Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

Article English OPEN
Gonzalez Robles, E.; Serrano Purroy, D.; Sureda, R.; Casas Pons, Ignasi; Pablo Ribas, Joan de;
(2015)
  • Publisher: Elsevier
  • Identifiers: doi: 10.1016/j.jnucmat.2015.05.012
  • Subject: high burn-up | fission-gas release | Instant release fraction | grain-boundary | Radioactive waste canisters | Static leaching | candu fuels | geological disposal | Combustibles nuclears gastats -- Emmagatzematge -- Mesures de seguretat | :Enginyeria química [Àrees temàtiques de la UPC] | source-term model | temperature air oxidation | Gap contribution | uo2 fuel | oxide fuels | behavior | Spent nuclear fuel

The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercises to govern the dose that could arise from the repository. A conservative definition of IRF comprises the total inventory of radionuclides located in the gap, fractures, ... View more
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