Norway. The specimens examined were irradiated at 300 °C and up to 2.5 × 1024 n/m2 (E > 0.1 MeV) under uniaxial tensile stress of <5 or 100 MPa. Irradiation-induced creep strain was defined as the differential time-dependent strain between the two specimens. Based on the dimensional inspections before and after irradiation, an axial primary creep strain of 0.06% was obtained at the end of irradiation. The lattice constant precisely determined from high-energy x-ray diffraction analysis showed a lattice expansion roughly accounting for the primary irradiation creep strain. Analysis of data from this and previous studies indicates that creep strain is significantly dependent on at least one of the experimental conditions, such as loading mode, neutron spectrum/flux, and material grade.

Original languageEnglish
Pages (from-to)63-70
Number of pages8
JournalJournal of Nuclear Materials
Volume521
DOIs
StatePublished - Aug 1 2019

Keywords

  • Irradiation creep
  • Microstructure
  • Neutron irradiation
  • SiC

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