In France, High-Level radioactive Wastes (HLW) coming from nuclear spent fuel treatment are confined at the atomic scale in an homogeneous sodium-borosilicate glass called the R7T7 glass. At different stages of the melting process performed at high temperature, crystallized phases which incorporate the radionuclides are temporarily formed before their dissolution. The formation conditions of these crystals have already been studied but, to date, few studies on their dissolution in nuclear glass melt have been performed. The objective of this thesis is the description of the kinetics and mechanisms of the crystals dissolution in the borosilicate melt.This study focuses on the dissolution of rare earth silicates with an apatite structure (Ca2...
Borosilicate glass is to be used for permanent disposal of high-level nuclear waste in a geologic re...
AbstractThe aim of this work is to determine the impact of a thermal gradient on the crystallization...
This thesis focuses on the modeling of dissolution phenomena during the early phase of a serious acc...
In France, High-Level radioactive Wastes (HLW) coming from nuclear spent fuel treatment are confined...
En France, les déchets de Haute Activité à Vie Longue (HAVL) issus du retraitement du combustible nu...
This work describes a new approach to help understand the chemical durability of partially crystalli...
Nuclear waste glasses are produced by chemical reactions between a solid waste (calcine) and a glass...
Nuclear waste glasses are produced by chemical reactions between a solid waste (calcine) and a glass...
In France, the highly radioactive nuclear liquid wastes arising from spent nuclear fuel reprocessing...
Alkali borosilicate glasses have been widely used as an immobilisation network for high level, radio...
Ces travaux proposent une nouvelle approche pour appréhender la durabilité chimique de matrices de c...
Mme Chevarier Noëlle (Rapporteur, Professeur à l'Université de Lyon) M. Beauvy Michel (Rapporteur, D...
Immobilization of high-level and intermediate-level nuclear wastes by vitrification in borosilicate ...
Borosilicate glass is to be used for permanent disposal of high-level nuclear waste in a geologic re...
AbstractThe aim of this work is to determine the impact of a thermal gradient on the crystallization...
This thesis focuses on the modeling of dissolution phenomena during the early phase of a serious acc...
In France, High-Level radioactive Wastes (HLW) coming from nuclear spent fuel treatment are confined...
En France, les déchets de Haute Activité à Vie Longue (HAVL) issus du retraitement du combustible nu...
This work describes a new approach to help understand the chemical durability of partially crystalli...
Nuclear waste glasses are produced by chemical reactions between a solid waste (calcine) and a glass...
Nuclear waste glasses are produced by chemical reactions between a solid waste (calcine) and a glass...
In France, the highly radioactive nuclear liquid wastes arising from spent nuclear fuel reprocessing...
Alkali borosilicate glasses have been widely used as an immobilisation network for high level, radio...
Ces travaux proposent une nouvelle approche pour appréhender la durabilité chimique de matrices de c...
Mme Chevarier Noëlle (Rapporteur, Professeur à l'Université de Lyon) M. Beauvy Michel (Rapporteur, D...
Immobilization of high-level and intermediate-level nuclear wastes by vitrification in borosilicate ...
Borosilicate glass is to be used for permanent disposal of high-level nuclear waste in a geologic re...
AbstractThe aim of this work is to determine the impact of a thermal gradient on the crystallization...
This thesis focuses on the modeling of dissolution phenomena during the early phase of a serious acc...