Fission products chemistry in simulated ...
Document type :
Article dans une revue scientifique: Article original
Permalink :
Title :
Fission products chemistry in simulated PWR fuel up to 2100C: Experimental characterisation and TAF-ID modelling
Author(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]
Journal title :
Journal of Nuclear Materials
Volume number :
572
Pages :
154040
Publisher :
Elsevier
Publication date :
2022-12-15
ISSN :
0022-3115
HAL domain(s) :
Chimie/Matériaux
English abstract : [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 ...
Show more >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.Show less >
Show more >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.Show less >
Language :
Anglais
Audience :
Internationale
Popular science :
Non
Administrative institution(s) :
Université de Lille
CNRS
INRAE
ENSCL
CNRS
INRAE
ENSCL
Collections :
Research team(s) :
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)
Submission date :
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