期刊
JOURNAL OF NUCLEAR MATERIALS
卷 432, 期 1-3, 页码 127-134出版社
ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2012.08.052
关键词
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资金
- US Department of Energy through Nuclear Energy University Program (NEUP)
- Idaho National Laboratory (INL)
- US Department of Energy Advanced Gas Reactor Fuel Development and Qualification Program
Pre-irradiation SiC microstructures in tristructural-isotropic (TRISO) coated fuel particles from the Advanced Gas Reactor Fuel Development and Qualification program's first irradiation experiment (AGR-1) were quantitatively characterized using electron backscatter diffraction (EBSD) and transmission electron microscopy (TEM). From EBSD, it was determined that only the cubic polymorph of as-deposited SiC was present and the SiC had a high fraction of coincident site lattice (CSL) Sigma 3 grain boundaries. Additionally, the local area misorientation (LAM), which is a qualitative measurement of strain in the SiC lattice, was mapped for each sample fuel variant. The morphology of the SiC/IPyC interfaces were characterized by TEM following site-specific focused ion beam (FIB) specimen preparation. It was determined that the SiC layer had a heavily faulted microstructure typical of chemical vapor deposition (CVD) SiC and that the average grain diameter increased radially from the SiC/IPyC interface for the samples manufactured with similar CVD conditions, while the last sample showed a nearly constant grain size across the layer. (c) 2012 Elsevier B.V. All rights reserved.
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