کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1565662 1514214 2013 8 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Microstructure of TRISO coated particles from the AGR-1 experiment: SiC grain size and grain boundary character
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Microstructure of TRISO coated particles from the AGR-1 experiment: SiC grain size and grain boundary character
چکیده انگلیسی

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) Σ3 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.


► Microstructural differences in the SiC of TRISO fuel types were evaluated.
► Grain size determination performed via EBSD and TEM.
► SiC grain size was consistent for particles produced using H2 gas for fluidization.
► A refined microstructure was found for SiC produced using H2 + Ar for fluidization.
► Differences in GBCD were observed in the different fuel types via EBSD analysis.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 432, Issues 1–3, January 2013, Pages 127–134
نویسندگان
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