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.
|Title of host publication||Proceedings of the International Conference on Nuclear Criticality Safety|
|Place of Publication||Paris, France|
|State||Published - 19 Sep 2011|
|Event||International Conference on Nuclear Criticality (ICNC) - Edinburgh|
Duration: 19 Sep 2011 → 23 Sep 2011
|Conference||International Conference on Nuclear Criticality (ICNC)|
|Period||2011-09-19 → 2011-09-23|