Expected total counts for the Self-Interrogation Neutron Resonance Densitometry measurements of spent nuclear fuel

Riccardo Rossa, Alessandro Borella, Pierre-Etienne Labeau, Nicolas Pauly, Klaas van der Meer

    Research outputpeer-review


    This poster is focused on the estimation of the total neutron counts that can be achieved ideally with the SINRD measurements of spent nuclear fuel. The contributions compares different detector types and SINRD filters that are used to measure the neutron flux in the fast and in the resonance energy region. Fission chambers using 239Pu or 235U as active material and proportional counters containing 3He or 10B were compared. The fission chambers obtained the highest sensitivity to the 239Pu content, whereas the proportional counters showed the highest total neutron counts.
    Original languageEnglish
    Title of host publicationProceedings of the 2015 ANIMMA conference
    Place of PublicationPortugal
    StatePublished - Apr 2015
    Event2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications: International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications - Lisbon
    Duration: 20 Apr 201524 Apr 2015


    Conference2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications

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