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Computations of Temperature Profiles in the Medium/Low-level Waste Cement and in the Rock Salt Surrounding the Disposal Cavern

Published online by Cambridge University Press:  15 February 2011

W. Hauser ,
E. Smailos  and
R. Köster
W. Hauser
Affiliation:
Kernforschungszentrum Karlsruhe GmbH., Institut für Nukleare Entsorgungstechnik, Postfach 3640, D–7500 Karlsruhe, Federal Republic of Germany
E. Smailos
Affiliation:
Kernforschungszentrum Karlsruhe GmbH., Institut für Nukleare Entsorgungstechnik, Postfach 3640, D–7500 Karlsruhe, Federal Republic of Germany
R. Köster
Affiliation:
Kernforschungszentrum Karlsruhe GmbH., Institut für Nukleare Entsorgungstechnik, Postfach 3640, D–7500 Karlsruhe, Federal Republic of Germany
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Extract

Prior to disposal of cemented medium level waste and low level waste in large caverns 1000 m below ground it is important to know what temperatures will be caused by heat generation in the waste product. During the disposal period the heat produced by hydration of the cement used as the binder as well as by decaying radionuclides in the waste may give rise to inadmissibly high temperatures in the waste product resulting in a deterioration of the produc:t qualities. To avoid such undesirable processes, a maximum permissible product temperature of 90°C was specified for the investigations, i.e. a temperature that is significantly below the boiling point of the water contained in the cemented product.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 11: Symposium – Scientific Basis for Nuclear Waste Management V , 1981 , 859
Copyright
Copyright © Materials Research Society 1982

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References

REFERENCES

1. Hauser, W., Smailos, E., Köster, R. (September 1979)Berechnungen zur Wärmeentwicklung bei der Lagerung and Verfestigung von MAW/LAW in großrāumigen Kavernen (Referenzsysteme A und B des “in-situ Projektes”).KfK 2857Google Scholar
2. Kraemer, R.H., Kroebel, R.H., In-situ solidification of low and medium level wastes. Proceedings of this symposium.Google Scholar
3. Ploumen, P., Strickmann, G., Winske, P. (1979) Untersuchungen zur Temperaturentwicklung bei der Endlagerung hochradioaktiver Abfälle. Atomwirtschaft, Jahrg. 24, Nr. 2, S. 85–91.Google Scholar