AbstractThe effects of Pu content on the dissolution rate and the mass of the insoluble residue of irradiated mixed oxide fuel were studied. On the basis of the kinetic analysis assuming the surface-area model, the dissolution rate was found to decrease exponentially with an increase of the Pu content, but those were estimated to be up to 103 times larger than non-irradiated fuels. The mass of the insoluble residue tended to increase with an increase of the Pu content, possibly due to the promotion of fission product formation and an increase of refractory Pu enriched zone
International audienceStudies dedicated to the chemical durability of spent nuclear fuel are usually...
In the safety case for the geological disposal of nuclear waste, the release of radioactivity from t...
In the safety case for the geological disposal of nuclear waste, the release of radioactivity from t...
International audienceSodium fast nuclear reactors might operate with MOX fuels containing up to 45%...
International audienceSeveral (U$_{1-x}$Pu$_x$)O$_{2±δ}$ powders with different morphologies and dif...
International audienceFast Reactors (FR) are considered in the future to fully exploit the uranium r...
This doctoral thesis is focused on radiation induced oxidative dissolution of UO2, Pd-doped UO2, SIM...
Small-scale tests with irradiated Zircaloy-clad fuels from Robinson, Oconee, Saxton, and Point Beach...
The typical flowsheet for reprocessing LMFBR fuel is described. The behavior during shearing, voloxi...
Le principal objectif de cette étude est d'acquérir des données de base sur la dissolution de compos...
Although a spent nuclear fuel is composed of about 96 wt. % of UO2, its composition and microstructu...
During the peaceful use of nuclear energy high level wastes, which contain long-lived radionuclides ...
International audienceFew studies exist concerning the alteration of Mimas Mixed-OXide (MOX) fuel, a...
International audienceAn important RandD program on reprocessing of MOX nuclear fuels is on-going at...
Voloxidation is a proposed head-end process to remove tritium from irradiated LWR fuel by roasting t...
International audienceStudies dedicated to the chemical durability of spent nuclear fuel are usually...
In the safety case for the geological disposal of nuclear waste, the release of radioactivity from t...
In the safety case for the geological disposal of nuclear waste, the release of radioactivity from t...
International audienceSodium fast nuclear reactors might operate with MOX fuels containing up to 45%...
International audienceSeveral (U$_{1-x}$Pu$_x$)O$_{2±δ}$ powders with different morphologies and dif...
International audienceFast Reactors (FR) are considered in the future to fully exploit the uranium r...
This doctoral thesis is focused on radiation induced oxidative dissolution of UO2, Pd-doped UO2, SIM...
Small-scale tests with irradiated Zircaloy-clad fuels from Robinson, Oconee, Saxton, and Point Beach...
The typical flowsheet for reprocessing LMFBR fuel is described. The behavior during shearing, voloxi...
Le principal objectif de cette étude est d'acquérir des données de base sur la dissolution de compos...
Although a spent nuclear fuel is composed of about 96 wt. % of UO2, its composition and microstructu...
During the peaceful use of nuclear energy high level wastes, which contain long-lived radionuclides ...
International audienceFew studies exist concerning the alteration of Mimas Mixed-OXide (MOX) fuel, a...
International audienceAn important RandD program on reprocessing of MOX nuclear fuels is on-going at...
Voloxidation is a proposed head-end process to remove tritium from irradiated LWR fuel by roasting t...
International audienceStudies dedicated to the chemical durability of spent nuclear fuel are usually...
In the safety case for the geological disposal of nuclear waste, the release of radioactivity from t...
In the safety case for the geological disposal of nuclear waste, the release of radioactivity from t...