Preliminary safety analysis gorieben: Source terms for heat-producing wastes

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Output type: Conference proceedings article

Author list: Kienzier B., Altmaier M., Bube C., Metz V.

Publication year: 2013

Volume number: 2

Start page: 709

End page: 716

Number of pages: 8

ISBN: 9781627486446

URL: http://api.elsevier.com/content/abstract/scopus_id:84886927617

Abstract

A preliminary safety analysis for a potential radioactive waste repository in the German Gorleben salt dome was performed. This analysis summarized all available information on the salt dome and the results of exploration activities to date. The main goal was to develop a clear documentation, whether the Gorleben site was qualified for complying with the German safety requirements for the disposal of heat-generating, radioactive waste. Therefore, the project was focused on long-term safety and a transparent evaluation, whether and under which circumstances it would be possible to dispose off heat-generating waste in the salt dome. The source term is based on kinetic and thermodynamic mobilization/retention processes and on the influence of temperature on these processes. Maximum expected solution concentrations of the radionuclides Am, Th, U, Np, Pu, Tc, Zr, and rare earth elements were derived for a simplified scenario. This scenario did not include the presence of carbonate and elevated temperature effects were not treated explicitly. Maximum radionuclide concentrations were assessed for 5 M NaCl solution at pH 6 and 9 and for 4.5 MMgCl solution for the same pH values.

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