Etude de l'altération de la matrice (U,Pu)O2 du combustible irradiéen conditions de stockage géologique : Approche expérimentale et modélisation géochimique

To assess the performance of direct disposal of spent fuel in a nuclear waste repository, researches are performed on the long-term behavior of spent fuel (UOx and MOx) under environmental conditions close to those of the French disposal site. The objective of this study is to determine whether the geochemistry of the Callovian-Oxfordian (COx) clay geological formation and the steel overpack corrosion (producing iron and hydrogen) have an impact on the oxidative dissolution of the (U,Pu)O2 matrix under alpha radiolysis of water.Leaching experiments have been performed with UO2 pellets doped with alpha emitters (Pu) and MIMAS MOx fuel (un-irradiated or spent fuel) to study the effect of the COx groundwater and of the presence of metallic iron upon the oxidative dissolution of these materials induced by the radiolysis of water. Results indicate an inhibiting effect of the COx water on the oxidative dissolution. In the presence of iron, two different behaviors are observed. Under alpha irradiation as the one expected in the geological disposal, the alteration of UO2 matrix and MOx fuel is very strongly inhibited because of the consumption of radiolytic oxidative species by iron in solution leading to the precipitation of Fe(III)-hydroxides on the pellets surface. On the contrary, under a strong beta/gamma irradiation field, alteration tracers indicate that the oxidative dissolution goes on and that uranium concentration in solution is controlled by the solubility of UO2(am,hyd). This is explained by the shifting of the redox front from the fuel surface to the bulk solution not protecting the fuel anymore. The developed geochemical (CHESS) and reactive transport (HYTEC) models correctly represent the main results and occurring mechanisms.Afin d’évaluer les performances du combustible irradié en situation de stockage géologique, des recherches sont menées sur le comportement à long terme des combustibles irradiés (UOx et MOx) en conditions environnementales se rapprochant de celles du site de stockage français. L’objectif de cette thèse est de déterminer si la géochimie de la couche géologique d'argilites du Callovo-Oxfordien (COx) et la corrosion des conteneurs en acier (produisant du fer et de l'hydrogène) ont un impact sur la dissolution oxydante de la matrice (U,Pu)O2 sous radiolyse alpha de l’eau.Des expériences de lixiviation ont été réalisées avec des pastilles de UO2 dopées en émetteurs alpha (Pu) et du combustible MOx MIMAS (non irradié ou irradié en réacteur) afin de mettre en évidence l’influence de l’eau du COx et de la présence de fer métallique sur la dissolution oxydante de ces différents matériaux induite par la radiolyse de l’eau. Les résultats indiquent un effet inhibiteur de l’eau du COx sur la dissolution oxydante de la matrice UO2. D’autre part en présence de fer, deux régimes différents sont observés. Sous irradiation alpha dominante telle que celle attendue en stockage géologique, la dissolution oxydante de la matrice UO2 et du combustible MOx est très fortement inhibée du fait de la consommation des espèces radiolytiques oxydantes par le fer en solution avec précipitation d’hydroxydes de Fe(III) à la surface des pastilles. En revanche, sous forte irradiation beta/gamma comme dans le cas du combustible irradié, les traceurs de l’altération indiquent que celle-ci se poursuit en présence de fer tandis que la concentration en uranium en solution est contrôlée par la solubilité de UO2(am,hyd). Ceci est expliqué par le déplacement du front redox de la surface du combustible vers la solution homogène ne protégeant plus le combustible. Les modèles géochimique (code CHESS) et de transport réactif (code HYTEC) développés représentent correctement les principaux résultats et mécanismes mis en jeu

Etude de l’altération de la matrice (Ux_x,Pu1−x_{1-x})O2_2 du combustible irradié en conditions de stockage géologique approche expérimentale et modélisation géochimique

Responsable CEA : Christophe JégouDirecteur universitaire : Laurent De WindtNational audienc

Study of (U,Pu)O2 spent fuel matrix alteration under geological disposal conditions : Experimental approach and geochemical modeling

Afin d’évaluer les performances du combustible irradié en situation de stockage géologique, des recherches sont menées sur le comportement à long terme des combustibles irradiés (UOx et MOx) en conditions environnementales se rapprochant de celles du site de stockage français. L’objectif de cette thèse est de déterminer si la géochimie de la couche géologique d'argilites du Callovo-Oxfordien (COx) et la corrosion des conteneurs en acier (produisant du fer et de l'hydrogène) ont un impact sur la dissolution oxydante de la matrice (U,Pu)O2 sous radiolyse alpha de l’eau.Des expériences de lixiviation ont été réalisées avec des pastilles de UO2 dopées en émetteurs alpha (Pu) et du combustible MOx MIMAS (non irradié ou irradié en réacteur) afin de mettre en évidence l’influence de l’eau du COx et de la présence de fer métallique sur la dissolution oxydante de ces différents matériaux induite par la radiolyse de l’eau. Les résultats indiquent un effet inhibiteur de l’eau du COx sur la dissolution oxydante de la matrice UO2. D’autre part en présence de fer, deux régimes différents sont observés. Sous irradiation alpha dominante telle que celle attendue en stockage géologique, la dissolution oxydante de la matrice UO2 et du combustible MOx est très fortement inhibée du fait de la consommation des espèces radiolytiques oxydantes par le fer en solution avec précipitation d’hydroxydes de Fe(III) à la surface des pastilles. En revanche, sous forte irradiation beta/gamma comme dans le cas du combustible irradié, les traceurs de l’altération indiquent que celle-ci se poursuit en présence de fer tandis que la concentration en uranium en solution est contrôlée par la solubilité de UO2(am,hyd). Ceci est expliqué par le déplacement du front redox de la surface du combustible vers la solution homogène ne protégeant plus le combustible. Les modèles géochimique (code CHESS) et de transport réactif (code HYTEC) développés représentent correctement les principaux résultats et mécanismes mis en jeu.To assess the performance of direct disposal of spent fuel in a nuclear waste repository, researches are performed on the long-term behavior of spent fuel (UOx and MOx) under environmental conditions close to those of the French disposal site. The objective of this study is to determine whether the geochemistry of the Callovian-Oxfordian (COx) clay geological formation and the steel overpack corrosion (producing iron and hydrogen) have an impact on the oxidative dissolution of the (U,Pu)O2 matrix under alpha radiolysis of water.Leaching experiments have been performed with UO2 pellets doped with alpha emitters (Pu) and MIMAS MOx fuel (un-irradiated or spent fuel) to study the effect of the COx groundwater and of the presence of metallic iron upon the oxidative dissolution of these materials induced by the radiolysis of water. Results indicate an inhibiting effect of the COx water on the oxidative dissolution. In the presence of iron, two different behaviors are observed. Under alpha irradiation as the one expected in the geological disposal, the alteration of UO2 matrix and MOx fuel is very strongly inhibited because of the consumption of radiolytic oxidative species by iron in solution leading to the precipitation of Fe(III)-hydroxides on the pellets surface. On the contrary, under a strong beta/gamma irradiation field, alteration tracers indicate that the oxidative dissolution goes on and that uranium concentration in solution is controlled by the solubility of UO2(am,hyd). This is explained by the shifting of the redox front from the fuel surface to the bulk solution not protecting the fuel anymore. The developed geochemical (CHESS) and reactive transport (HYTEC) models correctly represent the main results and occurring mechanisms

Modelling of metallic iron effect on radiolytic leaching of Pu-doped UO2 pellets in Callovian-Oxfordian groundwater under anoxic conditions

International audienc

Radiolytic leaching of Pu-doped UO2 pellets in the environment of clayey groundwater and iron canister

International audienc

Reactive transport modeling applied to radiolytic dissolution of uo2 in a synthetic clayey groundwater and in the presence of iron

International audienc

Modeling of radiolytic UO2 dissolution coupled to iron corrosion in clayey water

International audienc

Radiolytic leaching of pu-doped uo2 pellets in the environments of clayey groundwater and iron canister

International audienc

Effect of metallic iron on the oxidative dissolution of UO2 doped with a radioactive alpha emitter in synthetic Callovian-Oxfordian groundwater

International audienceIn the hypothesis of direct disposal of spent fuel in a geological nuclear waste repository, interactions between the fuel mainly composed of UO2 and its environment must be understood. The dissolution rate of the UO2 matrix, which depends on the redox conditions on the fuel surface, will have a major impact on the release of radionuclides into the environment. The reducing conditions expected for a geological disposal situation would appear to be favorable as regards the solubility and stability of the UO2 matrix, but may be disturbed on the surface of irradiated fuel. In particular, the local redox conditions will result from a competition between the radiolysis effects of water under alpha irradiation (simultaneously producing oxidizing species like H2O2, hydrogen peroxide, and reducing species like H2, hydrogen) and those of redox active species from the environment. In particular, Fe2+, a strongly reducing aqueous species coming from the corrosion of the iron canister or from the host rock, could influence the dissolution of the fuel matrix. The effect of iron on the oxidative dissolution of UO2 was thus investigated under the conditions of the French disposal site, a Callovian-Oxfordian clay formation chosen by the French National Radioactive Waste Management Agency (Andra), here tested under alpha irradiation. For this study, UO2 fuel pellets doped with a radioactive alpha emitter (238/239Pu) were leached in synthetic Callovian-Oxfordian groundwater (representative of the French waste disposal site groundwater) in the presence of a metallic iron foil to simulate the steel canister. The pellets had varying levels of alpha activity, in order to modulate the concentrations of species produced by water radiolysis on the surface and to simulate the activity of aged spent fuel after 50 and 10,000 years of alpha radioactivity decay. The experimental data showed that whatever the sample alpha radioactivity, the presence of iron inhibits the oxidizing dissolution of UO2 and leads to low uranium concentrations (between 4 × 10−10 and 4 × 10−9 M), through a reactional mechanism located in the very first microns of the UO2/water reactional interface. The mechanism involves consumption of oxidizing species, in particular of H2O2 by Fe2+ at the precise place where these species are produced, and is accompanied by the precipitation of an akaganeite-type Fe3+ hydroxide on the surface. The higher the radioactivity of the samples, the greater the precipitation induced. Modeling has been developed, coupling chemistry with transport and based on the main reactional mechanisms identified, which enables accurate reproduction of the mineralogy of the system under study, giving the nature of the phases under observation as well as the location of their precipitation. Obviously without excluding a potential contribution from the hydrogen produced by the anoxic corrosion of the iron foil, this study has shown that iron plays a major role in this oxidizing dissolution inhibition process for the system investigated (localized alpha radiolysis). This inhibitor effect associated with iron is therefore strongly dependent on the location of the redox front, which is found on the surface in the case of alpha irradiation UO2/water reactional interface