High‐temperature oxidation behavior of the SiC layer of TRISO particles in low‐pressure oxygen

Author:

Bratten Adam1ORCID,Jalan Visharad1,Shi Meng2,Gerczak Tyler3,Wen Haiming14,Doyle Peter5,Zhao Haiyan2,He Xiaoqing67

Affiliation:

1. Department of Materials Science and Engineering Missouri University of Science and Technology Rolla Missouri USA

2. Department of Chemical and Biological Engineering University of Idaho Idaho Falls Idaho USA

3. Particle Fuel Forms Group Oak Ridge National Laboratory Oak Ridge Tennessee USA

4. Department of Nuclear Engineering and Radiation Science Missouri University of Science and Technology Rolla Missouri USA

5. Nuclear Fuel Element Performance Group Oak Ridge National Laboratory Oak Ridge Tennessee USA

6. Electron Microscopy Core Facilities University of Missouri Columbia Missouri USA

7. Department of Mechanical and Aerospace Engineering University of Missouri Columbia Missouri USA

Abstract

AbstractSurrogate tristructural‐isotropic (TRISO)‐coated fuel particles were oxidized in 0.2 kPa O2at 1200–1600°C to examine the behavior of the SiC layer and understand the mechanisms. The thickness and microstructure of the resultant SiO2layers were analyzed using scanning electron microscopy, focused ion beam, and transmission electron microscopy. The majority of the surface comprised smooth, amorphous SiO2with a constant thickness indicative of passive oxidation. The apparent activation energy for oxide growth was 188 ± 8 kJ/mol and consistent across all temperatures in 0.2 kPa O2. The relationship between activation energy and oxidation mechanism is discussed. Raised nodules of porous, crystalline SiO2were dispersed across the surface, suggesting that active oxidation and redeposition occurred in those locations. These nodules were correlated with clusters of nanocrystalline SiC grains, which may facilitate active oxidation. These findings suggest that microstructural inhomogeneities such as irregular grain size influence the oxidation response of the SiC layer of TRISO particles and may influence their accident tolerance.

Funder

Nuclear Energy University Program

Publisher

Wiley

Subject

Materials Chemistry,Ceramics and Composites

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