BOT3P is a set of standard FORTRAN 77 language programs developed at the ENEA-Bologna Nuclear Data Centre. BOT3P Version 1.0 was originally conceived to give the users of the DORT and TORT deterministic transport codes some useful diagnostic tools to prepare and check their input data files. BOT3P Version 2.0 involved important additions in the input geometrical model description and extended the possibility to produce the geometrical, material distribution and fixed neutron source data to the deterministic transport codes TWODANT and THREEDANT of the DANTSYS system too, starting from the same input to BOT3P. BOT3P Version 3.0 further improved the geometrical capabilities with the possibility to include in a new mode! geometries coming from other DORT/TORT input files or derived from computerized tomography (C.T.) scans. BOT3P Version 3.0 could also generate a geometrical input far the MCNP Monte Carlo transport code, when users required X-Y-Z TORT/THREEDANT mesh grids to be generated. BOT3P Version 4.0 greatly improves the geometrical and modelling capabilities of previous BOT3P versions by also reducing CPU times. It produces the geometrical entries far the sensitivity code SUSD3D, for both Cartesian and cylindrical geometries and it also stores the geometrical entries in a binary file to be easily interfaced with any other transport code. Moreover this binary file content can be visualized by the graphics modules of BOT3P. Version 4.0 includes new modules, suggested or prepared by Adrien Bidaud from Institut de Physique Nucleaire Orsay (France) in order both to deal with the RTFLUX file of DANTSYS and to describe a more general neutron source input. BOT3P was developed on a DIGITAL UNIX ALPHA 500/333 Workstation and successfully used in some complex neutron shielding and criticality benchmarks. BOT3P was also tested on Red Hat Linux 7.1 and is designed to run on most UNlX platforms. All BOT3P versions are publicly available from OECD/NEA Data Bank.

BOT3P Version 4.0: The ENEA Bologna Pre/Post-Processors of the DORT, TORT, TWODANT, THREEDANT Transport Codes

Orsi, R.
2004

Abstract

BOT3P is a set of standard FORTRAN 77 language programs developed at the ENEA-Bologna Nuclear Data Centre. BOT3P Version 1.0 was originally conceived to give the users of the DORT and TORT deterministic transport codes some useful diagnostic tools to prepare and check their input data files. BOT3P Version 2.0 involved important additions in the input geometrical model description and extended the possibility to produce the geometrical, material distribution and fixed neutron source data to the deterministic transport codes TWODANT and THREEDANT of the DANTSYS system too, starting from the same input to BOT3P. BOT3P Version 3.0 further improved the geometrical capabilities with the possibility to include in a new mode! geometries coming from other DORT/TORT input files or derived from computerized tomography (C.T.) scans. BOT3P Version 3.0 could also generate a geometrical input far the MCNP Monte Carlo transport code, when users required X-Y-Z TORT/THREEDANT mesh grids to be generated. BOT3P Version 4.0 greatly improves the geometrical and modelling capabilities of previous BOT3P versions by also reducing CPU times. It produces the geometrical entries far the sensitivity code SUSD3D, for both Cartesian and cylindrical geometries and it also stores the geometrical entries in a binary file to be easily interfaced with any other transport code. Moreover this binary file content can be visualized by the graphics modules of BOT3P. Version 4.0 includes new modules, suggested or prepared by Adrien Bidaud from Institut de Physique Nucleaire Orsay (France) in order both to deal with the RTFLUX file of DANTSYS and to describe a more general neutron source input. BOT3P was developed on a DIGITAL UNIX ALPHA 500/333 Workstation and successfully used in some complex neutron shielding and criticality benchmarks. BOT3P was also tested on Red Hat Linux 7.1 and is designed to run on most UNlX platforms. All BOT3P versions are publicly available from OECD/NEA Data Bank.
Rapporto tecnico;Software;Metodi deterministici per la neutronica
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/6993
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