H-3 Measurement in Radioactive Wastes: Efficiency of the Pyrolysis Method to Extract Tritium from Aqueous Effluent, Oil, and Concrete

S. Guégan (1, 2) , R. Brennetot (3, 2) , M. Giuliani (2) , S. Guegan (2) , P. Fichet (2) , L. Chiri (4) , P. Deloffre (2) , A. Masset (2) , C. Mougel (2) , F. Bachelet (4)

1 LUBEM - Laboratoire Universitaire de Biodiversité et Ecologie Microbienne
2 CEA-DES (ex-DEN) - CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)
3 LANIE - Laboratoire de développement Analytique Nucléaire Isotopique et Elémentaire
4 CEA-Valduc - Centre CEA de Valduc

Tritium measurement in nuclear waste is a key to determine the type of repository. This paper describes the methodology used to validate tritium measurement in various matrices using pyrolysis method with a new instrument available in the market. The efficiency obtained for tritium recovery in aqueous matrix, oil and concrete are respectively higher than 95 per cent, 93 per cent and 85 per cent.

Mots clés: trititum

Domaines: Physique Nucléaire Théorique [nucl-th]; Physique Nucléaire Expérimentale [nucl-ex]

S. Guégan, R. Brennetot, M. Giuliani, S. Guegan, P. Fichet, et al.. H-3 Measurement in Radioactive Wastes: Efficiency of the Pyrolysis Method to Extract Tritium from Aqueous Effluent, Oil, and Concrete. Fusion Science and Technology, 2017, 71 (3), pp.397-402. ⟨10.1080/15361055.2017.1291242⟩. ⟨cea-02388596⟩