FEniCSx-OpenMC Coupling for Neutronic Calculation with Temperature Feedback

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[PDF][PDF] Analysis of Power Mesh Tally Resolution for Coupled Neutronic and Thermohydraulic Simulations of Advanced PWR Core

T Korınek, J Škarohlıd, R Škoda, J Závorka, M Lovecký - djs.si
Coupled neutron transport and thermal-hydraulics calculations are essential in designing
advanced nuclear reactors. The increase in computational power in recent decades has …
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