Investigations of fuel behaviour are carried out in close connection with experimental research operation feedback and computational analyses. In this connection, OECD NEA sets up the “public domain database on nuclear fuel performance experiments for the purpose of code development and validation – International Fuel Performance Experiments (IFPE) database”, with the aim of providing a comprehensive and well-qualified database on UO2 fuel with Zircaloy cladding for model development and code validation. The aim of the activity is to assess the capability of TRANSURANUS (version “v1m1j08”) code in predicting the phenomenon of the pellet clad interaction (PCI). The objective is pursued using two experimental databases carried out in the research reactor R2 at Studsvik and belonging to the IFPE database. The experiments address the behavior of standard-type BWR and PWR fuel rods, including preceding base irradiation, during the over-power ramping. Pre-, during-, and post- irradiation, non destructive and destructive examinations were executed, in order to determine and understand the behavior of the fuel rods, but also to provide suitable data, useful for code validation.
Capabilities of TRANSURANUS Code in Simulating Power Ramp Tests from the IFPE Database
D'AURIA, FRANCESCO SAVERIO
2009-01-01
Abstract
Investigations of fuel behaviour are carried out in close connection with experimental research operation feedback and computational analyses. In this connection, OECD NEA sets up the “public domain database on nuclear fuel performance experiments for the purpose of code development and validation – International Fuel Performance Experiments (IFPE) database”, with the aim of providing a comprehensive and well-qualified database on UO2 fuel with Zircaloy cladding for model development and code validation. The aim of the activity is to assess the capability of TRANSURANUS (version “v1m1j08”) code in predicting the phenomenon of the pellet clad interaction (PCI). The objective is pursued using two experimental databases carried out in the research reactor R2 at Studsvik and belonging to the IFPE database. The experiments address the behavior of standard-type BWR and PWR fuel rods, including preceding base irradiation, during the over-power ramping. Pre-, during-, and post- irradiation, non destructive and destructive examinations were executed, in order to determine and understand the behavior of the fuel rods, but also to provide suitable data, useful for code validation.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
