ALEPH2 Monte Carlo burn up code

    Research outputpeer-review


    ALEPH is a Monte Carlo burn up code under development at SCK-CEN. The first version (ALEPH1) was a coupling between MCNP/X and ORIGEN. Based on neutron spectra calculated by MCNP/X, a one-group cross section library would be generated to be used for the depletion calculations in ORIGEN. In the current version, ALEPH2, the dependence on ORIGEN has been removed and the depletion part is handled by a stiff ODE solver from the RADAU family. Next to this, many other improvements have been made.
    Original languageEnglish
    Title of host publicationProceedings of the International Conference on Nuclear Criticality Safety
    Place of PublicationParis, France
    StatePublished - 19 Sep 2011
    EventInternational Conference on Nuclear Criticality (ICNC) - Edinburgh
    Duration: 19 Sep 201123 Sep 2011


    ConferenceInternational Conference on Nuclear Criticality (ICNC)
    Country/TerritoryUnited Kingdom

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