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ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis
No full textADEFTA (Atomic Densities far Transport Analysis) is a script file for any UNIX/Linux platform that uses only Boume shell (bash) commands and the 'awk' UNIX (and Linux) utility in order to calculate the atomic densities related to any compositional model for transport analysis. Moreover ADEFfA is particularly addressed to users of both the GIP code. which prepares macroscopic cross-sections far the DORT/TORT deterministic transport codes. Version 4.1 changes with respect to the previous version regard only a format detail in the group cross-section library index file oriented lo the automatic generation of an input to the GIP code. Moreover a more complicated application example (VENUS-3) with respect to the one (VENUS-1) in previous version reports is described here. ADEFTA can run in Cygwin (http://www.cygwin.com) and so the output is available in Windows as well as in UNIXILinux
CATSM: A Pre-Processor Tool for Medical Applications
No full textThe CATSM program was developed in ENEA-Bologna (Italy) in the framework of the Computational Medical Physics Working Group (CMPWG, http://cmpwg.ans.org/index.html ) activities promoted by the American Nuclear Society. This report aims to give potential users an idea of CATSM performances. See report FIS-P9H6-014, which will be distributed with BOT3P Version 5.1, for user manual and more detailed information. CATSM is the latest addition to the BOT3P code package, which is a set of standard FORTRAN 77 language programs originally conceived to give the users of the DORT and TORT deterministic transport codes some useful diagnostic tools to prepare the mesh grid and check their input data files. BOT3P binary interface files made later this package performance potentially available to any transport code. CATSM reads voxelized geometries related to elaborated (already interpreted by physicians or by proper software) computerized (axial) tomography (CT/CAT) scans and aims to give the users of deterministic transport codes more manageable geometrical input with reduced sizes, without or with small detail loss with respect to the original voxelized geometry. CATSM can automatically generate tetrahedron mesh grids also, starting from the input voxelized geometry, even though the implemented algorithm is still rather rough and to be improved in the future. CATSM, as the entire BOT3P package, was developed on a DIGITAL UNIX ALPHA 500/333 Workstation, tested on Red Hat Linux 7 also, and designed to run on most UNIX platforms
BOT3P Version 5.1: A Pre/Post-Processor System for Transport Analysis
No full textBOT3P 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, PA.RTISN 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.O). BOT3P Version 5.1 contains important additions specifically addressed to radiation transport analysis for medical applications. The new module CATSM lets users reduce the geometrical size of problems related to elaborated (already interpreted by physicians or by proper software) computerized (axial) tomography (CT/CAT) scans without or with small detail loss with respect to the original voxelized geometry. This permits to have problem sizes that can be more easily managed by transport codes. CATSM can automatically generate tetrahedron mesh grids also, starting from the input voxelized geometry, even though the implemented algorithm is still rather rough and to be improved in the future. BOT3P-5.l contains new graphics capabilities that enable users to visualize tetrahedron mesh grids in 3D and 2D cuts. BOT3P was developed on a DIGITAL UNIX ALPHA 500/333 Workstation and 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)). BOT3P 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 OECD/NEA Data Bank (F) and most of them are also distributed by ORNL/RSICC (USA)
Dosimetry Cross Section Processing from IRDF-2002 in the BUGLE-96 (47 n) Neutron Group Structure
No full textThe whole set of the dosimetry point-wise cross sections of the International Reactor Dosimetry File IRDF-2002 were processed in the 47 neutron group structure of the ORNL broad-group cross section working library BUGLE-96 for LWR shielding applications through the GROUPIE program of the PREPRO 2007 package. The reported 47 energy group response functions were calculated for all the following weighting spectrum conditions: - flat weighting spectrum; - 1/4 T (T = LWR pressure vessel thickness) pressure vessel weighting spectrum obtained from transport calculations based on the JEFF-3.1.1 evaluated nuclear data library; - 1/4 T pressure vessel weighting spectrum obtained from transport calculations based on the ENDF/B-VII.0 evaluated nuclear data library
BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0
No full textBOT3P is a set of standard FORTRAN 77 language programs that were developed at the ENEA-Bologna Nuclear Data Centre. BOT3P aims to give the users of the DORT and TORT deterministic transport codes some useful diagnostic tools to prepare and to check their input data files. It also includes some plotting programs that can be employed both as preprocessors and as postprocessors of a transport analysis. The BOT3P plotting programs use the RSCORS Graphics System subroutines, included in the DOORS-3.3 and earlier software package together with the Oak Ridge National Laboratory DORT and TORT transport codes. BOT3P was developed on a DIGITAL UNIX ALPHA 500/333 workstation and successfully used in some complex applications such as the VENUS-1 and VENUS-3 neutron shielding benchmarks. BOT3P was tested on an IBM RS/6000 workstation also and is designed to run on most UNIX platforms. The following programs are included in the package: GGDM, DDM GGTM, DTM2, DTM3, and RVARSCL. GGDM ant GGTM generate the geometrical and material entries for DORT and TORT, respectively. DDM is a DORT graphics pre/post processor. DTM2 and DTM3 are graphics pre/post processors showing cuts and three-dimensional views of the TORT model, respectively. RVARSCL reads DORT/TORT VARSCL sequential format files and selects and writes the data required by the user in new files to be visualized by DDM, DTM2, and DTM3 as postprocessor applications. The package is publicly available from the Organization for Economic Cooperation and Development/ Nuclear Energy Agency Data Bank (NEA-1627)
BOT3P Version 2.0: The ENEA Nuclear Data Centre Pre/Post-Processors of the DORT, TORT, TWODANT and THREEDANT Deterministic Transport Codes
No full textBOT3P is a set of standard FORTRAN 77 language developed at the ENEA-Bologna Nuclear Data Centre. BOT 3P 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 not only contains some important additions in the input geometrical model description, but extends 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. In other words, it is now possible to get at the same time two files absolutely equivalent as for the data contents, one for DORT/TORT and the other one for TWODANT/THREEDANT starting from the same input to BOT3P. However the plotting capabilities are so far limited to the DORT/TORT data files produced by BOT3P. BOT 3P Version 1.0 is publicly available from OECD/NEA Data bank with the identification NEA-1627 and BOT3P Version 2.0 will soon be transferred too. BOT3P was developed on a DIGITAL UNIX ALPHA 500/333 Workstation and successfully used in some complex neutron benchmarks. BOT3P was also tested on Red Hat Linux 7.1 (compiler g77) and is designed to run on most UNIX platforms
The ENEA-Bologna Pre-Post-Processor Package BOT3P for the DORT and TORT Transport Codes
No full textBOT3P (Bologna Transport Analysis Pre-Post-Processors) is a set of standard FORTRAN 77 language programs which were developed at the ENEA-Bologna Nuclear Data Centre. These programs aim at giving the users of the DORTand TORT deterministic transport codes, incIuded in the DOORS-3 2 software package, some useful diagnostic tools to prepare and to check their input data files. The programs were compiled on a DIGITAL UNIX ALPHA 500 workstation and successfully used in some complex applications such as in shielding benchmarks
BOT3P Version 5.0: A Pre/Post-Processor System for Transport Analysis
No full textBOT3P Version 1.0 was originally conceived as a set of standard FORTRAN 77 language prograrms 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). Later BOT3P versions further improved the geometrical capabilities with the possibility to realise in a new model geometries caming from other DORT/TORT input files, to include data derived from computerized tomography (C.T.) scans, to model a reactor care by preserving exactly the single rod volume and to generate the geometrical entries for the sensitivity code SUSD3D and a geometrical input far the MCNP Monte Carlo transport (in case of X-Y-Z mesh grid). BOT3P Version 5.0 contains important additions, such as new 2D and 3D graphics options and the possibility to directly manage and plot 2D R-Z geometries. Users can optionally require as refined a computation as desired of the area/volume error of material zones with respect to the theoretical values (approximation due to the stair-cased geometry representation) and the automatic correction of material densities in order to globally conserve masses. A binary file is optionally written with the density distribution of the different materials contained in the single mesh, allowing also a local density correction (per mesh). BOT3P was developed on a DIGITAL UNIX ALPHA 500/333 Workstation and successfully used not only in some complex neutron shielding and criticality benchmarks but also in power reactor applications. BOT3P was also tested on Red Hat Linux 7.1 and is designed to run on most UNIX platforms. All BOT3P versions are publicly and freely available from OECD/NEA Data Bank
'TORT Solutions to the Three-Dimensional MOX neutron Transport Benchmarks' presentato a: 2003 ANS/ENS International Winter Meeting 'Nuclear Technology: Achieving Global Economic Growth While Safeguarding the Environment', November 16-20, 2003 New Orleans, Louisiana, USA
No full textADEFTA: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis
No full textADEFTA (Atomic Densities for Transport Analysis) is a script file for any UNIX/Linux platform that uses only Bourne shell commands and th
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