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-2.5 and KATRIN-2.0). BOT3P was successfully used in some complex neutron shielding and criticality benchmarks and in power reactor applications such as, for example, in Westinghouse AP 1000 internals heating rate distribution calculations by Ansaldo Nucleare (Italy). BOT3P Version 5.3 (BOT3P-5.3) contains new pre-processor and post processor features required in order to perform the preliminary vessel shielding analysis by deterministic methods in the IRIS(International Reactor Innovative and Secure) project. BOT3P was developed up to Version 5.1 on a DIGITAL UNIX ALPHA 500/333 Workstation and later versions were developed and tested on Linux openSUSE 10.2 (with FORTRAN g77 compiler). However BOT3P is designed to run on all Linux/UNIX platforms. All BOT3P versions are publicly available from OECD/NEA Data Bank (F) and most of them are also distributed by ORNL/RSICC (USA).

B0T3P Version 5.3: A Pre/Post-Processor System for Transport Analysis

Orsi, R.
2008

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-2.5 and KATRIN-2.0). BOT3P was successfully used in some complex neutron shielding and criticality benchmarks and in power reactor applications such as, for example, in Westinghouse AP 1000 internals heating rate distribution calculations by Ansaldo Nucleare (Italy). BOT3P Version 5.3 (BOT3P-5.3) contains new pre-processor and post processor features required in order to perform the preliminary vessel shielding analysis by deterministic methods in the IRIS(International Reactor Innovative and Secure) project. BOT3P was developed up to Version 5.1 on a DIGITAL UNIX ALPHA 500/333 Workstation and later versions were developed and tested on Linux openSUSE 10.2 (with FORTRAN g77 compiler). However BOT3P is designed to run on all Linux/UNIX platforms. All BOT3P versions are publicly available from OECD/NEA Data Bank (F) and most of them are also distributed by ORNL/RSICC (USA).
Rapporto tecnico;Software;Metodi deterministici
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/5296
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