The impact of the matrix and buffer properties on residual stresses in TRISO particles during manufacture and early life
A three-dimensional finite-element model was developed using Abaqus to simulate the fabrication and initial power ramp-up of a tri-structural isotropic (TRISO) particle, featuring a UO2 kernel, encapsulated in either a SiC or graphite matrix. After sintering, the residual compressive hoop stress in the SiC coating layer reached -540 MPa when encapsulated in a graphite matrix, 94 MPa more compressive than in a SiC matrix. However, following the initial power ramp-up, the predicted compressive hoop stresses in the SiC layer of a particle embedded in a SiC matrix (-388 MPa) were significantly greater than in a graphite matrix (-222 MPa), emphasizing the matrix material's critical role in the stress state of the SiC layer. Model validation attempts were made with the experimental measurements of the residual stresses of a zirconia-kernel surrogate particle. We found that in a fully-bonded surrogate TRISO particle, the stress state of the SiC layer is highly sensitive to the buffer porosity with compressive SiC layer hoop stresses ranging from up to -1.06 GPa at a porosity of 0.14 to -0.77 GPa at a porosity of 0.60. Partial kernel/buffer delamination simulations revealed a significantly varied geometric stress distribution, with tensile stresses reaching up to +54 MPa and compressive stresses up to -546 MPa at different axes of the sectioned plane in the model. This finding suggests that contrary to the common assumption of complete delamination at the kernel/buffer interface during fabrication, partial delamination is a more plausible explanation for the high compressive stresses observed in the SiC layer experimentally.
Authors
- Mark R. Wenman (ORCID: https://orcid.org/0000-0001-9032-1091)
- Alexander J. Leide (ORCID: https://orcid.org/0000-0002-3103-9210)
- A. Battistini (ORCID: https://orcid.org/0000-0001-7845-7981)
- T.A. Haynes (ORCID: https://orcid.org/0000-0003-0058-2939)
- Lloyd Jones
- Udeme Chukwuemeka Inyang-Udoh (ORCID: https://orcid.org/0009-0004-9277-1191)
Publication Details
- Journal
- Journal of Nuclear Materials
- Published
- 2025-11-20
- DOI
- https://doi.org/10.1016/j.jnucmat.2025.156311
- Primary Topic
- Graphite, nuclear technology, radiation studies
- Type
- article
- Field-Weighted Citation Impact
- 0.00