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Tritium Release Reduction and Radiolysis Gas Formation

Gaƫl Batifol, Christophe Douche, Christophe Sejournant

Fusion Science and Technology / Volume 54 / Number 1 / July 2008 / Pages 205-208

Technical Paper / Waste Handling

At CEA Valduc, the usual tritiated waste container is the steel drum. It allows good release reduction performance for middle activity waste but in some cases tritium outgassing from the waste drums is too high. It was decided to overpackage each drum in a tighter container called the over-drum. According to good safety practices it was also decided to measure gas composition evolution into the over-drum in order to detect hydrogen formation over time. After a few months, a significant release reduction was observed. Additionally there followed contamination reduction in the roof storage building rainwater. However hydrogen was also observed in some over-drums, in addition to other radiolysis products. Catalyst will be added to manage the hydrogen risk in the over-drums.

 
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