Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels

William A. Hanson; Fabiola Cappia; Joshua T. White; Kenneth J. McClellan; Jason M. Harp

doi:10.1016/j.jnucmat.2023.154346

Post-irradiation examination of low burnup U₃Si₅ and UN-U₃Si₅ composite fuels

William A. Hanson, Fabiola Cappia, Joshua T. White, Kenneth J. McClellan, Jason M. Harp

Nuclear Fuel Element Performance

Research output: Contribution to journal › Article › peer-review

2 Scopus citations

Abstract

This work presents post-irradiation examination data on UN-U₃Si₅ and U₃Si₅ fuels at low burnup (i.e., <10–15 GWd/tHM) with Kanthal AF® cladding. The results suggest good irradiation performance for both the silicide and nitride-silicide composite pellets. Optical microscopy revealed that the pellet-cladding gap is still open, and limited axial cracking was observed only in UN-U₃Si₅ pellets. Microcracking was isolated to the U₃Si₅ phase in all cases and was observed in pre-irradiation and depleted pellets, indicating that it was not irradiation induced. The fission gas release was minimal for the calculated fission density achieved (2.6 – 3.15 × 10²⁰ fiss/cm³). No fission gas bubbles were observed in the optical metallography. These results suggest acceptable swelling and fission gas behavior for both the single phase and composite compositions.

Original language	English
Article number	154346
Journal	Journal of Nuclear Materials
Volume	578
DOIs	https://doi.org/10.1016/j.jnucmat.2023.154346
State	Published - May 2023

Funding

This work is supported by the U.S. Department of Energy , under DOE Idaho Operations Office Contract DE-AC07–05ID14517 and National Nuclear Security Administration contract number 89233218CNA000001 . Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. The authors would also like to acknowledge the staff, engineers, and operators of the Materials and Fuels Complex (MFC) Hot Fuel Examination Facility (HFEF) for their efforts during the post-irradiation examinations. This work is supported by the U.S. Department of Energy, under DOE Idaho Operations Office Contract DE-AC07–05ID14517 and National Nuclear Security Administration contract number 89233218CNA000001. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. The authors would also like to acknowledge the staff, engineers, and operators of the Materials and Fuels Complex (MFC) Hot Fuel Examination Facility (HFEF) for their efforts during the post-irradiation examinations.

Funders	Funder number
Hot Fuel Examination Facility
U.S. Department of Energy	DE-AC07–05ID14517
National Nuclear Security Administration	89233218CNA000001

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10.1016/j.jnucmat.2023.154346

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title = "Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels",

abstract = "This work presents post-irradiation examination data on UN-U3Si5 and U3Si5 fuels at low burnup (i.e., <10–15 GWd/tHM) with Kanthal AF{\textregistered} cladding. The results suggest good irradiation performance for both the silicide and nitride-silicide composite pellets. Optical microscopy revealed that the pellet-cladding gap is still open, and limited axial cracking was observed only in UN-U3Si5 pellets. Microcracking was isolated to the U3Si5 phase in all cases and was observed in pre-irradiation and depleted pellets, indicating that it was not irradiation induced. The fission gas release was minimal for the calculated fission density achieved (2.6 – 3.15 × 1020 fiss/cm3). No fission gas bubbles were observed in the optical metallography. These results suggest acceptable swelling and fission gas behavior for both the single phase and composite compositions.",

author = "Hanson, {William A.} and Fabiola Cappia and White, {Joshua T.} and McClellan, {Kenneth J.} and Harp, {Jason M.}",

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doi = "10.1016/j.jnucmat.2023.154346",

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AU - Hanson, William A.

AU - Cappia, Fabiola

AU - White, Joshua T.

AU - McClellan, Kenneth J.

AU - Harp, Jason M.

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N2 - This work presents post-irradiation examination data on UN-U3Si5 and U3Si5 fuels at low burnup (i.e., <10–15 GWd/tHM) with Kanthal AF® cladding. The results suggest good irradiation performance for both the silicide and nitride-silicide composite pellets. Optical microscopy revealed that the pellet-cladding gap is still open, and limited axial cracking was observed only in UN-U3Si5 pellets. Microcracking was isolated to the U3Si5 phase in all cases and was observed in pre-irradiation and depleted pellets, indicating that it was not irradiation induced. The fission gas release was minimal for the calculated fission density achieved (2.6 – 3.15 × 1020 fiss/cm3). No fission gas bubbles were observed in the optical metallography. These results suggest acceptable swelling and fission gas behavior for both the single phase and composite compositions.

AB - This work presents post-irradiation examination data on UN-U3Si5 and U3Si5 fuels at low burnup (i.e., <10–15 GWd/tHM) with Kanthal AF® cladding. The results suggest good irradiation performance for both the silicide and nitride-silicide composite pellets. Optical microscopy revealed that the pellet-cladding gap is still open, and limited axial cracking was observed only in UN-U3Si5 pellets. Microcracking was isolated to the U3Si5 phase in all cases and was observed in pre-irradiation and depleted pellets, indicating that it was not irradiation induced. The fission gas release was minimal for the calculated fission density achieved (2.6 – 3.15 × 1020 fiss/cm3). No fission gas bubbles were observed in the optical metallography. These results suggest acceptable swelling and fission gas behavior for both the single phase and composite compositions.

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Post-irradiation examination of low burnup U₃Si₅ and UN-U₃Si₅ composite fuels

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