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Article
Open AccessCharacterisation of high burnup spent mixed oxide fuel after leaching at hyperalkaline pH in a reducing environment
Microstructural investigations of a Zircaloy-4 clad mixed oxide fuel rod segment with a burnup of 50.3 GWd/tHM after exposure to a synthetic young cementitious water at a hyperalkaline pH of 13.7(2) under reducin...
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Article
Open AccessCaesium and iodine release from spent mixed oxide fuels under repository relevant conditions: Initial leaching results
Autoclave leaching experiments are conducted on three well-characterised, irradiated, and cladded mixed oxide fuel-rod segments with burnups ranging from 29 GWd/tHM to 52 GWd/tHM to investigate the instant releas...
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Article
Open AccessEvolution of the uranium concentration in dissolution experiments with Cr-(Pu) doped UO2 in reducing conditions at SCK CEN
Cr-doped UO2-based model materials were prepared at SCK CEN, mimicking modern LWR fuels, to understand the influence of Cr do** on the spent fuel dissolution behaviour in geological repository conditions. Tests...
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Article
Influence of the alpha radiation on the UO2 dissolution in high pH cementitious waters
To assess the long-term behaviour of spent fuel in conditions of the Belgian Supercontainer design, dissolution tests were performed to determine the solubility and dissolution rate of depleted and Pu-doped UO2 ...
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Article
Dissolution Behaviour of UO2 in Anoxic Conditions. Comparison of Ca-Bentonite and Boom Clay
A general concept for the disposal of spent fuel in clay formations is based on the multibarrier principle. In such concept, the barriers for radionuclides released into the environment are the clay host rock,...
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Article
Effect of Gamma and Alpha Irradiation on the Corrosion of the French Borosilicate Glass SON 68
Corrosion experiments with the French borosilicate glass SON 68 were conducted under gamma (60Co source) and alpha (cyclotron) irradiation conditions. Static tests with glass powder were conducted at 90°C under s...
