Approaches to Long-Term Performance Assessment of Deep Underground Disposal of Radioactive Wastes: A European Perspective

1992 ◽  
Vol 294 ◽  
Author(s):  
Trevor J. Sumerling ◽  
David Read

ABSTRACTThe aim of long-term performance assessment (PA) is generally to develop confidence that the disposal system will perform within certain bounds and give rise to acceptably low impacts or risks. The PA procedure must be able to deal with:- uncertainty due to incomplete understanding of the relevant processes;- uncertainty due to limited sampling of the structures and characteristics of the system and especially the geological media;- uncertainty about future conditions and processes leading to changes in the engineered barriers and natural environment that may affect radionuclide release, transport and exposure pathways.A number of approaches have been taken to solving the problem of how to deal with such uncertainties. The differences in approach may be due to the stage of project development, differences in national regulatory guidance and the different r6les of the implementor and the regulator. This paper examines the rôles of the implementor and regulator and discusses possible approaches appropriate to both points of view.

2019 ◽  
Vol 145 (5) ◽  
pp. 04019034 ◽  
Author(s):  
G. Granello ◽  
C. Leyder ◽  
A. Frangi ◽  
A. Palermo ◽  
E. Chatzi

Energy ◽  
2016 ◽  
Vol 107 ◽  
pp. 716-724 ◽  
Author(s):  
Pulin Yeh ◽  
Chu Hsiang Chang ◽  
Naichien Shih ◽  
Naichia Yeh

1993 ◽  
Vol 333 ◽  
Author(s):  
B. Grambow ◽  
Kernforschungszentrum Karlsruhe

ABSTRACTThe current knowledge on the glass dissolution mechanism and the representation of glass dissolution concepts within overall repository performance assessment models are briefly summarized and uncertainties related to mechanism, radionuclide chemistry and parameters are discussed. Understanding of the major glass dissolution processes has been significantly increased in recent years. Long-term glass stability is related to the long-term maintenance of silica saturated conditions. The behavior of individual radionuclides in the presence of a dissolving glass has not been sufficiently and results do not yet allow meaningful predictions. Conservative long-term predictions of glass matrix dissolution as upper limit for radionuclide release can be made with sufficient confidence, however these estimations generally result in a situation were the barrier function of the glass is masked by the efficiency of the geologic barrier. Realistic long-term predictions may show that the borosilicate waste glass contributes to overall repository safety to a much larger extent than indicated by overconservatism. Today realistic predictions remain highly uncertain and much more research work is necessary. In particular the long-term rate under silica saturated conditions needs to be understood and the behavior of individual radionuclides in the presence of a dissolving glass deserves more systematic investigations.


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