Correlation Analysis with Neutron Count Distribution for a Paralyzing Dead-Time Counter for the Assay of Spontaneous Fissioning Material

Author:

Hage W.1,Cifarelli D. M.2

Affiliation:

1. Commission of the European Communities, Joint Research Centre Safety Technology Institute, 121020 Ispra (Va), Italy

2. Universita L. Bocconi, Istituto di Metodi Quantitativi, 120136 Milano, Italy

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference28 articles.

1. Dénombrement de processus nucléaires comportant l'émission simultanée de plusieurs neutrons

2. G. BIRKHOFF, L. BONDAR, J. LEY, R. BERG, R. SWENNEN, and G. BUSCA, “On the Determination of the240Pu in Solid Waste Containers by Spontaneous Fission Neutron Measurements. Application to Reprocessing Plant Waste,” EUR-5158e, Commission of the European Communities, Joint Research Centre, Ispra (1974).

3. K. BöHNEL, “Die Plutoniumbestimmung in Kernbrennstoffen mit der Neutronen-Koinzidenzmethode,” KFK-2203, Kernforschungszentrum Karlsruhe (1975).

4. Neutron Signal Multiplet Analysis for the Mass Determination of Spontaneous Fission Isotopes

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