Radman, StefanFiorina, CarloSong, PingPautz, Andreas2022-05-232022-05-232022-05-232022-04-0110.1016/j.anucene.2021.108891https://infoscience.epfl.ch/handle/20.500.14299/188013WOS:000793280500008Following the growing interest that we observe in the use of OpenFOAM for nuclear reactor analysis, the current work presents a point-kinetics model and associated open-source code that can easily be inte-grated in existing thermal-hydraulic solvers to streamline the use of OpenFOAM for multi-physics inves-tigations. As a proof of concept, we have integrated the new solver in the GeN-Foam multiphysics platform, and validated it against past experimental measurements from the Fast Flux Test Facility, a 400 MW (th) Sodium-cooled Fast Reactor located at the Hanford Site, Washington, USA. Both steady-state and transient simulations provide satisfactory results, also in view of previous studies with other codes. Overall, the developed point-kinetics model and its integration in GeN-Foam have proven to be suitable for the system-level investigation of nuclear reactor transients, thus enabling a more widespread use by the nuclear community of a major open-source toolkit like OpenFOAM.(c) 2021 The Author(s). Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).Nuclear Science & Technologygen-foamopenfoampoint-kineticssodium-cooled fast reactorunprotected loss of flowneutron-transporttext::journal::journal article::research article