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Home / Publications / Journals / Nuclear Science and Engineering / Volume 150 / Number 3

BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0

Roberto Orsi

Nuclear Science and Engineering / Volume 150 / Number 3 / July 2005 / Pages 368-373

Computer Code Abstract /

BOT3P consists of 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 3.0 introduced some 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, THREEDANT, and PARTISN, and in the case of X-Y-Z mesh grids, a geometrical input to the MCNP Monte Carlo transport code, starting from the same input to BOT3P.

BOT3P Version 4.0 extends the modeling capabilities of previous BOT3P versions, reduces CPU times, and facilitates the debugging of the computer code input. Version 4.0 also produces the geometrical entries for the sensitivity code SUSD3D, for both Cartesian and cylindrical geometries, and stores the fine-mesh arrays and the material zone map in a binary file, the contents of which can be visualized by the graphics modules of BOT3P. This new feature makes interfacing to any deterministic and Monte Carlo transport code easy and might open new promising application fields to this package.

BOT3P was developed on a DIGITAL UNIX ALPHA 500/333 workstation and successfully used in some complex neutron shielding and criticality benchmarks. It was also tested on Red Hat Linux 7.1 and is designed to run on most UNIX platforms. All BOT3P versions are publicly available from the Organization for Economic Cooperation and Development/Nuclear Energy Agency Data Bank.

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