Microstructurally validated stable and predictable swelling in low-enriched uranium monolithic U-10Mo fuel mini-plates

Hanson, William A.; Salvato, Daniele; Robinson, Adam B.; Lybeck, Nancy J.; Jue, Jan-Fong; Trowbridge, Tammy L.; Burns, Jatuporn; Di Lemma, Fidelma G.; Smith, Charlyne A.; Marshall, Margaret A.; Keiser Jr., Dennis D.; Giglio, Jeffrey J.; Cole, James I.

doi:10.1016/j.jnucmat.2025.155746

Microstructurally validated stable and predictable swelling in low-enriched uranium monolithic U-10Mo fuel mini-plates

Journal Article · Mon Mar 17 20:00:00 EDT 2025 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2025.155746· OSTI ID:2564712

^[1]; ^[1]; ^[1]; ^[1]; Jue, Jan-Fong ^[1]; ^[1]; Burns, Jatuporn ^[1]; ^[1]; Smith, Charlyne A. ^[1]; ^[1]; Keiser Jr., Dennis D. ^[1]; Giglio, Jeffrey J. ^[1]; ^[1]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Qualification of the low-enriched uranium (LEU) monolithic U-10 wt%Mo (U-10Mo) plate-type fuel system requires a demonstration of a stable and predictable fuel swelling behavior over the anticipated operating conditions of the United States high-performance research reactors (USHPRRs) selected for conversion to LEU operation. This will allow each reactor to develop appropriate safety margins that will retain fuel element lifetime coolability. Additionally, the fuel system must maintain performance attributes when fabricated at a commercial scale. The Mini-plate 1 experiment represents the first irradiation test of commercially fabricated miniaturized monolithic LEU U-10Mo fuel plates. Here, the swelling behavior within this experiment was compared against that of historical fuel developmental tests to reveal that the commercially fabricated fuel performed within the current recommended U-10Mo swelling model's predictions. Additionally, the fuel microstructural evolution was evaluated to link initial conditions to subtle variations detected in the swelling response, providing validation and confidence that the fuel system is robust.

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2564712

Alternate ID(s):: OSTI ID: 3011941

Report Number(s):: INL/JOU--24-77218-Rev000

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 609; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (6)

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Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR2 Leenaers, A.; Van den Berghe, S.; Koonen, E. Journal of Nuclear Materials, Vol. 458 https://doi.org/10.1016/j.jnucmat.2014.12.073	journal	March 2015
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High burn-up structure of U(Mo) dispersion fuel Leenaers, A.; Van Renterghem, W.; Van den Berghe, S. Journal of Nuclear Materials, Vol. 476 https://doi.org/10.1016/j.jnucmat.2016.04.035	journal	August 2016
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Properties of DU–10wt% Mo alloys subjected to various post-rolling heat treatments Burkes, Douglas E.; Prabhakaran, Ramprashad; Hartmann, Thomas Nuclear Engineering and Design, Vol. 240, Issue 6 https://doi.org/10.1016/j.nucengdes.2010.02.008	journal	June 2010

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Microstructurally validated stable and predictable swelling in low-enriched uranium monolithic U-10Mo fuel mini-plates

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