Transient fuel performance analysis for the preliminary fuel concept of general atomics fast modular reactor

• GA-FMR fuel performance analyzed using BISON with SiGA cladding during RIA and LOCA scenarios. • LOCA analysis predicts PCMI in hot and average rods using Mortar contact algorithm. • Knowledge gaps identified in UO2 fuel models with recommendations for improve fuel performance. This study investigates the transient fuel performance of General Atomics Fast Modular Reactor (GA-FMR) during accident scenarios, focusing on the behavior of its innovative fuel system that combines high-assay low enriched uranium dioxide (HALEUO2) fuel with SiGA® ceramic matrix composite silicon carbide cladding. The preliminary fuel design’s response was analyzed during reactivity-initiated accidents (RIA) and loss of coolant accidents (LOCA) using BISON fuel performance analysis code, which included both the diffusion enhanced and BISON-FASTGRASS coupled UO 2 models. The RIA analysis demonstrated that effective reactivity control reduced fuel temperature, though with transient fission gas release resulting in additional tensile stress state on the cladding. LOCA simulations revealed differing predictions between the two models: the BISON UO 2 model showed more transient fission gas release but minimal pellet expansion, while the BISON-FASTGRASS UO 2 model predicted less pronounced fission gas release but more fuel swelling and thermal expansion, potentially leading to pellet-cladding mechanical interaction. These findings highlight critical areas for fuel design optimization and identify knowledge gaps requiring further experimental and computational investigation to advance GA-FMR fuel development.

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Publication Details

Journal
Nuclear Engineering and Design
Published
2025-09-30
DOI
https://doi.org/10.1016/j.nucengdes.2025.114494
Primary Topic
Nuclear Materials and Properties
Type
article
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article

Transient fuel performance analysis for the preliminary fuel concept of general atomics fast modular reactor

Aaron Oaks, Yinbin Miao, Shipeng Shu, Christopher Ellis et al.
Nuclear Engineering and Design
Nuclear Materials and Properties
article

Transient fuel performance analysis for the preliminary fuel concept of general atomics fast modular reactor

Aaron Oaks, Yinbin Miao, Shipeng Shu, Christopher Ellis, Jason Rizk, Hangbok Choi, Abdellatif M. Yacout, John Bolin, Soon Lee
article en

Abstract

• GA-FMR fuel performance analyzed using BISON with SiGA cladding during RIA and LOCA scenarios. • LOCA analysis predicts PCMI in hot and average rods using Mortar contact algorithm. • Knowledge gaps identified in UO2 fuel models with recommendations for improve fuel performance. This study investigates the transient fuel performance of General Atomics Fast Modular Reactor (GA-FMR) during accident scenarios, focusing on the behavior of its innovative fuel system that combines high-assay low enriched uranium dioxide (HALEUO2) fuel with SiGA® ceramic matrix composite silicon carbide cladding. The preliminary fuel design’s response was analyzed during reactivity-initiated accidents (RIA) and loss of coolant accidents (LOCA) using BISON fuel performance analysis code, which included both the diffusion enhanced and BISON-FASTGRASS coupled UO 2 models. The RIA analysis demonstrated that effective reactivity control reduced fuel temperature, though with transient fission gas release resulting in additional tensile stress state on the cladding. LOCA simulations revealed differing predictions between the two models: the BISON UO 2 model showed more transient fission gas release but minimal pellet expansion, while the BISON-FASTGRASS UO 2 model predicted less pronounced fission gas release but more fuel swelling and thermal expansion, potentially leading to pellet-cladding mechanical interaction. These findings highlight critical areas for fuel design optimization and identify knowledge gaps requiring further experimental and computational investigation to advance GA-FMR fuel development.

Nuclear Engineering and DesignVol. 445
Openalex Percentile: Top 79%
Nuclear Materials and Properties
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