Micromechanical response of SiC-OPyC layers in TRISO fuel particles

• Impact testing of the SiC layer of surrogate TRISO to explore crack propagation . • Determination of preferential crack behavior of the SiC layer of TRISO fuel. • Modeling produced stress state profiles of TRISO fuel at various temperatures. Tristructural isotropic (TRISO)–coated particle fuel is a proposed fuel for multiple advanced reactor concepts. The performance of the particle depends on whether the silicon carbide (SiC) layer remains intact to prevent the release of metallic and gaseous fission products. Mechanical fracture of the SiC layer is a potential failure mode under various fuel configurations and operating environments, including the potential transmission of matrix-originating cracks through TRISO particles. This study uses instrumented indentation techniques on cross-sectioned surrogate particles to examine the mechanical stability of the critical interface between SiC and the outer pyrolytic carbon (OPyC) layer. The observed behavior at the interface is rationalized by examining the radially dependent fracture behavior of the SiC layer and performing a numerical analysis to quantify the residual stresses that develop during the processing and cross-sectioning of the as-fabricated particle. Characterizing the SiC-OPyC interface of surrogate TRISO particles using nanoindentation provides unique insight into the interface's room-temperature residual stress and mechanical stability. The modeling efforts were used to investigate the experimental procedure further, and the results are presented herein to validate this fuel form's potential mechanical failure modes.

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Publication Details

Journal
Journal of Nuclear Materials
Published
2025-01-23
DOI
https://doi.org/10.1016/j.jnucmat.2025.155654
Citations
4
Primary Topic
Advanced ceramic materials synthesis
Type
article
Field-Weighted Citation Impact
2.91
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article

Micromechanical response of SiC-OPyC layers in TRISO fuel particles

Danny Schappel, Erik G. Herbert, Katherine Montoya, Tyler Gerczak
4 citations
Journal of Nuclear Materials
Advanced ceramic materials synthesis
2.91
article

Micromechanical response of SiC-OPyC layers in TRISO fuel particles

Danny Schappel, Erik G. Herbert, Katherine Montoya, Tyler Gerczak
article en
4 citations

Abstract

• Impact testing of the SiC layer of surrogate TRISO to explore crack propagation . • Determination of preferential crack behavior of the SiC layer of TRISO fuel. • Modeling produced stress state profiles of TRISO fuel at various temperatures. Tristructural isotropic (TRISO)–coated particle fuel is a proposed fuel for multiple advanced reactor concepts. The performance of the particle depends on whether the silicon carbide (SiC) layer remains intact to prevent the release of metallic and gaseous fission products. Mechanical fracture of the SiC layer is a potential failure mode under various fuel configurations and operating environments, including the potential transmission of matrix-originating cracks through TRISO particles. This study uses instrumented indentation techniques on cross-sectioned surrogate particles to examine the mechanical stability of the critical interface between SiC and the outer pyrolytic carbon (OPyC) layer. The observed behavior at the interface is rationalized by examining the radially dependent fracture behavior of the SiC layer and performing a numerical analysis to quantify the residual stresses that develop during the processing and cross-sectioning of the as-fabricated particle. Characterizing the SiC-OPyC interface of surrogate TRISO particles using nanoindentation provides unique insight into the interface's room-temperature residual stress and mechanical stability. The modeling efforts were used to investigate the experimental procedure further, and the results are presented herein to validate this fuel form's potential mechanical failure modes.

Journal of Nuclear MaterialsVol. 606
Oak Ridge National Laboratory (US)
Affordable and clean energy
Openalex Percentile: Top 11%
Advanced ceramic materials synthesis
2.91
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Micromechanical response of SiC-OPyC layers in TRISO fuel particles — Danny Schappel, Erik G. Herbert, et al. · Journal of Nuclear Materials (2025) | TGRS Research Map | TGRS