Determination of preferential binder oxidation in HTGR matrix material subjected to high temperature steam

Katherine I. Montoya, Cole J. Moczygemba, Brian A. Brigham, Tyler L. Spano, Anne A. Campbell, Tyler J. Gerczak, Elizabeth S. Sooby

Research output: Contribution to journalArticlepeer-review

6 Scopus citations

Abstract

Graphitic matrix material encapsulates tristructural isotropic (TRISO) coated fuel particles and is a structural component for both pebble and cylindrical fuel compacts in high temperature gas reactor (HTGR) designs. In an off-normal event involving steam exposure, the matrix material is exposed to oxidants, leading to degradation of the fuel compact and subsequent exposure of the TRISO particle fuel to oxidizing species. This study presents microstructural characterization of matrix material after exposure to high temperature (1200°C), 48 kPa steam in which the evolved microstructure demonstrated nonuniform degradation. Subsequent Raman spectroscopy determined the nature of the remaining material post-exposure. The electron microscopy characterization suggests and Raman spectroscopic analysis confirms, under off-normal conditions, the carbonized phenolic resin binder is preferentially oxidized ahead of the graphite flake filler and is responsible for the nonuniform degradation and enhanced depth of attack.

Original languageEnglish
Article number152674
JournalJournal of Nuclear Materials
Volume544
DOIs
StatePublished - Feb 2021

Funding

This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE 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 ). Raman Spectroscopic measurements were made in Process & Materials Characterization Group facilities at ORNL. Materials for this work were provided by the US Department of Energy'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.

FundersFunder number
AGR
Advanced Gas Reactor Fuel Development and Qualification
DOE Office of Nuclear EnergyDE-NE0008798
Office of Nuclear Energy AGR Program
US Department of Energy
U.S. Department of Energy
Office of Nuclear Reactor Deployment

    Keywords

    • Graphitic matrix material
    • High Temperature Gas Reactors
    • Raman Spectroscopy
    • Steam oxidation

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