Lessons learned from in situ corrosion experiments in the HADES URL

Author:

Kursten Bruno1ORCID,Caes Sébastien1,de Souza Valdir1,Gaggiano Roberto2

Affiliation:

1. SCK CEN, Belgian Nuclear Research Centre, Institute for Environment, Health and Safety, Boeretang 200, B-2400 Mol, Belgium

2. ONDRAF/NIRAS, Kunstlaan 14, B-1210 Brussels, Belgium

Abstract

Abstract A wide range of metals have been studied as a candidate container material to be considered in the geological disposal concept of high-level radioactive waste and spent fuel in Belgium. More than 40 years ago, SCK CEN started studies on the corrosion of these metals. The HADES underground research laboratory (URL) played an important role in the corrosion research as it enabled in situ corrosion experiments to be carried out that simulate realistic disposal conditions as closely as possible. These experiments consisted of placing metallic coupons on a steel support tube, heated from the inside, that was installed in Boom Clay, thereby exposing the coupons to various conditions representative of the disposal concept that was considered at that time. Test durations lasted from 6 months to approximately 7.5 years. This paper summarizes the results from the various corrosion studies and discusses their implications in the choice of disposal concept. One of the main outcomes of these experiments was a change of rationale regarding the choice of the container material from carbon steel (corrosion-allowance) to stainless steel (corrosion-resistant). The main arguments for this change were the need to avoid severe pitting corrosion during the aerobic period and to minimize the generation of hydrogen gas during the subsequent anaerobic period.

Publisher

Geological Society of London

Subject

Geology,Ocean Engineering,Water Science and Technology

Reference80 articles.

1. Accary, A. (ed.) 1985. Corrosion Behaviour of Container Materials for Geological Disposal of High Level Radioactive Waste. Report EUR 9836 EN. Commission of the European Communities, Brussels.

2. Aertsens M. and Valcke E. 2009. CORALUS: An Integrated in situ Corrosion Test onα-Active Glass Phase 2004–2008 – Topical Report on the fitting of the SIMS Profiles of the U/Th-doped SON68 Glass Samples. Report SCK•CEN-ER-97. SCK CEN Mol Belgium.

3. Atkinson A. and Marsh G.P. 1991. Engineered Barriers: Current Status. NIREX Safety Studies Report NSS/G102 (available from UK Nuclear Decommissioning Authority).

4. SELFRAC: Experiments and conclusions on fracturing, self-healing and self-sealing processes in clays

5. Development of the Supercontainer Design for Deep Geological Disposal of High-Level Heat Emitting Radioactive Waste in Belgium

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