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Neutron-irradiation creep of silicon carbide materials beyond the initial transient

  • Takaaki Koyanagi
  • , Yutai Katoh
  • , Kazumi Ozawa
  • , Kazuya Shimoda
  • , Tatsuya Hinoki
  • , Lance L. Snead
  • Oak Ridge National Laboratory
  • Japan Atomic Energy Agency
  • Kyoto University

Research output: Contribution to journalArticlepeer-review

30 Scopus citations

Abstract

Irradiation creep beyond the transient regime was investigated for various silicon carbide (SiC) materials. The materials examined included polycrystalline or monocrystalline high-purity SiC, nanopowder sintered SiC, highly crystalline and near-stoichiometric SiC fibers (including Hi-Nicalon Type S, Tyranno SA3, isotopically-controlled Sylramic and Sylramic-iBN fibers), and a Tyranno SA3 fiber-reinforced SiC matrix composite fabricated through a nano-infiltration transient eutectic phase process. Neutron irradiation experiments for bend stress relaxation tests were conducted at irradiation temperatures ranging from 430 to 1180 °C up to 30 dpa with initial bend stresses of up to ∼1 GPa for the fibers and ∼300 MPa for the other materials. Initial bend stress in the specimens continued to decrease from 1 to 30 dpa. Analysis revealed that (1) the stress exponent of irradiation creep above 1 dpa is approximately unity, (2) the stress normalized creep rate is ∼1 × 10-7 [dpa-1 MPa-1] at 430-750 °C for the range of 1-30 dpa for most polycrystalline SiC materials, and (3) the effects on irradiation creep of initial microstructures - such as grain boundary, crystal orientation, and secondary phases - increase with increasing irradiation temperature.

Original languageEnglish
Pages (from-to)97-111
Number of pages15
JournalJournal of Nuclear Materials
Volume478
DOIs
StatePublished - Sep 1 2016

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