Fission products chemistry in simulated ...
Type de document :
Article dans une revue scientifique: Article original
URL permanente :
Titre :
Fission products chemistry in simulated PWR fuel up to 2100C: Experimental characterisation and TAF-ID modelling
Auteur(s) :
Geiger, E [Auteur]
CEA- Saclay [CEA]
Guéneau, C [Auteur]
CEA- Saclay [CEA]
Alpettaz, T [Auteur]
CEA- Saclay [CEA]
Bonnet, C [Auteur]
CEA- Saclay [CEA]
Chatain, S [Auteur]
CEA- Saclay [CEA]
Tougait, Olivier [Auteur]
Unité de Catalyse et Chimie du Solide (UCCS) - UMR 8181
Menut, D [Auteur]
Synchrotron SOLEIL [SSOLEIL]
Bellayer, Séverine [Auteur]
Unité Matériaux et Transformations (UMET) - UMR 8207
Hunault, M.O.J.Y. [Auteur]
Synchrotron SOLEIL [SSOLEIL]
Corcoran, E.C. [Auteur]
Royal Military College of Canada [RMCC]
CEA- Saclay [CEA]
Guéneau, C [Auteur]
CEA- Saclay [CEA]
Alpettaz, T [Auteur]
CEA- Saclay [CEA]
Bonnet, C [Auteur]
CEA- Saclay [CEA]
Chatain, S [Auteur]
CEA- Saclay [CEA]
Tougait, Olivier [Auteur]
Unité de Catalyse et Chimie du Solide (UCCS) - UMR 8181
Menut, D [Auteur]
Synchrotron SOLEIL [SSOLEIL]
Bellayer, Séverine [Auteur]
Unité Matériaux et Transformations (UMET) - UMR 8207
Hunault, M.O.J.Y. [Auteur]
Synchrotron SOLEIL [SSOLEIL]
Corcoran, E.C. [Auteur]
Royal Military College of Canada [RMCC]
Titre de la revue :
Journal of Nuclear Materials
Numéro :
572
Pagination :
154040
Éditeur :
Elsevier
Date de publication :
2022-12-15
ISSN :
0022-3115
Discipline(s) HAL :
Chimie/Matériaux
Résumé en anglais : [en]
The capabilities of the Thermodynamic of Advanced Fuels – International Database (TAF-ID) for reproducing the chemical behaviour of irradiated nuclear fuel in severe accident conditions were studied, by comparing calculation ...
Lire la suite >The capabilities of the Thermodynamic of Advanced Fuels – International Database (TAF-ID) for reproducing the chemical behaviour of irradiated nuclear fuel in severe accident conditions were studied, by comparing calculation results to experimental observations. SIMFUELs samples containing UO2 + 11 elements (Ba, Ce, La, Mo, Nd, Pd, Rh, Ru, Sr, Y and Zr, in concentration representative of a 76 GWd•tU-1 Burn-up) were submitted to 1327°C in oxidizing conditions, and to 1800, 2000, and 2100°C under reducing ones. Samples were characterized by Electron Probe Micro-Analysis (EPMA), High-Resolution XRD, and X-ray Absorption Spectroscopy (XAS). Thermodynamic calculations reproduced accurately the solubility of fission products in the UO2 matrix, and the type and composition of minor oxide and most metallic phases. Calculations also explain metallic phases microstructure as a result of the progressive solidification of liquids. However, some features such as the U-Pd-Rh association could not be reproduced, due to the lack of a thermodynamic model for this ternary system.Lire moins >
Lire la suite >The capabilities of the Thermodynamic of Advanced Fuels – International Database (TAF-ID) for reproducing the chemical behaviour of irradiated nuclear fuel in severe accident conditions were studied, by comparing calculation results to experimental observations. SIMFUELs samples containing UO2 + 11 elements (Ba, Ce, La, Mo, Nd, Pd, Rh, Ru, Sr, Y and Zr, in concentration representative of a 76 GWd•tU-1 Burn-up) were submitted to 1327°C in oxidizing conditions, and to 1800, 2000, and 2100°C under reducing ones. Samples were characterized by Electron Probe Micro-Analysis (EPMA), High-Resolution XRD, and X-ray Absorption Spectroscopy (XAS). Thermodynamic calculations reproduced accurately the solubility of fission products in the UO2 matrix, and the type and composition of minor oxide and most metallic phases. Calculations also explain metallic phases microstructure as a result of the progressive solidification of liquids. However, some features such as the U-Pd-Rh association could not be reproduced, due to the lack of a thermodynamic model for this ternary system.Lire moins >
Langue :
Anglais
Audience :
Internationale
Vulgarisation :
Non
Établissement(s) :
Université de Lille
CNRS
INRAE
ENSCL
CNRS
INRAE
ENSCL
Collections :
Équipe(s) de recherche :
Procédés de Recyclage et de Fonctionnalisation (PReF)
Chimie, matériaux et procédés pour un nucléaire durable (CIMEND)
Chimie, matériaux et procédés pour un nucléaire durable (CIMEND)
Date de dépôt :
2022-12-07T13:15:24Z
2022-12-09T08:56:35Z
2022-12-09T09:18:11Z
2022-12-09T08:56:35Z
2022-12-09T09:18:11Z