2025/02/24 by Mathis Caprais, Caprais, Mathis, Nathan J. Greiner +3
Engineering · Materials Science · #Computational Physics (physics.comp-ph) #FOS: Physical sciences #Graphite, nuclear technology, radiation studies #Nuclear and radioactivity studies #Nuclear reactor physics and engineering
paper · pdf · doi:10.48550/arxiv.2502.17014
openalex publication_date 2025/02/24 · openalex created_date 2025/10/10 · openalex updated_date 2026/07/28
In this work, a new numerical method for the transport of Delayed Neutron Precursors (DNPs) is applied to the Aircraft Reactor Experiment (ARE). The pathline method is based on the Method of Characteristics (MOC) and leverages the pathlines of the liquid nuclear fuel to derive an integral form of the DNPs balance equation. The method has previously been tested on the CNRS benchmark and in a simplified 2D geometry where turbulent diffusivity was significant compared to advection. Here, the pathline method is applied to a real-world Molten Salt Reactor (MSR), the ARE. DNPs transport is implemented in the framework of the coupling between neutron transport solver APOLLO3\textregistered and computational fluid dynamics code TrioCFD, both developed at the French Atomic and Energy Commission (CEA). The DNPs concentration obtained with the pathline method were compared with those previously computed by TrioCFD, highlighting the importance of recirculation of fission products. The L-7 experiment was also replicated to demonstrate the method's capability.