Monte Carlo simulations of the SPERT III E-core transient experiments
Université Paris-Saclay, CEA, Service d’Etudes des Réacteurs et de Mathématiques Appliquées, 91191, Gif-sur-Yvette, France
2 EDF Lab, Palaiseau, France
Accepted: 23 December 2021
Published online: 17 January 2022
We perform simulations of two reactivity-insertion experiments in the SPERT III E-core nuclear research reactor. The simulations use the TRIPOLI-4® Monte Carlo neutron transport code as a neutron-transport solver, and the SUBCHANFLOW sub-channel code as a thermal-hydraulics solver. The results are in fair agreement with the measured total reactor power deposition. Sensitivity studies indicate that the simulation results appear to be relatively insensitive to the details of the model, but are sensitive to the assumed initial power of the system.
© The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2022