Hostname: page-component-78c5997874-94fs2 Total loading time: 0 Render date: 2024-11-14T17:50:41.568Z Has data issue: false hasContentIssue false

Pitting Studies Under Anoxic Conditions on Candidate Container Materials AISI 316L hMo and UHB 904L for The Disposal of HLW in Argillaceous Formations

Published online by Cambridge University Press:  01 February 2011

Bruno Kursten
Affiliation:
SCK•CEN, The Belgian Nuclear Research Centre, Boeretang 200, B–2400 Mol, Belgium
Frank Druyts
Affiliation:
SCK•CEN, The Belgian Nuclear Research Centre, Boeretang 200, B–2400 Mol, Belgium
Get access

Abstract

Stainless steel is being envisaged as the primary candidate container material for the final disposal of vitrified HLW in deep geological argillaceous formations in Belgium. The impact of an evolving underground repository environment, i.e. a progressive change from oxic to anoxic conditions (due to the consumption of entrapped oxygen), on the pitting behaviour of austenitic stainless steels AISI 316L hMo and UHB 904L was studied. CPP-experiments were performed in synthetic solutions, which are representative for the near-field chemistry of an underground repository. The solutions contained various amounts of Cl- (100–50,000 mg/L) at near-neutral pH. Experiments were conducted at 16 and 90°C.

AISI 316L hMo and UHB 904L will not be subjected to immediate pitting problems neither under oxic, nor under anoxic conditions. However, AISI 316L hMo could present long-term pitting problems under oxic conditions. Pits are much easier initiated on AISI 316L hMo, for both oxic and anoxic conditions. The pits propagate in a rather similar manner under oxic conditions for both alloys, whereas under anoxic conditions the pits formed on AISI 316L hMo are much deeper. AISI 316L hMo is more susceptible to crevice attack.

Type
Research Article
Copyright
Copyright © Materials Research Society 2004

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

1. NIRAS/ONDRAF, SAFIR 2, Safety Assessment and Feasibility Interim Report 2 (2001).Google Scholar
2. Coulon, H., “Propriétés Physico-Chimiques de Sédiments Argileux Français: Contribution au Stockage de Déchets Radioactifs,” PhD thesis, Université des Sciences et Techniques de Lille Flandres-Artois (1987).Google Scholar
3. Dunn, D.S., Cragnolino, G.A., and Sridhar, N., Corrosion 56(1), pp. 90104 (2000).Google Scholar
4. Sridhar, N. and Cragnolino, G.A., Corrosion 49(11), pp. 885894 (1993).Google Scholar
5. Tsujikawa, S. and Kojima, Y., “Repassivation Method to Predict Long Term Integrity of Low Alloy Titanium for Nuclear Waste Package,” in Scientific Basis for Nuclear Waste Management XIV, edited by Abrajano, T. and Johnson, L.H., (Res. Soc. Symp. Proc. 212, Pittsburgh, PA 1991), pp. 261268 Google Scholar