In the present work, the power histories of 26 LWR 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 TRANSURANUS fuel 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 BWR Inter-Ramp Projects is performed. This analysis points out that a systematic under-estimation occurs when the input variables considered as standard TRANSURANUS options are chosen. Since the fuel gaseous swelling under Pellet-Cladding Interaction (PCI) conditions is a current open issue, a preliminary study concerning the modelling of this phenomenon is carried out in order to address future research activities in the framework of the IAEA Coordinated Research Project FUMEX-III. Influence of different fuel densification and pelletfragment relocation models on fission gas release predictions is also discussed.

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

PASTORE, GIOVANNI;BOTAZZOLI, PIETRO;DI MARCELLO, VALENTINO;LUZZI, LELIO
2009

Abstract

In the present work, the power histories of 26 LWR 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 TRANSURANUS fuel 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 BWR Inter-Ramp Projects is performed. This analysis points out that a systematic under-estimation occurs when the input variables considered as standard TRANSURANUS options are chosen. Since the fuel gaseous swelling under Pellet-Cladding Interaction (PCI) conditions is a current open issue, a preliminary study concerning the modelling of this phenomenon is carried out in order to address future research activities in the framework of the IAEA Coordinated Research Project FUMEX-III. Influence of different fuel densification and pelletfragment relocation models on fission gas release predictions is also discussed.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11311/545469
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