Simulation of Power Ramp Tested LWR Fuel Rods by means of the TRANSURANUS Code

摘要

In the present work. the power histories of 26LWR fuel rods. which were ramp tested in the Studsvik reactor R2 after base irradiation to burn - ups in the range of 10 - 45 MWd/kgU, are simulated by means of the TRANSURANUSfuel performance code. A critical comparison between the code predictions in terms of fission gas release and the experimental data available from the PWR Super - Ramp and WR Inter - Roamp Projects is performed Thi analyis pints out that a systematic under - estimation occurs when the input variables considered as standard TRANSURANUS options are chosen. Since the fuegaseous swelling under Pele - Cadding Interaction(PC) conditions is a nurrent open issue, a preliminary study concerning the modelling of this phenomenon is carried out in order to address future research activilies in the framework of the IAEA Coordinated Research Project FUMEX - III. Influence of different fuel densification and pellet-fragment relocation models on fission gas release predicions is also discussed.fragment relocation models on fission gas release predicions is also discussed.