5–8 May 2026
Gotland, Visby
Europe/Stockholm timezone

Neutronic Analysis of a Hybrid Fuel Cycle Between Maritime and Terrestrial Fluoride-salt-cooled High-temperature Reactors

6 May 2026, 17:10
7m
Bryggarsalen (Gotland, Visby)

Bryggarsalen

Gotland, Visby

Visby Strand Hotel
flash 5+2 Flash talks

Speaker

Mr Josef A. H. Hisanawi (Department of Physics, University of Oslo)

Description

This study computationally evaluates a hybrid nuclear fuel cycle in which partially depleted fuel pebbles from a compact maritime Fluoride-salt-cooled High-temperature Reactor (FHR) are transferred to a larger terrestrial FHR for continued utilization. Neutronic behavior is analyzed using a high-fidelity Monte Carlo framework: the Hyper-Fidelity (HxF) tool models detailed depletion in the maritime reactor, while the Search Equilibrium tool determines the equilibrium steady-state fuel composition in the terrestrial core. Results indicate that the hybrid approach significantly enhances total energy extraction per unit mass of heavy metal compared to independent single-reactor operation. While a conventional once-through cycle achieves an average burnup of 148 MWd/kgHM, transferring pebbles at burnup of 47.5 MWd/kgHM enables a subsequent burnup of 110 MWd/kgHM in the terrestrial core, yielding a total of 157.5 MWd/kgHM, a 6.4% increase. Additionally, performance improves further at lower transfer burnups, with 35 MWd/kgHM transfers achieving total burnups up to 163 MWd/kgHM. These results demonstrate that sequential burning of pebbles in spectrally different reactor environments can outperform the energy extraction limit of single-core operation, providing a potential path toward improved fuel utilization and reduced waste generation for advanced FHR fleets, and potentially other TRISO fueled reactors.

Author

Mr Josef A. H. Hisanawi (Department of Physics, University of Oslo)

Presentation materials

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