In this work, FINIX is used as an internal fuel behaviour module both in reactor physics and in reactor dynamics codes to simulate coupled behaviour in fast transient scenarios. | Multiphysics simulation of fast transients with the FINIX fuel behaviour module EPJ Nuclear Sci. Technol. 2 37 2016 Nuclear Sciences T. Ikonen et al. published by EDP Sciences 2016 amp Technologies DOI epjn 2016032 Available online at http REGULAR ARTICLE Multiphysics simulation of fast transients with the FINIX fuel behaviour module Timo Ikonen Elina Syrjälahti Ville Valtavirta Henri Loukusa Jaakko Leppänen and Ville Tulkki VTT Technical Research Centre of Finland . Box 1000 02044 VTT Finland Received 24 November 2015 Received in final form 25 April 2016 Accepted 2 August 2016 Abstract. FINIX is a recently developed fuel behaviour module that is designed to provide simple but sufficient descriptions of the most essential fuel behaviour phenomena in multiphysics simulations. In such simulations it is possible to obtain significant improvement in the feedback to neutronics or thermal hydraulics modelling even with a relatively simple fuel performance model. In this work FINIX is used as an internal fuel behaviour module both in reactor physics and in reactor dynamics codes to simulate coupled behaviour in fast transient scenarios. With the Monte Carlo reactor physics code Serpent we model a prompt transient in a VVER-1000 pin cell and with the reactor dynamics code HEXTRAN a control rod ejection accident in a VVER-440 reactor. 1 Introduction without imposing on them the complete fuel behaviour phenomenology but still provide significant improvements In light water reactors the thermal and mechanical to stand-alone simulation methods. behaviour of the fuel rods strongly influences the behaviour As examples of multiphysics simulations we use the of the reactor in both steady state and transient conditions. FINIX fuel behaviour module integrated into Serpent 2 For example the power of the reactor is sharply affected by Monte Carlo reactor physics code and HEXTRAN reactor the fuel temperature due to the absorption of neutrons by dynamics code. As a
