Monitoring the fast neutrons in a high flux: The case for242Pu fission chambers

P. Filliatre, Christian Jammes, L. Oriol, B. Geslot, L. Vermeeren

    Research outputpeer-review

    Abstract

    Fission chambers are widely used for on-line monitoring of neutron fluxes in irradiation reactors. A selective measurement of a component of interest of the neutron flux is possible in principle thanks to a careful choice of the deposit material. However, measuring the fast component is challenging when the flux is high (up to 1015 n/cm2/s) with a significant thermal component. The main problem is that the isotopic content of a material selected for its good response to fast neutrons evolves with irradiation, so that the material is more and more sensitive to thermal neutrons. Within the framework of the FNDS (Fast Neutron Detector System) project, we design tools that simulate the evolution of the isotopic composition and fission rate for several deposits under any given flux. In the case of a high flux with a significant thermal component, 242Pu is shown after a comprehensive study of all possibilities to be the best choice for measuring the fast component, as long as its purity is sufficient. If an estimate of the thermal flux is independently available, one can correct the signal for that component. This suggests a system of two detectors, one of which being used for such a correction. It is of very high interest when the detectors must be operated up to a high neutron fluence.

    Original languageEnglish
    Title of host publicationANIMMA 2009
    Subtitle of host publication2009 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications
    Publisher IEEE Computer Society and the Association for Computing Machinery
    ISBN (Print)9781424452088
    DOIs
    StatePublished - 2009
    Event2009 - ANIMMA : 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications - CEA, Marseille
    Duration: 7 Jun 200910 Jul 2009

    Publication series

    NameANIMMA 2009 - 2009 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications
    PublisherIEEE

    Conference

    Conference2009 - ANIMMA
    Abbreviated titleANIMMA
    Country/TerritoryFrance
    CityMarseille
    Period2009-06-072009-07-10

    ASJC Scopus subject areas

    • Nuclear Energy and Engineering

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