The REBUS experimental programme for burn-up credit

Pierre D'hondt, Klaas Van Der Meer, Peter Baeten, Daniel Marloye, Benoit Lance, Jacques Basselier

    Research outputpeer-review

    Abstract

    An international programme called REBUS (REactivity tests for a direct evaluation of the Burn-Up credit on Selected irradiated LWR fuel bundles) for the investigation of the burn-up credit has been initiated by the Belgian Nuclear Research Center SCK•CEN and Belgonucléaire with the support of USNRC, EdF from France, VGB, representing German nuclear utilities and NUPEC, representing the Japanese industry. The programme aims to establish a neutronic benchmark for reactor physics codes. This benchmark will qualify the codes to perform calculations of the burn-up credit. The benchmark exercise investigates the following fuel types with associated burn-up: • Reference 3.3% enriched UO2 fuel • Fresh commercial PWR UO2 fuel • Irradiated commercial PWR UO2 fuel (51 GWd/tM) • Fresh PWR MOX fuel • Irradiated PWR MOX fuel (20 GWd/tM) Reactivity effects are measured in the critical facility VENUS. Fission rate and flux distributions in the experimental bundles will be determined. The accumulated burn-up of all rods is measured non-destructively in a relative way by gross gamma-scanning, while some rods are examined by gamma-spectrometry for an absolute determination of the burn-up. Some rods will be analyzed destructively with respect to accumulated burn-up, actinides content and TOP-19 fission products (i.e. those non-gaseous fission products that have most implications on the reactivity). Additionally some irradiated rods have undergone a profilometry and length determination. The experimental implementation of the programme has started in 2000 with major changes in the VENUS critical facility. Gamma scans, profilometry, length determination and gamma-spectrometry measurements on the MOX fuel have been performed. In the course of October 2001 the first fresh fuel configuration will be investigated. In the same period the commercial irradiated fuel will arrive at the SCK•CEN hot cells and will be refabricated into fuel rodlets of 1 meter length.
    Original languageEnglish
    Title of host publicationASME Conference Proceedings
    Subtitle of host publication10th International Conference on Nuclear Engineering
    Pages227-234
    Number of pages8
    Volume4
    DOIs
    StatePublished - 2002
    Event2002 - ICONE: 10th International Conference on Nuclear Engineering - Arlington
    Duration: 14 Apr 200218 Apr 2002

    Publication series

    NameInternational Conference on Nuclear Engineering (ICONE)
    PublisherASME

    Conference

    Conference2002 - ICONE
    Abbreviated titleICONE 10
    Country/TerritoryUnited States
    CityArlington
    Period2002-04-142002-04-18

    ASJC Scopus subject areas

    • Nuclear Energy and Engineering

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