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

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

doi:10.1016/j.jnucmat.2023.154385

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

Journal Article · Sun Mar 12 00:00:00 EST 2023 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2023.154385· OSTI ID:1985403

^[1]; ^[1]; Helmreich, Grant W. ^[2]; Werden, Jesse ^[2]; Gerczak, Tyler J. ^[2]; ^[1]

University of Texas at San Antonio, TX (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

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. Therefore, 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.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725; NE0008798

OSTI ID:: 1985403

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 579; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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