This work presents the results for a coupled neutronic-thermalhydraulic-thermomechanic pin-level depletion calculation of a PWR fuel assembly using Serpent2-SUBCHANFLOWTRANSURANUS. This tool is based on a semi-implicit depletion scheme with pin-by-pin feedback, mesh-based field exchange and an object-oriented software design. The impact of including fuel-performance capabilities is analyzed, with focus on high-burnup effects. The treatment of the Doppler feedback to the neutronics is examined as well, in particular the use of radial fuel-temperature profiles or radially averaged values.
|Number of pages||8|
|Journal||EPJ Web of Conferences|
|Publication status||Published - 2020|
|MoE publication type||A4 Article in a conference publication|
|Event||International Conference on Physics of Reactors, PHYSOR 2020: Transition to a Scalable Nuclear Future - Cambridge, United Kingdom|
Duration: 28 Mar 2020 → 2 Apr 2020