ALEPH2 Monte Carlo burn up code

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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
Publication statusPublished - 19 Sep 2011
EventInternational Conference on Nuclear Criticality (ICNC) - Edinburgh, United Kingdom
Duration: 19 Sep 201123 Sep 2011


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


  • ALEPH, Monte Carlo, depletion, ORIGEN

ID: 150781