"Micromechanical response of SiC-OPyC layers in TRISO fuel particles" Erik G. Herbert, Danny P. Schappel, Christian M. Petrie, Andrew T. Nelson, Tyler J. Gerczak, Katherine I. Montoya, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2025.155654 | |
"Raman spectroscopy of uranium nitride kernels" Liangbo Liang, J. Matthew Kurley, Katherine Montoya, William F. Cureton, Rachel Siebert, Rodney D. Hunt, Nathan Capps, Andrew T. Nelson, Eddie Lopez-Honorato, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155050 | |
"Evaluation of Radiography for TRISO Buffer Layer Density Measurement" Katherine Montoya, J. Jones, John Hunn, Grant Helmreich, [2024] · DOI: 10.2172/2429818 | |
"Evaluation of XCT for Matrix Density Measurement of Particle Fuel Forms" Katherine Montoya, John Hunn, Grant Helmreich, [2024] · DOI: 10.2172/2438889 | |
"Raman spectroscopy of zirconium hydride" Liangbo Liang, Yong Yan, Katherine Montoya, Nathan Capps, Eddie Lopez-Honorato, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.154988 | |
"Quality Control Methods for Measurement of UCO Kernel Composition and SiC Microstructure" Katherine Montoya, William Cureton, Eddie Lopez-Honorato, Tyler Gerczak, John Hunn, Grant Helmreich, [2023] · DOI: 10.2172/2311297 | |
"Microstructural analysis of tristructural isotropic particles in high-temperature steam mixed gas atmospheres" Brian A. Brigham, Grant Helmreich, Jesse Werden, Tyler J. Gerczak, Elizabeth S. Sooby, Katherine I. Montoya, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154385 | |
"Semantic Segmentation of Micrographs for Nuclear Fuel Analysis and Degradation Quantification" Katherine I. Montoya, David Patrick, Jordan Stone, Daniel Mohanadhas, Elizabeth S. Sooby, Amanda S. Fernandez, Christopher Snyder, [2023] IEEE Access · DOI: 10.1109/access.2023.3326074 | |
"Oxidation of 3D‐printed SiC in air and steam environments"
Pádraigín Stack, Danny Schappel, Katherine Montoya, Peter Mouche, Elizabeth Sooby, Kurt Terrani, Kenneth Kane,
[2021]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.17632
The high‐temperature oxidation of additively manufactured and chemically vapor infiltrated (3D‐printed SiC) has been compared to chemical vapor deposited (CVD) SiC. 100‐h isothermal exposures were conducted at 1425° and 1300°C at 1 atm under both dry air and steam environments. A SiC reaction tube was utilized to reduce silica volatility. After steam oxidation at 1425° and 1300°C, on the 3D‐printed SiC surface, which was intrinsically rougher than the CVD surface, scales were 70%–90% thicker at the convex regions compared to concave/flat regions. In the convex regions, large cracks perpendicular to the oxidizing interface were observed. After dry air oxidation, scale thicknesses were comparable between 3D‐printed SiC and CVD SiC, regardless of geometry. Finite element modeling, conducted to elucidate the relationship between SiC geometry and ß‐ to α‐cristobalite transformation stress, determined cristobalite transformation tensile stresses to be on the order of 103 MPa during cool down, assuming a 6 vol% reduction. Compared to flat SiC substrates, tensile transformation stresses were elevated at concave regions and relaxed at convex regions. Combined with specimen mass gain (accounting for the rougher surface) of 3D‐printed SiC being 15%–32% higher for 3D‐printed SiC after 1300°C and 1425°C steam oxidation, the work presented concludes that the increased oxidation of 3D‐printed SiC is primarily caused by tensile hoop stresses driven by oxidation volume expansion. Lastly, the efficacy of the 3D‐printing method is demonstrated through the production of tristructural isotropic imbedded 3D‐printed SiC fuel forms. |
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"Oxidation of 3D-printed SiC in air and steam environments"
Pádraigín Stack, Danny Schappel, Katherine Montoya, Peter Mouche, Elizabeth Sooby, Kurt Terrani, Kenneth Kane,
[2021]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.17632
· EID: 2-s2.0-85099464562
· ISSN: 1551-2916
The high‐temperature oxidation of additively manufactured and chemically vapor infiltrated (3D‐printed SiC) has been compared to chemical vapor deposited (CVD) SiC. 100‐h isothermal exposures were conducted at 1425° and 1300°C at 1 atm under both dry air and steam environments. A SiC reaction tube was utilized to reduce silica volatility. After steam oxidation at 1425° and 1300°C, on the 3D‐printed SiC surface, which was intrinsically rougher than the CVD surface, scales were 70%–90% thicker at the convex regions compared to concave/flat regions. In the convex regions, large cracks perpendicular to the oxidizing interface were observed. After dry air oxidation, scale thicknesses were comparable between 3D‐printed SiC and CVD SiC, regardless of geometry. Finite element modeling, conducted to elucidate the relationship between SiC geometry and ß‐ to α‐cristobalite transformation stress, determined cristobalite transformation tensile stresses to be on the order of 103 MPa during cool down, assuming a 6 vol% reduction. Compared to flat SiC substrates, tensile transformation stresses were elevated at concave regions and relaxed at convex regions. Combined with specimen mass gain (accounting for the rougher surface) of 3D‐printed SiC being 15%–32% higher for 3D‐printed SiC after 1300°C and 1425°C steam oxidation, the work presented concludes that the increased oxidation of 3D‐printed SiC is primarily caused by tensile hoop stresses driven by oxidation volume expansion. Lastly, the efficacy of the 3D‐printing method is demonstrated through the production of tristructural isotropic imbedded 3D‐printed SiC fuel forms. |
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"Determination of preferential binder oxidation in HTGR matrix material subjected to high temperature steam" Cole J. Moczygemba, Brian A. Brigham, Tyler L. Spano, Anne A. Campbell, Tyler J. Gerczak, Elizabeth S. Sooby, Katherine I. Montoya, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152674 | |
"Determination of oxidation rates and volatile oxidation products for HTGR graphite matrix material exposed to steam atmospheres" Katherine I. Montoya, Tyler J. Gerczak, Elizabeth S. Sooby, Brian A. Brigham, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153256 · EID: 2-s2.0-85114777455 · ISSN: 0022-3115 | |
"Oxidation of the SiC layer of tristructural-isotropic particles in high-temperature mixed gas atmospheres" [2021] Transactions of the American Nuclear Society · DOI: 10.13182/t124-35197 · EID: 2-s2.0-85117921483 · ISSN: 0003-018X | |
"Analysis of graphite matrix kinetics and burn-off products under off-normal high-temperature gas-cooled reactors conditions" T. Gerczak, K. Montoya, E. Wood, B. Brigham, [2020] Transactions of the American Nuclear Society · DOI: 10.13182/t122-32580 · EID: 2-s2.0-85092159638 · ISSN: 0003-018X | |
"Microstructural analysis of the SiC layer of tristructural-isotropic particles in high-temperature steam atmospheres" T. Gerczak, K. Montoya, E. Wood, B. Brigham, [2020] Transactions of the American Nuclear Society · DOI: 10.13182/t122-32591 · EID: 2-s2.0-85092200694 · ISSN: 0003-018X | |
"Analysis of matrix graphite degradation under varied oxidizing atmospheres" T. Gerczak, K. Montoya, E. Wood, B. Brigham, [2019] Transactions of the American Nuclear Society · DOI: 10.13182/t31165 · EID: 2-s2.0-85092165147 · ISSN: 0003-018X | |
Source: ORCID/CrossRef using DOI |
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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