BOT3P Version 1.0 was originally conceived as a set of standard FORTRAN 77 language programs in order to give the users of the DORT and TORT deterministic transport codes some useful diagnostic tools to prepare and check their input data files. Later versions extended the possibility to produce the geometrical, material distribution and fixed neutron source data to other deterministic transport codes such as TWODANT/THREEDANT of the DANTSYS system, PARTISN and, potentially, to any transport code through BOT3P binary output files that can be easily interfaced (see, for example, the case of the Russian two-dimensional (2D) and three-dimensional (3D) discrete ordinates neutron, photon and charged particle transport codes KASKAD-S-2.S and KATRIN-2.0). BOT3P Version 5.1 introduced important additions specifically addressed to radiation transport analysis far medical applications. BOT3P Version 5.2 (BOT3P-5.2) contains new important graphics capabilities that improve the visualization possibilities of the mesh grids generated by BOT3P itself. A new modulo was also added in order to allow a simpler interface to radiation transport analysis codes. BOT3P was developed up to Version 5.1 on a DIGlTAL UNIX ALPHA 500/333 Workstation, whereas Version 5.2 was developed and tested on Linux openSUSE 10.2 (with FORTRAN g77 compiler). However BOT3P is designed to run on most Linux/UNIX platforms. BOT3P was successfully used not only in some complex neutron shielding and criticality benchmarks but also in power reactor applications (Westinghouse AP1000 internals heating rate distribution calculations by Ansaldo Nucleare (Italy)). All BOT3P versions are publicly available from OECD/NEA Data Bank (F) and most of them are also distributed by ORNL/RSICC (USA).
BOT3P Version 5.2: A Pre/Post-Processor System for Transport Analysis
Orsi, R.
2007-03-08
Abstract
BOT3P Version 1.0 was originally conceived as a set of standard FORTRAN 77 language programs in order to give the users of the DORT and TORT deterministic transport codes some useful diagnostic tools to prepare and check their input data files. Later versions extended the possibility to produce the geometrical, material distribution and fixed neutron source data to other deterministic transport codes such as TWODANT/THREEDANT of the DANTSYS system, PARTISN and, potentially, to any transport code through BOT3P binary output files that can be easily interfaced (see, for example, the case of the Russian two-dimensional (2D) and three-dimensional (3D) discrete ordinates neutron, photon and charged particle transport codes KASKAD-S-2.S and KATRIN-2.0). BOT3P Version 5.1 introduced important additions specifically addressed to radiation transport analysis far medical applications. BOT3P Version 5.2 (BOT3P-5.2) contains new important graphics capabilities that improve the visualization possibilities of the mesh grids generated by BOT3P itself. A new modulo was also added in order to allow a simpler interface to radiation transport analysis codes. BOT3P was developed up to Version 5.1 on a DIGlTAL UNIX ALPHA 500/333 Workstation, whereas Version 5.2 was developed and tested on Linux openSUSE 10.2 (with FORTRAN g77 compiler). However BOT3P is designed to run on most Linux/UNIX platforms. BOT3P was successfully used not only in some complex neutron shielding and criticality benchmarks but also in power reactor applications (Westinghouse AP1000 internals heating rate distribution calculations by Ansaldo Nucleare (Italy)). All BOT3P versions are publicly available from OECD/NEA Data Bank (F) and most of them are also distributed by ORNL/RSICC (USA).I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
