Failure analysis of nuclear transient-tested UN tristructural isotropic fuel particles in a 3D printed SiC matrix

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Abstract

Fully ceramic microencapsulated fuel elements containing UN tristructural isotropic (TRISO) fuel particles within a 3D printed SiC matrix were subjected to transient testing with varying energy depositions. Detailed post-irradiation examinations were performed, including leaching in hot HNO3 and post-leaching X-ray computed tomography, to quantify the percentage of failed TRISO particles and crack propagation within the particles and surrounding fuel matrix. In parallel, detailed finite element analyses were performed for comparison with experimental findings and to better evaluate transient failure modes. The lowest transient energy deposition—which still exceeded bounding values for high-temperature gas-cooled reactor applications—resulted in no detectable TRISO particle failures or matrix cracking, which was consistent with the simulations. Simulations of the higher-energy transients for which significant TRISO particle failure was expected were generally able to reproduce the transient temperatures and matrix cracking. Thus, the TRISO particle failures were explained based on the effects of local SiC matrix thickness and porosity. Results generally confirmed the high strength of the additively manufactured SiC matrix but also affirmed the need for a modified UN TRISO architecture to prevent SiC matrix cracks from propagating through TRISO layers. This unique failure mode has not historically been considered for TRISO fuels contained in weaker graphite matrices.

Original languageEnglish
Article number154691
JournalJournal of Nuclear Materials
Volume586
DOIs
StatePublished - Dec 1 2023

Funding

The experimental irradiation testing and PIE were supported by the TCR Program under the US Department of Energy's (DOE's) Office of Nuclear Energy (NE). The simulations used the resources of the High Performance Computing Center at INL, which is supported by DOE NE and the Nuclear Science User Facilities Program under contract no. DE-AC07–05ID14517. The transient testing of the AM fuel elements at TREAT involved many former ORNL staff members, including Gokul Vasudevamurthy, Michael Trammell, Brian Jolly, and Kurt Terrani. Many current and former INL staff members contributed to the irradiation testing and initial PIE, including Nicolas Woolstenhulme, Daniel Chapman, Austin Fleming, Connie Hill, Nikolaus Cordes, Colby Jensen, Jason Schulthess, and Matthew Ramirez. Nicholas Brown (University of Tennessee, Knoxville) and Jacob Gorton provided helpful thoughts and discussions on the technical results and manuscript. The experimental irradiation testing and PIE were supported by the TCR Program under the US Department of Energy's (DOE's) Office of Nuclear Energy (NE). The simulations used the resources of the High Performance Computing Center at INL, which is supported by DOE NE and the Nuclear Science User Facilities Program under contract no. DE-AC07–05ID14517. The transient testing of the AM fuel elements at TREAT involved many former ORNL staff members, including Gokul Vasudevamurthy, Michael Trammell, Brian Jolly, and Kurt Terrani. Many current and former INL staff members contributed to the irradiation testing and initial PIE, including Nicolas Woolstenhulme, Daniel Chapman, Austin Fleming, Connie Hill, Nikolaus Cordes, Colby Jensen, Jason Schulthess, and Matthew Ramirez. Nicholas Brown (University of Tennessee, Knoxville) and Jacob Gorton provided helpful thoughts and discussions on the technical results and manuscript.

FundersFunder number
U.S. Department of Energy
Office of Nuclear EnergyDE-AC07–05ID14517
University of Tennessee

    Keywords

    • Additive manufacturing
    • Failure
    • Silicon carbide
    • Transient
    • Tristructural-isotropic
    • Uranium nitride

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