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D. Schappel

Oak Ridge National Laboratory

6

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29

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Oxidation of 3D‐printed SiC in air and steam environments

2021 Journal of the American Ceramic Society
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Architecture and properties of TCR fuel form

2021 Journal of Nuclear Materials
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Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON1

2020 Journal of Nuclear Materials
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Fabrication of yttrium hydride for high-temperature moderator application

2020 Journal of Nuclear Materials
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Characteristics of Fuel Articles for Irradiation Testing in TREAT and MITR

2020
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Key Material Properties for Thermo-Structural Analysis of TCR Core Components

2019
- D. Schappel
- Kurt A. Terrani
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