Standard neutron fields at the BR1-reactor and their application to neutron dosimetry

    Research outputpeer-review

    Abstract

    The concept of the MOL Cavity Fission Spectrum Standard Neutron Field is highlighted. Two applications to neutron dosimetry are treated - Neutron flux determination by distinct fission fragment absolute radiometric measurements on fission foils. - Neutron flux determination by detection of the delayed neutrons emitted by a fissile sample. For both applications the measuring technique, the calibration procedure, the application domain, the advantages of the method as well as the restrictions in absolute neutron flux determination are considered.

    Original languageEnglish
    Pages (from-to)238-242
    Number of pages5
    JournalProceedings of SPIE - The International Society for Optical Engineering
    Volume2339
    DOIs
    StatePublished - 3 Mar 1995
    Event4th International Conference on Applications of Nuclear Techniques: Neutrons and Their Applications 1994 - Crete
    Duration: 12 Jun 1994 → …

    ASJC Scopus subject areas

    • Electronic, Optical and Magnetic Materials
    • Condensed Matter Physics
    • Computer Science Applications
    • Applied Mathematics
    • Electrical and Electronic Engineering

    Cite this