BOT3P consists of a set of standard FORTRAN 77 language programs that gives the users of the deterministic transport codes DORT and TORT some useful diagnostic tools to prepare and check the geometry of their input data files for both Cartesian and cylindrical geometries inc1uding graphical display modules. BOT3P produces at the same time the geometrical and material distribution data for the deterministic transport codes TWODANT and THREEDANT and, only in three-dimensional (3D) Cartesian geometry, for the Monte Carlo Transport Code MCNP. This makes it possible to compare directly for the same geometry the effects stemming from the use of different data libraries and solution approaches on transport analysis resu1ts. Through the lise of BOT3P, radiation transport problems with complex 3D geometrical structures can be modelled easily, as a relatively small amount of engineer-time is required and refinement is achieved by changing few parameters. This tool is useful for solving very large challenging problems.

BOT3P: A MESH GENERATION SOFTWARE PACKAGE FOR THE TRANSPORT ANALYSIS CODES DORT, TORT, TWODANT, TRREEDANT AND MCNP presentato a: INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS SNA 2003, PARIS, SEPTEMBER 22-24 2003

Orsi, R.
2003-10-09

Abstract

BOT3P consists of a set of standard FORTRAN 77 language programs that gives the users of the deterministic transport codes DORT and TORT some useful diagnostic tools to prepare and check the geometry of their input data files for both Cartesian and cylindrical geometries inc1uding graphical display modules. BOT3P produces at the same time the geometrical and material distribution data for the deterministic transport codes TWODANT and THREEDANT and, only in three-dimensional (3D) Cartesian geometry, for the Monte Carlo Transport Code MCNP. This makes it possible to compare directly for the same geometry the effects stemming from the use of different data libraries and solution approaches on transport analysis resu1ts. Through the lise of BOT3P, radiation transport problems with complex 3D geometrical structures can be modelled easily, as a relatively small amount of engineer-time is required and refinement is achieved by changing few parameters. This tool is useful for solving very large challenging problems.
Lavori presentati a convegno o conferenza;Software;Dati nucleari
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/6987
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