Progress in the Modeling of High Burnup Structure: Application of the TRANSURANUS//MFPR-F Coupling to the NRC-192 Studsvik LOCA TEST - IRSN - Institut de radioprotection et de sûreté nucléaire Accéder directement au contenu
Communication Dans Un Congrès Année : 2023

Progress in the Modeling of High Burnup Structure: Application of the TRANSURANUS//MFPR-F Coupling to the NRC-192 Studsvik LOCA TEST

Andrius Tidikas
  • Fonction : Auteur
  • PersonId : 1362374
Andrius Slavickas
  • Fonction : Auteur
  • PersonId : 1362375

Résumé

The MFPR-F (Module for Fission Product Release – France) code coupled with the TRANSURANUS fuel performance code was applied to the Studsvik NRC-192 Loss of Coolant Accident experiment on a high burnup UO2 fuel rod. The presented study, conducted in the framework of the R2CA project, focuses on the formation of the High-Burnup Structure during irradiation and on the fission gas release during the LOCA transient. MFPR-F code supplements TRANSURANUS code with a more in-depth description of the local microstructure in the UO2 matrix, allowing to predict the onset of fuel restructuring [1]. This modelling is used in the present study to calculate the width of the HBS zone in the fuel rod at the end of irradiation, which is found to be 400 µm. Regarding the LOCA transient, the MFPR-F model for fission gas release from the HBS pores, based on an empirical parameter related to the pore over-pressurization, predicts that a large part the gas is released for over-pressure ranging from 150 to 300 MPa.
Fichier principal
Vignette du fichier
WRFPM2023_Paper_Kremer_Tidikas_Slavickas.pdf (588 Ko) Télécharger le fichier
Origine Fichiers produits par l'(les) auteur(s)

Dates et versions

irsn-04498965 , version 1 (30-05-2024)

Licence

Copyright (Tous droits réservés)

Identifiants

Citer

François Kremer, Andrius Tidikas, Andrius Slavickas. Progress in the Modeling of High Burnup Structure: Application of the TRANSURANUS//MFPR-F Coupling to the NRC-192 Studsvik LOCA TEST. WRFPM 2023 - International Conference on Water Reactor Fuel Performance Meeting, Chinese Nuclear Society(CNS), Jul 2023, Xi'an, China. pp.330-339, ⟨10.1007/978-981-99-7157-2⟩. ⟨irsn-04498965⟩
7 Consultations
0 Téléchargements

Altmetric

Partager

Gmail Mastodon Facebook X LinkedIn More