SharePoint
Aide
Faire avancer la sûreté nucléaire

La Recherchev2

Publications

Analyses préliminaires de l'essai Phebus FPT3 avec les codes Accidents Graves (ICARE2, ATHLET-CD, MELCOR)


Fermer

Authentification

Email :

Mot de passe :

Titre du congrès :European Review Meeting on Severe Accident Research Ville du congrès :Karlsruhe Date du congrès :12/06/2007

Résumé

The aim of the Phebus FP experimental program is to study the degradation phenomena and the behaviour of the fission products (FP) released in the reactor coolant system and the containment building. The program consists of four in-pile bundle tests (FPT-0, FPT-1, FPT-2 and FPT-3), performed under different conditions concerning the thermal hydraulics and the environment of fuel rods, in particular the amount of steam (strongly or weakly oxidizing atmosphere). The last test of this program, FPT-3, has been performed in Novem-ber 2004 in Cadarache. During the FPT-3 experiment boron carbide was used as absorber material for the first time instead of Ag-In-Cd, which was used in all the previous tests. Boron carbide is used in nuclear power plants like western type PWR, EPR, BWR and VVER, which shows the importance to asses its effects on the main degradation phenomena, as well as the gas release, and the impact on the fission products behaviour. This paper is focused on the FPT3 preliminary analyses, and in particular on the B4C control rod behaviour using Severe Accident Codes, i.e. ATHLET-CD, ICARE/CATHARE, MELCOR, performed in the framework of the Work Package 9.2 of the Network of Excellence SARNET. The first part of this paper deals with an overview of the experimental results (boundary conditions, tempera-ture evolutions, hydrogen and carbon compounds releases coming from the oxidation of the Zircaloy claddings and the B4C absorber and bundle degradation). The second part proposes a summary of the code modelling used in the different code applications, in particular those regarding the absorber rod degradation and oxida-tion. The third part summarizes the code results with comparisons regarding some important experimental parameters (thermal behaviour, gas releases and bundle degradation). The conclusion will be focused on the preliminary synthesis of the Severe Accident Code capabilities to simu-late the control rod behaviour in a fuel rod assembly during the course of severe accident transient.