Microstructural analysis of tristructural isotropic particles in high-temperature steam mixed gas atmospheres

Katherine I. Montoya, Brian A. Brigham, Grant Helmreich, Jesse Werden, Tyler J. Gerczak, Elizabeth S. Sooby

Research output: Contribution to journalArticlepeer-review

2 Scopus citations

Abstract

High-temperature gas-cooled reactors (HTGRs) use tristructural isotropic (TRISO) particles embedded in a graphitic matrix material to form the integral fuel element. Potential off-normal reactor conditions for HTGRs include steam ingress with temperatures above 1,000 °C. Fuel element exposure to steam can cause the graphitic matrix material to evolve, forming an atmosphere composed of oxidants and oxidation products and potentially exposing the TRISO particles to these conditions. Investigating the oxidation response of TRISO particles exposed to a mixed gas atmosphere will provide insight into the stability under off-normal conditions. In this study, surrogate TRISO particles were exposed to high temperatures (T = 1,200 °C) in flowing steam (3% < pH2O < 21%) and CO (pCO < 1%) to determine the oxidation behavior of the SiC layer when exposed to various mixed gas atmospheres. Scanning electron microscopy, x-ray diffraction, and focused ion beam milling was used to determine the impact of CO and steam on the oxidation behavior of the SiC layer. The data presented demonstrates how the SiC layer showed strong oxidation resistance due to limited SiO2 growth and maintained its structural integrity under these off-normal conditions.

Original languageEnglish
Article number154385
JournalJournal of Nuclear Materials
Volume579
DOIs
StatePublished - Jun 2023

Funding

FIB microscopic measurements were taken in the Low Activation Materials and Development and Analysis facilities at Oak Ridge National Laboratory. Ion milling cross-sectioning was performed at the University of Texas at San Antonio Kleberg Advanced Microscopy Center with the support of Hitachi High-Tech. Materials for this work were provided by the US Department of Energy's (DOE's) Office of Nuclear Energy Advanced Reactor Technologies as part of the Advanced Gas Reactor Fuel Development and Qualification (AGR) program. This material is based upon work supported by the U.S. Department of Energy, Office of Nuclear Energy AGR Program, ORISE H.E.R.E Program, and Department of Energy Nuclear Energy University Programs. Award Number: DE-NE0008798. FIB microscopic measurements were taken in the Low Activation Materials and Development and Analysis facilities at Oak Ridge National Laboratory. Ion milling cross-sectioning was performed at the University of Texas at San Antonio Kleberg Advanced Microscopy Center with the support of Hitachi High-Tech. Materials for this work were provided by the US Department of Energy's (DOE's) Office of Nuclear Energy Advanced Reactor Technologies as part of the Advanced Gas Reactor Fuel Development and Qualification (AGR) program. This material is based upon work supported by the U.S. Department of Energy , Office of Nuclear Energy AGR Program, ORISE H.E.R.E Program, and Department of Energy Nuclear Energy University Programs. Award Number: DE-NE0008798.

Keywords

  • High-temperature gas reactor
  • Ion milling techniques
  • Nuclear fuel
  • Silicon carbide
  • Steam oxidation
  • TRISO

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