ATTILA® – Deterministic Radiation Transport Software System
I first heard of ATTILA® in 2004 when my colleague brought the information from a conference.
For the modelling of the TRIGA reactor for designing an irradiation facility for the BNCT I made several attempts with MCNP. By discussing these we thought that something like the commercial CFD programs should exist for radiation transport issues. So I desided to try it with ATTILA®.
Since then for ATTILA® were made big improvements and developments.
Besides its graphical user interface it is extremly powerful in parallel mode on a cluster. We calculated finally with 80 cores the detailled activation, waste quantities and dose distribution for the structural materials of a PWR and in a further project even for the components in the surrounding area.
Today ATTILA® is highly interesting also due to its interface to MCNP. That way we can connect the functionalities of both program systems. With ATTILA® or rather ATTILA4MC® we may generate by now very comfortable the MCNP input, with the variance reduction, geometry and source definition.