Analysis of Neutron Emission on PWR Spent Fuel Assemblies for Bum-Up Assessment

J. Debrue, Ch De Raedt, G. Minsart

    Research outputpeer-review

    Abstract

    A series of passive neutron measurements performed on TIHANGEI spent fuel assemblies were analyzed for comparison with calculated bum-up values and neutron emission rates. The bum-up range of these assemblies was between 10 and 45 MWd/kg and the cooling time varied from 1 to 8 years approximately. The measurements, performed with-" U fission chambers, were correlated with neutron emission and bum-up by means of the ORIGEN-2 point model depletion code, taking into account the inadiation history. A fairly good correlation was found between the -'"Cm contributions, as deduced from the measurements corrected with ORIGEN-2, and the burn-up values as calculated with fuel management codes. It was noticed that the ratio of the calculated (ORIGEN-2) neutron emission and the measured neutron detection varied with the bum-up.

    Original languageEnglish
    Title of host publicationReactor Dosimetry
    Subtitle of host publicationMethods, Applications, and Standardization
    EditorsHarry Farrar, Ezra Parvin Lippincott
    PublisherASTM International
    Pages710-719
    Number of pages10
    ISBN (Electronic)9780803111844
    DOIs
    StatePublished - 1989
    Event6th ASTM-Euratom Symposium on Reactor Dosimetry: Methods, Applications, and Standardization - Jackson Hole
    Duration: 31 May 19875 Jun 1987

    Publication series

    NameASTM Special Technical Publication
    VolumeSTP 1001
    ISSN (Print)0066-0558

    Conference

    Conference6th ASTM-Euratom Symposium on Reactor Dosimetry: Methods, Applications, and Standardization
    Country/TerritoryUnited States
    CityJackson Hole
    Period1987-05-311987-06-05

    ASJC Scopus subject areas

    • General Materials Science

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