No CrossRef data available.
Article contents
In-Situ Corrosion Studies on Cast Steel High-Level Waste Containers Plated with Titanium/Nickel-Alloys
Published online by Cambridge University Press: 25 February 2011
Abstract
Previous corrosion studies have shown that the passive alloys Ti 99.8-Pd and Hastelloy C4 are the most promising corrosion protection materials for long-term resistant carbon-steel containers for the disposal of heat-generating wastes in rock salt formations. Consequently, these materials are subject to more detailed investigations. The influence of selected container manufacturing characteristics (sealing technique, application mode of the corrosion protecting layer on the steel) on the corrosion behaviour of Ti 99.8-Pd and Hastelloy C4was studied using in-situ experiments. The corrosion resistance of the materials was examined both in NaCI brine and MgCl2-rich brine, which might enter into an HLW borehole under certain disposal conditions. Four electron-beam welded cast-steel tubes plated with corrosion protection layers made of Ti 99.8-Pd and Hastelloy C4, respectively, were stored for 18 months in 2-m deep heated boreholes in the Asse salt mine. The annular gap between the tubes and the borehole wall was filled with saturated NaCl-brine or Qbrine (MgCl2-rich). The vertical temperature profile in the boreholes ranged from 90°C to 200°C
In the cast-steel tube with a corrosion protection of Ti 99.8-Pd, no indication of corrosion was observed on the EB-welds or on the explosion plated material in both brines. The cast-steel tube with a corrosion protection of Hastelloy C4 also was found to be resistant to any kind of corrosion in the NaCl-brine. In the MgCl2-rich brine, however, small pitting corrosion of 15 pm was observed after 1.5 years on the passive surface layer that was formed.
On the basis of these results, Ti 99.8-Pd continues to be considered as a promising corrosion protection material for long-lived HLW containers.
- Type
- Research Article
- Information
- Copyright
- Copyright © Materials Research Society 1992
References
REFERENCES
[1]
Sicherheitskriterien für die Endlagerung radioaktiver Abfälle in einem Bergwerk, Bundesanzeiger
35, No. 2, p. 45 (1983).Google Scholar
[2]
Smailos, E., Schwarzlo-opf, W., Köster, R., “Corrosion behaviour of container materials for the disposal of high-level wastes in rock salt formations”, Nuclear Science and Technology, CEC-Report, EUR
10400 (1986).Google Scholar
[3]
Schwarzkopf, W., Smailos, E., Koster, R., “Lang zeitbestandige Korrosionsschutzumhüllung for dicht verschlossene Gebinde mit hochradioaktivem In-halt”, DE-OS 34
47
278 (June1986).Google Scholar
[4]
Schwarzkopf, W., Köster, R., “Langszylindrischer Behalter fur die Endla gerung von einer oder mehreren mit hochradioaktiven Abfallen gef011ten Kokillen”, DE-OS 36
10
862 (Oktober 1987).Google Scholar
[5]
Schwarzkopf, W., Smailos, E., Köster, R., “In-Situ Corrosion Studies on Cast Steel for a High-Level Waste Packaging in a Rock-Salt Repository”, Mat. Res. Symp., Proc. Vol. 127, pp. 411–418, Materials Research Society (1988).CrossRefGoogle Scholar
[6]
Marsh, G.P., Pinard-Legry, G., Smailos, E.
et al. “HLW Container Corrosion and Design”, Proc. of the Second European Community Conference on Radioactive Waste Management and Disposal, Luxembourg, April 22-26, 1985, p. 314.Google Scholar
[7]
Schmitt, R.E., Koster, R., “Elektrochemische Korrosionsuntersuchungen an metallischen Verpackungsmaterialien fur hochaktive Abfèlle. Verhalten von Hastelloy C4 in quinarer Salzlösung und 1M NaCl”, KfK Report No.4039, 1986.Google Scholar
[8]
Smailos, E., Koster, R., “Corrosion Studies on Selected Packaging Materials for Disposal of High-Level Wastes”, Proc. of a Technical Committee Meeting of the IAEA on Materials Reliability in the Back End of the Nuclear Fuel Cycle, Vienna, September 2-5, 1986, IAEA-Tecdoc-421, p. 7.Google Scholar