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Corrosion of Carbon-Steel Containers for Heat-Generating Nuclear Waste in Brine Environments Relevant for A Rock-Salt Repository

Published online by Cambridge University Press:  25 February 2011

E. Smailos ,
W. Schwarzkopf ,
B. Kienzler  and
R. KÖster
E. Smailos
Affiliation:
Kernforschungszentrum Karlsruhe GmbH, P.O. Box 3640, W-7500 Karlsruhe 1, GERMANY
W. Schwarzkopf
Affiliation:
Kernforschungszentrum Karlsruhe GmbH, P.O. Box 3640, W-7500 Karlsruhe 1, GERMANY
B. Kienzler
Affiliation:
Kernforschungszentrum Karlsruhe GmbH, P.O. Box 3640, W-7500 Karlsruhe 1, GERMANY
R. KÖster
Affiliation:
Kernforschungszentrum Karlsruhe GmbH, P.O. Box 3640, W-7500 Karlsruhe 1, GERMANY
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Abstract

In previous corrosion studies, carbon steels, especially the fine-grained steel TStE355, were identified as promising materials for heat-generating nuclear waste containers acting as a barrier in a rock-salt repository. In the present study detailed investigations have been performed on fine-grained steel to determine the influence of important parameters on its corrosion behaviour in disposal-relevant salt brines. These parameters are: brine composition (Mg Cl2-rich and NaCI-rich brines), temperature (90°C, 170°C), and salt impurities, such as H2S concentrations of 25 mg/I-200 mg/I salt brine.

Under the conditions of the tests used here, carbon steel was subjected to general corrosion. Pitting and crevice corrosion or stress-corrosion cracking were not observed. The increase in temperature from 90°C to 170°C strongly enhanced the corrosion rate of the steel. In the MgCl2-rich brines, considerably higher rates (37-70 μm/a at 90°C, 200-300 °m/a at 170°C) were observed than in the NaCI-rich brine (5 μm/a at 90°C, 46 μm/a at 170°C). H2S concentrations in the MgCl2-rich Qbrine of up to 200 mg/l did not influence significantly the corrosion rate of the steel. The corrosion rates determined imply corrosion allowances that are technically acceptable for thick-walled containers. In view of these results, fine-grained steel continues to be considered as a promising material for long-lived HLW containers.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 257: Symposium – Scientific Basis for Nuclear Waste Management XV , 1991 , 399
Copyright
Copyright © Materials Research Society 1992

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References

REFERENCES

[1] Smailos, E., “Korrosionsuntersuchungen an ausgewahlten metallischen Werkstoffen als Behaltermaterialien fOr die Endlagerung von hochradioaktiven Abfallprodukten in Steinsalzformationen”, KfK Report No. 3953, 1985.Google Scholar
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