Published 1967 | Version v1
Report Open

The determination by irradiation with a pulsed neutron generator and delayed neutron counting of the amount of fissile material present in a sample

  • 1. Commissariat a l'Energie Atomique, Saclay (France). Centre d'Etudes Nucleaires

Description

A preliminary study was conducted to determine the amount of fissile material present in a sample. The method used consisted in irradiating the sample by means of a pulsed neutron generator and delayed neutron counting. Results show the validity of this method provided some experimental precautions are taken. Checking on the residual proportion of fissile material in leached hulls seems possible. (authors)

Availability note (English)

Available from INIS in electronic form

Abstract (French)

Ce rapport rend compte d'une etude preliminaire effectuee en vue de determiner la quantite de matiere fissile presente dans un echantillon. La methode utilisee consiste a irradier l'echantillon considere au moyen d'une source puisee de neutrons et a compter les neutrons retardes produits. Les resultats obtenus permettent de conclure a la validite de la methode moyennant certaines precautions. Un controle de la teneur residuelle en matiere fissile des gaines apres traitement semble possible. (auteurs)

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Additional details

Additional titles

Original title (French)
Determination de la quantite de matiere fissile presente dans un echantillon par irradiation au moyen d'une source pulsee de neutrons et comptage des neutrons retardes

Publishing Information

Imprint Pagination
[91 p.]
Report number
CEA-R--3272

Optional Information

Notes
6 refs.