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Communication Dans Un Congrès Année : 2017

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.
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hal-04258507 , version 1 (25-10-2023)

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Paternité - Pas d'utilisation commerciale - Pas de modification

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  • HAL Id : hal-04258507 , version 1

Citer

Gregory Nicaise. Radiological characterization of in-pile irradiated graphite - Metrological problem, mathematical method and physical modelisation. Technical meeting on the International Project on Irradiated Graphite Processing Approahces (GRAPA), International Atomic Energy Agency, Jun 2017, Vienna (AUSTRIA), Austria. ⟨hal-04258507⟩

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