Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Production and characterization of TRISO fuel particles with multilayered SiC

Journal Article · · Journal of Nuclear Materials
 [1];  [1];  [2];  [3];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of California, Berkeley, CA (United States)
  3. Univ. of Tennessee, Knoxville, TN (United States)

Three distinct composite architectures of silicon carbide (SiC) and pyrocarbon (PyC) were incorporated into the SiC coating layer of tristructural-isotropic (TRISO) nuclear fuel particles. The composite architectures are meant to increase the resistance of SiC coating layer to cracking and fission product attack during operation and accident scenarios. All composite layers were produced using the existing fluidized bed chemical vapor deposition apparatus that is used for production of TRISO fuel particles without modifications. Detailed characterization of the composite microstructure was carried out via optical and electron microscopy. Nano-indentation examination confirms that mechanical properties of the SiC phase was not affected in the composite architectures, however, the resistance to crack propagation in this coating layer was greatly increased in all cases when compared to the reference monolithic coating layer. The stress required to debond the SiC-inner PyC interface in the reference TRISO particles was determined to be ~1 GPa using micropillar compression technique. The high strength may explain the ease of crack propagation from the inner PyC to SiC in the reference design. In the composite architectures, the means of crack deflection were effectively incorporated at this interface. Lastly, finite element analysis of stress evolution in the fuel particles during normal operation with the reference and composite SiC coating layer architectures did not show any significant differences between the variants.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1491324
Alternate ID(s):
OSTI ID: 22886837
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 515; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

Similar Records

Shear Properties at the PyC/SiC Interface of TRISO-Coating
Journal Article · Sun Dec 31 23:00:00 EST 2006 · Journal of Nuclear Materials · OSTI ID:966071

Micromechanical Properties of the SiC and Pyrolytic Carbon Layers in Tristructural-Isotropic Coated Particles
Conference · Wed Oct 01 00:00:00 EDT 2025 · OSTI ID:3009473

Progress on Fabrication of Planar Diffusion Couples with Representative TRISO PyC/SiC Microstructure
Technical Report · Sun Oct 01 00:00:00 EDT 2017 · OSTI ID:1410914