Hostname: page-component-586b7cd67f-dsjbd Total loading time: 0 Render date: 2024-11-28T16:26:27.370Z Has data issue: false hasContentIssue false
  • English
  • Français

Radioelement Solubilities in SR-Site, the Influence of Variability and Uncertainty

Published online by Cambridge University Press:  18 January 2013

Christina Greis Dahlberg ,
Patrik Sellin ,
Mireia Grivé ,
Lara Duro  and
Kastriot Spahiu
Christina Greis Dahlberg
Affiliation:
Svensk Kärnbränslehantering AB, Swedish Nuclear Fuel and Waste Management Co, Box 250, SE-101 24 Stockholm, Sweden
Patrik Sellin
Affiliation:
Svensk Kärnbränslehantering AB, Swedish Nuclear Fuel and Waste Management Co, Box 250, SE-101 24 Stockholm, Sweden
Mireia Grivé
Affiliation:
Amphos 21,Consulting S.L. Passeig de García i Faria, 49-51, E08019 Barcelona, Spain
Lara Duro
Affiliation:
Amphos 21,Consulting S.L. Passeig de García i Faria, 49-51, E08019 Barcelona, Spain
Kastriot Spahiu
Affiliation:
Svensk Kärnbränslehantering AB, Swedish Nuclear Fuel and Waste Management Co, Box 250, SE-101 24 Stockholm, Sweden
Get access

Abstract

If groundwater enters a damaged canister and comes in contact with the spent fuel, radionuclides are released into the water in the void inside the canister when fuel dissolves. Solubility limits restrict the amount of radioelements that may migrate with the water flowing from the canister. In this study the impact of variability in groundwater chemistry compositions and the impact of uncertainties in thermodynamic data on solubility limits for Np, Pb, Pu, Ra, Se, Th, U and Zr were looked into. The solubility limits for all the studied radioelements seemed to be more sensitive to uncertainties in thermodynamic data than to differences in groundwater chemistry. The sole exception was radium, where variability in water composition has a somewhat larger impact. Radium is also the most safety critical element in the safety assessment SR-Site and groundwater compositions are expected to vary during the assessment period of one million years.

Keywords

Rawaternuclear materials
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1518: Symposium LL – Scientific Basis for Nuclear Waste Management XXXVI , 2012 , pp. 179 - 184
Copyright
Copyright © Materials Research Society 2013 

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

SKB. Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report of the SR-Site project. SKB TR-11–01, Svensk Kärnbränslehantering AB (2011).Google Scholar
SKB. Radionuclide transport report for the safety assessment SR-Site. SKB TR-10–50, Svensk Kärnbränslehantering AB (2010).Google Scholar
@RISK, Risk analysis and simulation add-in for Microsoft Excel, Palisade Corporation, USA. www.palisade.com Google Scholar
Grivé, M, Domènech, C, Montoya, V, Garcia, D and Duro, L. Simple Functions Spreadsheet tool presentation. SKB TR-10–61, Svensk Kärnbränslehantering AB (2010).Google Scholar
Hummel, W, Berner, U, Curti, E, Pearson, F and Thoenen, T. NAGRA/PSI Chemical Thermodynamic Data Base 01/01, Universal Publishers (2002).CrossRefGoogle Scholar
Duro, L, Grivé, M, Cera, E, Domenech, C and Bruno, J. Update of a thermodynamic database for radionuclides to assist solubility limits calculation for performance assessment. SKB TR-06–17, Svensk Kärnbränslehantering AB (2006).Google Scholar
Duro, L, Grivé, M, Cera, E, Gaona, X, Domènech, C and Bruno, J. Determination and assessment of the concentration limits to be used in SR-Can. SKB TR-06–32, Svensk Kärnbränslehantering AB, (2006).Google Scholar
Grivé, M, Domènech, C, Montoya, V, Garcia, D and Duro, L. Determination and assessment of the concentration limits to be used in SR-Can. Supplement to TR-06-32. SKB R-10–50, Svensk Kärnbränslehantering AB (2010).Google Scholar