One option envisioned for the future management of high level nuclear waste is the transmutation of minor actinides into short-lived fission products in sodium fast reactor. This route requires the development of pellet fabrication processes to prepare Minor Actinide Bearing Blanket (MABB) for the transmutation of americium.Currently, those ceramic pellets are produced by powder metallurgy processes involving numerous grinding and milling steps that generate very fine and highly contaminating and irradiating particles. A viable option for reducing the amount of those fine particles would be to develop a dustless process by working on much coarser particles. In this context, this study is concerned with the pelletization of porous and spheri...
Cette étude s’inscrit dans le cadre d’une gestion commune de l’uranium et du plutonium par un procéd...
One option under consideration for the recycling of minor actinides is to incorporate about 10% into...
This thesis is part of the research and development program performed at the ALTO facility (Accéléra...
One option envisioned for the future management of high level nuclear waste is the transmutation of ...
Ce travail de thèse s'inscrit dans le cadre de recherches sur le retraitement futur du combustible n...
International audienceThe future management of nuclear ultimate waste requires pellet fabrication of...
Dans le cadre des recherches sur l'aval du cycle du combustible et des projets de transmutation de l...
One of the studied routes to reduce nuclear waste amount, is, after plutonium recycling, americium (...
This study is devoted to the synthesis and the characterization of porous metal oxide microsphere fr...
Une des voies à l’étude permettant de réduire l’inventaire des déchets nucléaires, après recyclage d...
This report gives a synthesis of the work I have carried out or to which I have numerically contribu...
International audienceThis study deals with the preliminary development of a powder-free process cal...
Sintering is a key step in the elaboration of UOx and MOx (U/Pu mixed oxide) nuclear fuels pellets u...
The context of this study is about increasing the performances of nuclear fuel used in existing nucl...
Sintering is a key step during the fabrication of UOx and MOx nuclear fuels used in the PWR reactors...
Cette étude s’inscrit dans le cadre d’une gestion commune de l’uranium et du plutonium par un procéd...
One option under consideration for the recycling of minor actinides is to incorporate about 10% into...
This thesis is part of the research and development program performed at the ALTO facility (Accéléra...
One option envisioned for the future management of high level nuclear waste is the transmutation of ...
Ce travail de thèse s'inscrit dans le cadre de recherches sur le retraitement futur du combustible n...
International audienceThe future management of nuclear ultimate waste requires pellet fabrication of...
Dans le cadre des recherches sur l'aval du cycle du combustible et des projets de transmutation de l...
One of the studied routes to reduce nuclear waste amount, is, after plutonium recycling, americium (...
This study is devoted to the synthesis and the characterization of porous metal oxide microsphere fr...
Une des voies à l’étude permettant de réduire l’inventaire des déchets nucléaires, après recyclage d...
This report gives a synthesis of the work I have carried out or to which I have numerically contribu...
International audienceThis study deals with the preliminary development of a powder-free process cal...
Sintering is a key step in the elaboration of UOx and MOx (U/Pu mixed oxide) nuclear fuels pellets u...
The context of this study is about increasing the performances of nuclear fuel used in existing nucl...
Sintering is a key step during the fabrication of UOx and MOx nuclear fuels used in the PWR reactors...
Cette étude s’inscrit dans le cadre d’une gestion commune de l’uranium et du plutonium par un procéd...
One option under consideration for the recycling of minor actinides is to incorporate about 10% into...
This thesis is part of the research and development program performed at the ALTO facility (Accéléra...