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Gas migration from nuclear waste repositories: calculation of vault effective permeability
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It is envisaged that the low and intermediate level waste resulting from Britain's nuclear power generation activities are to be placed in disposal facilities deep underground. After emplacement of waste in the disposal vaults, the facilities will be backfilled and closed. Processes such as corrosion will then result in large quantities of gas being produced within the repository vaults. Many studies have been carried out to investigate the behaviour of the gases in the repository environment. These studies often model the vault containing the waste packages with one set of material parameters which combines the properties of the waste packages and backfill using a volume-weighted average approach. This article introduces a new way of deriving the effective permeability of the vault and examines the effect of the vault design, such as the fill material of the crown space and the permeability of the vault liner, on the calculated  ermeability. The work is carried out with the TOUGH2 software package.
   
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