Application of solubility and transport limited radionuclide release in performance assessment of a spent fuel repository in Boom Clay

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Abstract

This report focuses on the modelling assumptions of radionuclide release from a spent fuel (SF) repository from performance assessment (PA) point of view. Radionuclides dissolved in the crystalline UO2 grains of the spent fuel matrix constitute the vast majority of the radionuclide source term and their release will be governed by the matrix dissolution rate. In previous PA studies, fuel matrix dissolution is modelled as a predefined constant-rate process, i.e, all the radionuclides (RNs) are released from the matrix at the same constant rate as the fuel matrix dissolution rate, followed by an independent transport process of RNs which can be solubility limited.

Details

Original languageEnglish
PublisherStudiecentrum voor Kernenergie
Number of pages40
StatePublished - 1 Jan 2016

Publication series

NameSCK•CEN Reports
PublisherStudiecentrum voor Kernenergie
No.ER-294

Keywords

  • spent fuel, modelling assumptions, radionuclide release, performance assessment

ID: 878997