In case of a severe accident in Sodium-cooled Fast Reactors, interactions between partly molten fuel and sodium could happen at high temperature. Therefore, to predict the degradation evolution of fuel pins and phase formation in the different systems existing in the irradiated fuel, a thorough study of the Na-FP-Pu-U-O with FP= Ba, Cs, I, Mo, Te has to be performed. For such multicomponent system and large temperature and composition range, the Calphad method is a suitable way for developing a thermodynamic database to predict the phase formation depending on the temperature, pressure and composition of the system. Compositions with four Pu/(U+Pu) ratio in the Na-O-Pu-U system were synthesised by solid state synthesis method using nanopart...
Nuclear waste glasses are produced by chemical reactions between a solid waste (calcine) and a glass...
International audienceFor the understanding of severe accidents in sodium cooled fast reactors (SFR)...
In order to limit the consequences of a hypothetical core meltdown accident in Generation IV Sodium ...
Dans le cas d’un accident grave dans un réacteur refroidi au sodium, des interactions entre le combu...
The present study focuses on safety aspects of Sodium cooled Fast Reactors (SFR) and the potential i...
In support of the internal storage feasibility of future sodium cooled fast reactors, the present re...
A thermodynamic model for the Na-O system was developed for the first time using the CALPHAD method ...
Na3.16(2)UV,VI0.84(2)O4 is obtained from the reaction of sodium with uranium dioxide under oxygen po...
International audienceIn some of the currently developed Sodium Fast Reactor (SFR) designs the core ...
Neutron diffraction measurements of the double molybdate Cs3Na(MoO4)2 have been performed for the fi...
In order to limit the consequences of a hypothetical core meltdown accident in Generation IV Sodium ...
In the nuclear community, it is a top priority to gain in-depth understanding of fission product (FP...
Graduation date:2018Pyroprocessing is an advanced technology for recycling used nuclear fuel. Pyroch...
Nuclear waste glasses are produced by chemical reactions between a solid waste (calcine) and a glass...
International audienceFor the understanding of severe accidents in sodium cooled fast reactors (SFR)...
In order to limit the consequences of a hypothetical core meltdown accident in Generation IV Sodium ...
Dans le cas d’un accident grave dans un réacteur refroidi au sodium, des interactions entre le combu...
The present study focuses on safety aspects of Sodium cooled Fast Reactors (SFR) and the potential i...
In support of the internal storage feasibility of future sodium cooled fast reactors, the present re...
A thermodynamic model for the Na-O system was developed for the first time using the CALPHAD method ...
Na3.16(2)UV,VI0.84(2)O4 is obtained from the reaction of sodium with uranium dioxide under oxygen po...
International audienceIn some of the currently developed Sodium Fast Reactor (SFR) designs the core ...
Neutron diffraction measurements of the double molybdate Cs3Na(MoO4)2 have been performed for the fi...
In order to limit the consequences of a hypothetical core meltdown accident in Generation IV Sodium ...
In the nuclear community, it is a top priority to gain in-depth understanding of fission product (FP...
Graduation date:2018Pyroprocessing is an advanced technology for recycling used nuclear fuel. Pyroch...
Nuclear waste glasses are produced by chemical reactions between a solid waste (calcine) and a glass...
International audienceFor the understanding of severe accidents in sodium cooled fast reactors (SFR)...
In order to limit the consequences of a hypothetical core meltdown accident in Generation IV Sodium ...