Radiological characterization of in-pile irradiated graphite - Metrological problem, mathematical method and physical modelisation
Résumé
The presentation deals with theoretical computation of irradiation of high purity graphite used in french "UNGG" reactors (graphite moderated and gas cooled).
Methods and résultats are presented.
The striking result is that Be-10 is the mainly long term contributor to activity of irradiated graphite and that Be-9 is the main stable element resulting from graphite activation.
Origine : Fichiers produits par l'(les) auteur(s)
Licence : CC BY NC ND - Paternité - Pas d'utilisation commerciale - Pas de modification
Licence : CC BY NC ND - Paternité - Pas d'utilisation commerciale - Pas de modification