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Conference Article: Radiolytic corrosion of graphite surveillance and lessons drawn from the operation of the BUGEY-1 reactor

Petit, A. (Electricite de France (EDF), 01 - Loyettes (France). Centrale de Bugey); Phalippou, C.; Brie, M. (CEA Centre d'Etudes de Saclay, 91 - Gif-sur-Yvette (France))

Abstract

This document briefly describes some of the feedback of experience from operation of the BUGEY-1 reactor. There is a major radiolytic corrosion problem with the graphite of the stack of this reactor and small quantities of methane are added to the coolant gas to limit its effect. Inhibition with methane has the drawback of resulting in hydrocarbon deposits forming on the fuel elements, which makes it necessary to periodically eliminate them by injecting oxygen. The amount of weight loss is determined by annually taking core samples from the channel walls. Additional examinations are made, on completing each core drilling session, of the core samples with the highest corrosion factors: determination of the density profiles (and verification of weight loss) by gamma ray absorption. Measurement of the compressive strength (perpendicularly to the channel wall). Hydrogen analysis (on a few samples). Identical examinations are made on samples taken for the purpose parallel to the channel wall.

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key words: bugey-1 reactor; corrosion products; corrosion; deposition; graphite; methane; monitoring; oxygen; radiolysis; reactor components; carbon; gas cooled reactors; gcr type reactors; graphite moderated reactors

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Reference:

Specialists' meeting on the status of graphite development for gas cooled reactors. Tokai, Ibaraki (Japan). 9-12 Sep 1991

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--690, pp:265-272