Abstract. Deaerated 5 M NaCl soluti n is irradiated in the presence of UO2 pellets with a-radiation from 238Pu. Experiments are conducted with 238Pu doped pellets and others with 238Pu dissolved in the brine. The radiolysis products and yields of mobi-lized U and Pu from the oxidative dissolut on of UO2 are determined. Results found for radiolysis products and for the oxidation/dissolution of pellets immersed in Pu containing brine are similar to results for Pu doped pellets, where the radiation chemi-cal processes occur only in the liquid layer of some 10mm thickness adjacent to the pellet. The yield of radiolysis products is comparable to earlier results, that of mobi-lized U from the pellets is < 1 % of the total amount of oxidized sp...
This doctoral thesis is focused on radiation induced oxidative dissolution of UO2, Pd-doped UO2, SIM...
Irradiated UO/sub 2/ was processed for recycle by one version of the Salt Cycle Process. The irradia...
The effects of hydrogen peroxide, H2O2, on UO2 corrosion is investigated in aerated deionized water ...
In the near-field chemistry of a salt repository, the radiolytically-induced redox reactions in conc...
In the near-field chemistry of a salt repository, the radiolytically-induced redox reactions in conc...
In the near-field chemistry of a salt repository, the radiolytically-induced redox reactions in conc...
To assess the impact of alpha radiolysis of water on the oxidative dissolution of UO2 under anoxic c...
In order to determine the long-term performance of spent fuel during direct disposal, high burnup fu...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
In the event of inundation of a nuclear waste repository located in a geological salt formation, chl...
International audienceThe aim of this work was to study the separate effect of fission fragment dama...
This doctoral thesis is focused on radiation induced oxidative dissolution of UO2, Pd-doped UO2, SIM...
Irradiated UO/sub 2/ was processed for recycle by one version of the Salt Cycle Process. The irradia...
The effects of hydrogen peroxide, H2O2, on UO2 corrosion is investigated in aerated deionized water ...
In the near-field chemistry of a salt repository, the radiolytically-induced redox reactions in conc...
In the near-field chemistry of a salt repository, the radiolytically-induced redox reactions in conc...
In the near-field chemistry of a salt repository, the radiolytically-induced redox reactions in conc...
To assess the impact of alpha radiolysis of water on the oxidative dissolution of UO2 under anoxic c...
In order to determine the long-term performance of spent fuel during direct disposal, high burnup fu...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
In the event of inundation of a nuclear waste repository located in a geological salt formation, chl...
International audienceThe aim of this work was to study the separate effect of fission fragment dama...
This doctoral thesis is focused on radiation induced oxidative dissolution of UO2, Pd-doped UO2, SIM...
Irradiated UO/sub 2/ was processed for recycle by one version of the Salt Cycle Process. The irradia...
The effects of hydrogen peroxide, H2O2, on UO2 corrosion is investigated in aerated deionized water ...