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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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Open AccessAccelerated dissolution of doped UO2-based model systems as analogues for modern spent nuclear fuel under repository conditions
Systematic single-effect dissolution studies were carried out on the dissolution behaviour of pure and Cr- or Nd-doped UO2 reference pellets as model materials for spent nuclear fuel with varying do** levels, d...