Characterization of fluidized bed chemical vapor deposition ZrC coatings on PyC/YSZ kernels deposited under differing conditions
Source abstract
Abstract
Coated fuel particle architectures with ZrC coatings are candidate fuels for advanced power reactors and space nuclear propulsion (SNP) concepts. Owing to its relevance to SNP, the composition, microstructure, and mechanical properties of eight ZrC coatings prepared by fluidized bed chemical vapor deposition were evaluated. Evaluation by SEM and EBSD showed that all grains were columnar. Across the various examined samples, minor axis diameters varied between 0.3 and 1.1 μm, and major axis diameters varied between 0.4 and 2.3 μm. Major and minor diameters increased with thickness particularly at higher deposition temperatures in which the major grain axis (from an ellipse fit to the grain shape) increased by 2.5 μm over the entire coating. Coatings with higher reactive gas flows and Zr/C concentrations closer to 1 were observed to contain nanocrystalline graphite deposits. Reactive gas flow doubling led to increases in coating thickness from around 10–15 μm to around 22–27 μm.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Advanced ceramic materials synthesis · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (40)
Show source-provided references
1. Associations of Pd, U and Ag in the SiC layer of neutron-irradiated TRISO fuel10.1016/j.jnucmat.2015.02.010 ↗
2. Electron microscopy study of Pd, Ag, and Cs in carbon areas in the locally corroded SiC layer in a neutron-irradiated TRISO fuel particle10.1016/j.jeurceramsoc.2018.05.003 ↗
3. Irradiation experiment on ZrC-coated fuel particles for high-temperature gas-cooled reactors10.13182/NT00-A3093 ↗
4. Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800°C safety testing10.1016/j.jnucmat.2020.152453 ↗
5. SiC layer microstructure in AGR-1 and AGR-2 TRISO fuel particles and the influence of its variation on the effective diffusion of key fission products10.1016/j.jnucmat.2016.08.011 ↗
6. Handbook of SiC properties for fuel performance modeling10.1016/j.jnucmat.2007.05.016 ↗
7. Properties of zirconium carbide for nuclear fuel applications10.1016/j.jnucmat.2013.05.037 ↗
8. Massalski · 1986
9. On the stoichiometry of zirconium carbide10.1038/s41598-020-63037-0 ↗
10. Characterization of zirconium carbides using electron microscopy, optical anisotropy, Auger depth profiles, X-ray diffraction, and electron density calculated by charge flipping method10.1016/j.jssc.2012.04.047 ↗
11. Elastic properties of zirconium carbide10.1002/pssb.19660180150 ↗
12. Low-Temperature Elastic Properties of ZrC and TiC10.1063/1.1707923 ↗
13. Microstructure and mechanical properties of heat-treated and neutron irradiated TRISO-ZrC coatings10.1016/j.jnucmat.2015.04.026 ↗
14. Measurement of the fracture properties of brittle solids by hertzian indentation10.1016/0001-6160(78)90087-1 ↗
15. The preparation and characteristics of ZrC and TaC single crystals using an r.f. floating-zone process10.1007/BF02402865 ↗
16. Hardness and elastic properties of Ti(CxN1−x), Zr(CxN1−x) and Hf(CxN1−x)10.1016/S0925-8388(00)01057-4 ↗
17. Deposition Mechanism for Chemical Vapor Deposition of Zirconium Carbide Coatings
18. Coating microspheres with zirconium carbide-carbon alloy by iodide process10.1080/18811248.1974.9730657 ↗
19. Co-deposition of zirconium with carbon by the bromide process10.1016/0022-5088(76)90133-8 ↗
20. Fray · 2011
21. Miller · 2009
22. Samarium and europium beta”-alumina derivatives characterized by XPS10.1116/1.4972828 ↗
23. Microstructure of TRISO coated particles from the AGR-1 experiment: SiC grain size and grain boundary character10.1016/j.jnucmat.2012.08.052 ↗
24. Quantification of silicon carbide grain structure in TRISO fuel by BSE image analysis10.1016/j.jnucmat.2020.152075 ↗
25. Damage production in carbide single crystals irradiated with MeV heavy ions10.1016/j.nimb.2012.11.091 ↗
26. Raman investigation of ion irradiated TiC and ZrC10.1016/j.nimb.2019.02.012 ↗
27. Zirconia growth on zirconium carbide single crystals by oxidation10.1016/j.surfcoat.2004.05.035 ↗
28. Raman microspectroscopy of soot and related carbonaceous materials: Spectral analysis and structural information10.1016/j.carbon.2005.02.018 ↗
29. Raman Spectroscopy of Amorphous, Nanostructured, Diamond-like Carbon, and Nanodiamond10.1098/rsta.2004.1452 ↗
30. Microstructure evolution of a ZrC coating layer in TRISO particles during high-temperature annealing10.1016/j.jnucmat.2016.06.024 ↗
31. Preparation and characterization of zirconium carbide coating on coated fuel particles
32. Understanding the CVD process of (Si)–B–C ceramics through FTIR spectroscopy gas phase analysis10.1016/j.surfcoat.2007.01.039 ↗
33. Temperature dependency of the LPCVD growth of ZrC with the ZrCl4–CH4–H2 system10.1016/j.surfcoat.2008.09.009 ↗
34. Thermodynamics of the production of condensed phases in the chemical vapor deposition of ZrC in the ZrCl4–CH4–H2–Ar system10.1016/j.tsf.2014.03.023 ↗
35. Laidler · 2002
36. Raman spectroscopy on amorphous carbon films10.1063/1.362745 ↗
37. Raman spectroscopy of hydrogenated amorphous carbons10.1103/PhysRevB.72.085401 ↗
38. Formation and characterization of carbon at the ZrCZrO2 interface by oxidation of ZrC single crystals10.1016/S0008-6223(98)00087-6 ↗
39. Large grain polycrystalline Si thin films by nucleation-controlled chemical vapor deposition using intermittent source gas supply10.1016/j.tsf.2005.01.029 ↗
40. Influence of SiC grain boundary character on fission product transport in irradiated TRISO fuel10.1016/j.jnucmat.2016.01.040 ↗