RSICC CODE PACKAGE PSR-530

 

1.         NAME AND TITLE

BOT3P-5.0:       Code System for 2D and 3D Mesh Generation and Graphical Display of Geometry and Results for Radiation Transport Codes.                    

 

AUXILIARY ROUTINES

RVARSCL:        Reads DORT/TORT gVARSCLh sequential format files.

GGDM: Generates the geometric and material entries for DORT.

DDM:               Plot program used as a DORT pre/post processor.

GGTM: Generates the geometric and material entries for TORT.

DTM2:  2D        Plot program used as a TORT pre/post processor.

DTM3:  3D        Plot program used as a TORT pre/post processor.

ADEFTA:          Calculates atomic densities of a compositional model.

 

2.         CONTRIBUTORS

ENEA Nuclear Data Center, Bologna, Italy.

 

3.         CODING LANGUAGE AND COMPUTER

Fortran 77; DEC Alpha, PC Linux  and IBM RS/6000 (P00530MNYCP00).

 

4.         NATURE OF PROBLEM SOLVED

Bologna Transport Analysis Pre‑Post‑Processors (BOT3P) is a set of standard Fortran 77 language programs developed at the ENEA -Bologna Nuclear Data Center.  The following programs are included in the BOT3P software package: GGDM, DDM, GGTM, DTM2, DTM3, RVARSCL, COMPARE and MKSRC.
  
GGDM requires in input all the geometrical, material and fixed neutron source information to generate the fine mesh boundary arrays, the material density factor for each fine space mesh array, the material number for each material zone array and the distributed source distribution array for DORT/TWODANT/PARTISN (two-dimensional (2D) transport applications) for both X-Y, R-Z and R-Theta geometries. GGTM is the 'twin' code of GGDM for three-dimensional applications. It requires in input all the geometrical, material and fixed neutron source information to generate the geometrical, material and distributed source distribution arrays for TORT/THREEDANT/PARTISN for both X-Y-Z and R-Theta-Z geometries.
  
The main feature of GGDM and GGTM consists in de-coupling the geometrical model description, which must be prepared once and for all, and the mesh grid refinement options. If users decide to create a more or less refined mesh than the one they have got or to switch from a X-Y/X-Y-Z mesh grid to a R-Theta/R-Theta-Z mesh grid or vice versa, it is sufficient for them to change very few data entries and to run GGDM/GGTM again, without modifying the geometrical description of the model to be analysed. Both GGDM and GGTM can also produce the data entries related to the presence of a fixed volumetric isotropic neutron source as a function of the generated mesh.
  
Users can define model areas/volumes with a more (or less) refined mesh grid with respect to the standard one for all the geometry. Moreover, GGDM and GGTM allow creating 'very small' geometrical zones centred about the key flux positions for edit purposes. That gives users the possibility to get the target quantity values in such locations directly from the transport code outputs as region response averages, without any need to interpolate the cell results.
  
DDM is a graphics pre/post processor, and it allows users to check the correctness of the entries generated by GGDM by plotting the geometry, the material mixture distribution or the fixed neutron source distribution, if any. DDM can work as a DORT/TWODANT (or other transport codes, through simple interfaces) post-processor also, by displaying any non-negative scalar target quantities of the transport analysis, such as, for example, the scalar neutron flux.
  
DTM2 and DTM3 allow users to check the correctness of the entries generated by GGTM by plotting the geometry, the material mixture distribution or the fixed neutron source distribution, if any, in two dimensional plots and three dimensional plots, respectively. Both DTM2 and DTM3 can work as TORT/THREEDANT (or other transport codes, through simple interfaces) post-processors also, by displaying any non-negative scalar target quantity of the transport analysis, such as, for example, the scalar neutron flux.


DTM2 makes 2D cuts of the model normal to one of the 3 co-ordinate directions X-Y-Z/R-Theta-Z and plots the material distribution or any non-negative target quantity on those cuts. DTM3 can make 3D parallel projections of a selected set of model material mixtures in a user defined model volume by reproducing the material distribution or a target quantity distribution on the visible surfaces of the selected model.
  
DDM, DTM2 and DTM3 generate plots by using the RSCORS Graphics System subroutines which are included in (at least up to) the DOORS-3.2 software package together with DORT and TORT. DDM, DTM2 and DTM3 can visualize the geometrical content (fine mesh boundaries and zone map) stored in a binary file. This feature makes it possible to easily interface them with other transport codes in order to use them as pre/post-processors not only of DORT and TORT.
  
RVARSCL can read a VARSCL sequential format file produced by DORT/TORT and the RTFLUX file produced by TWODANT/THREDANT/PARTISN, when the discontinuous space mesh option is not used, and can write a new binary sequential format file according to the input requirements of the post-processors DDM, DTM2, DTM3. RVARSCL gets the spatial distribution of the scalar neutron flux as the result of the sum of a selected number of energy groups. It accepts any user's non-negative weight (response) input function too, depending only on the energy group structure used in the DORT/TORT analysis, to be multiplied by the scalar neutron flux obtained in the DORT/TORT transport calculations.
  
COMPARE makes it possible to calculate the ratio between two positive target quantities in output from transport analyses (for example the neutron flux in output from DORT/TORT and TWODANT/THREEDANT, using the same fine mesh grid), to store it in a binary file in order to be visualized by the plot programs DDM, DTM2 and DTM3.
  
MKSRC makes it possible to produce a source binary file in format 'varsor' for DORT, format 'flxmom' for TORT and format 'fixsrc' for TWODANT and THREEDANT, by reading the region map and the scalar source produced by GGDM/GGTM and the spectra associated to each spatial region (up to now, only one moment different from zero can be input).

 

Also included in the package is ADEFTA, which is a script file for any UNIX/Linux platform that uses only Bourne Shell commands and the "awk" UNIX (and Linux) utility in order to calculate the atomic densities related to any compositional model for transport analysis. The output produced by ADEFTA can be useful for applications with many transport codes and is particularly addressed to users of GIP, DORT and TORT (DOORS) and the Monte-Carlo MCNP code.

 

BOT3P Version 1.0 (BOT3P1.0) 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, included in the DOORS-3.2 software package, some useful diagnostic tools to prepare and check their input data files.
  
BOT3P Version 2.0 (BOT3P2.0) extended the possibility to produce the geometrical, material distribution and fixed neutron source data also to the deterministic transport codes TWODANT/THREEDANT of the DANTSYS system and to PARTISN, making it possible to get two files absolutely equivalent as for the data contents, one for DORT/TORT and the other one for TWODANT/THREEDANT/PARTISN starting from the same BOT3P input.
  
BOT3P Version 3.0 (BOT3P3.0) further improved the geometrical capabilities with the possibility to include in a new model geometries coming from other DORT/TORT input files or derived from computerized tomography (C.T.) scans. BOT3P3.0 could also generate a geometrical input for the MCNP Monte Carlo transport code, when users required X-Y-Z TORT/THREDANT/PARTISN mesh grid to be generated.
  
BOT3P Version 4.1(BOT3P4.1) improved the geometrical modelling capabilities of previous BOT3P versions by reducing CPU times too. New geometrical objects could be input in the combinatorial geometry, and the geometrical entries for the sensitivity code SUSD3D were also generated for both Cartesian and cylindrical geometries.
As from version 4.1, BOT3P includes new modules suggested or prepared by Adrien Bidaud (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. Moreover, as from version 4.1, BOT3P stores the fine mesh boundaries and the material zone map in a binary file to be easily interfaced with any other transport code and the content of this binary file can be visualized by BOT3P graphics programs. For example, an interface has already been prepared in the Keldysh Institute of Applied Mathematics (Moscow) for the codes KASKAD-S-2.5 and KATRIN-2.0 (Two-Dimensional and Three-Dimensional Discrete Ordinates Neutron, Photon and Charged Particle Transport Codes, respectively).
  
BOT3P Version 5.0 (BOT3P5.0) contains important additions, such as, for instance, new 2D and 3D graphics options, more detailed standard output information and the possibility to directly manage and plot 2D R-Z geometries. But the most significant new feature of BOT3P5.0 regards the mesh generation programs. 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 representation of the geometry) and the automatic correction of material densities and uniformly distributed neutron sources to globally preserve masses and neutron sources, respectively. Moreover, a binary file is optionally written with the density distribution of the different materials contained in the single mesh (for those meshes cutting at the same time more than one material zone), allowing a local density correction (per mesh) in alternative to a global density correction on the whole domain of the material zone. This 'fine' material distribution can optionally be visualized by the 2D plot BOT3P5.0 modules DDM, DTM2.

 

BOT3P-5.0 and ADEFTA are also distributed by the NEA Data Bank. See package abstracts

NEA-1678/06 http://www.nea.fr/abs/html/nea-1678.html and

NEA-1708/03 http://www.nea.fr/abs/html/nea-1708.html

 

5.         METHOD OF SOLUTION

GGDM and GGTM work similarly from the logical point of view. Since the 3D case is more general, the following description refers to GGTM. All the co-ordinate values that characterise the geometrical scheme at the basis of the 3D transport code geometrical and material model are read, sorted and all stored if different from the neighbouring ones more than an input tolerance established by the user. These co-ordinates are always present in the fine-mesh boundary arrays independently of the mesh grid refinement options, because they describe the user's scheme. According to the mesh grid refinement options, GGTM introduces further co-ordinate values, which complete the input mesh grid. A loop for each cell is performed to determine the zone and the material to be attributed to the cell. The cell is ideally represented by its centre and it is relatively simple to determine which material zone the cell belongs to. Material zones may have very complicated geometrical shapes in space thanks to the combinatorial geometry among volumes existing in GGTM. Moreover, the priority parameter associated to each material zone can easily solve any overlapping situation among zones. Fixed neutron sources, if any, are adapted to the mesh refinement at the same time.

 

As from version 5.0, GGTM can optionally calculate errors in volume values due to the stair-cased approximation in geometry. GGTM considers a 'very' refined uniform sub-grid for those single meshes cutting more than one material zone at zone interfaces and works in same way as previously described in the mesh attribution to zones for each single sub-mesh. This method lets users calculate the exact material zone volume values with great precision, independently of the geometry complexity and lets GGTM automatically update material zone densities to conserve mass.

 

As for the plot programs DDM, DTM2 and DTM3, they do not make any value interpolations among cell values to have contours, when used as post-processors or to plot any fixed neutron source distribution; they simply attribute the entire single mesh grid cell the colour corresponding to the adopted value scale. This simple and fast method lets users faithfully reproduce transport results and overlap material, zone, body or mesh borders on the same plots without overcrowding them with too many lines.

 

6.         RESTRICTIONS OR LIMITATIONS

The RSCORS, Sandia National Laboratory library of graphical primitives, is required to install and run BOT.  RSCORS is distributed with the CCC-650/DOORS3.2 and DOORS3.2a packages. 

 

Only a continuous space mesh grid can be generated by GGDM and GGTM and input to DDM, DTM2, DTM3, RVARSCL, COMPARE and MKSRC.

 

7.         TYPICAL RUNNING TIME

Central processor unit (CPU) time is roughly proportional to the number of cells the 2D/3D models created by GGDM/GGTM consist of and of the number of geometrical objects defined in the combinatorial geometry. For 3D applications, the distributed source distribution array generation may really be time consuming for the R-Theta-Z model if a core simulating neutron source is present.

 

Just to give an idea of the typical running time of GGTM, it is worth while mentioning that the CPU times required by BOT3P Version 1.0 to produce the ENEA VENUS-3 X-Y-Z and R-Theta-Z models, distributed source distribution array included, were respectively 148 s and 293 s on a DIGITAL UNIX ALPHA 500/333 workstation. Both models were more or less one million cells large.

 

8.         COMPUTER HARDWARE REQUIREMENTS

BOT3P-5.0 was developed on DEC Alpha and was also tested on PC Linux and IBM RS/6000.

 

9.         COMPUTER SOFTWARE REQUIREMENTS

A Fortran 77 compiler is required to compile the codes on all computers. No BOT3P-5.0 executables are included in this package. BOT3P Version 5.0 runs on DEC Alpha systems and on personal computers under Red Hat LINUX, but is very likely to run on all UNIX platforms since no machine dependent subroutine is called. The developers tested it on a DIGITAL UNIX Alpha 500/333 Workstation (128 Mbytes of RAM) and on a personal computer (INTEL Pentium III 800 MHz, 448MB RAM) under Red Hat Linux.

The RSCORS, Sandia National Laboratory library of graphical primitives, is required to install and run BOT.  RSCORS is distributed with the CCC-650/DOORS3.2 and DOORS3.2a packages. Linux and DEC versions of librscors.a are included in the BOT3P-5.0 distribution. These will not run on all systems but were compatible with the test computers.

 RSICC tested BOT3P under the following systems:

AMD Athlon running RedHat Linux 7.3 with g77 Version 2.96

DEC alpha ‑ Compaq Unix Tru64 V5.1A with HP Fortran V5.5A-3548-48D88

IBM RS/6000 ‑ AIX 5.1 ‑ IBM XL Fortran for AIX Version 8.01.0000.0003

 

10.        REFERENCES

a)  included in documentation:

Roberto Orsi, gBOT3P Version 5.0: A Pre/Post-Processor System for Analysis,h FIS‑P9H6-008 (April 2005).

Roberto Orsi, gADEFTA Version 3.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis,h FIS-P9H6-007 (March 24, 2005).

 

b) background information:

W.A. Rhoades, R.L. Childs, RSICC Computer Code Collection CCC-650, gDOORS‑3.2, One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System,h

W.A. Rhoades and D. B. Simpson, gThe TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code,h ORNL/TM-13221 (October 1997).

S.L. Thompson, gThe RSCORS Graphics System,h SAND99-XXXX Sandia National Laboratory Working Document (October 19, 1991).

R.E. Alcouffe, R.A. Baker, F.W. Brinkley, D.R. Marr, R.D. O'Dell, W.F. Walters, "DANTSYS 3.0: One‑,Two‑, and Three‑Dimensional, Multigroup, Discrete‑Ordinate Transport Code System", LA‑12969‑M, Los Alamos National Laboratory, Los Alamos, New Mexico, USA (1995).

"MCNP TM ‑ A General Monte Carlo N‑Particle Transport Code. Version 4C." LA‑1309‑M, Los Alamos National Laboratory, Los Alamos, New Mexico, USA (March 2000).

Ivo Kodeli,'NEA-1628 SUSD3D. SUSD3D, 1-,2-,3-Dimensional Cross Section Sensitivity and Uncertainty Code', OECD/NEA Data Bank, Issy-les-Moulineaux, France (2000).

Prediction of Neutron Embrittlement in the Reactor Pressure Vessel: VENUS‑1 and VENUS‑3 Benchmarks, NEA/NSC/DOC(2000)5, OECD/NEA‑DATA BANK.

M. Pescarini, R. Orsi, M.G. Borgia, T. Martinelli, ENEA Nuclear Data Centre Neutron Transport Analysis of the VENUS‑3 Shielding Benchmark Experiment, KT‑SCG‑00013, ENEA‑Bologna, Italy.

R. Orsi, "BOT3P Version 2.0: The ENEA Nuclear Data Centre Pre/Post‑Processors of the DORT, TORT , TWODANT and THREEDANT Deterministic Transport Codes", FS‑P127‑001, ENEA‑Bologna, Italy (2002).

E. E. Lewis (NW‑University), M. A. Smith & N. Tsoulfanidis (U‑Missouri), G. Palmiotti, T. A. Taiwo & R. N. Blomquist (ANL): "Specification for Deterministic 2‑D/3‑D MOX fuel assembly transport calculations without spatial homogenisation (C5G7 MOX)", Expert Group on 3‑D Radiation Transport Benchmarks Benchmark, NEA/NSC/DOC(2001)4, Organization for Economic Cooperation and Development Nuclear Energy Agency, Paris, France, (March 2001).

"Expert Group on 3‑D Radiation Transport Benchmarks. Summary of meeting on C5G7 Mox Benchmark", Hollywood, Florida, USA, June 11, 2002, NEA/NSC/DOC(2002)13.

M. Pescarini, M.G. Borgia, R. Orsi, T. Martinelli, gENEA‑Bologna Validation of the BUGLE‑96 ENDF/B‑VI Library on the VENUS‑1 Neutron Shielding Benchmark Experiment. A Synthesis of the Final Results,hJEF/DOC‑778, JEFF Working Group Meeting on Benchmark Testing, Data Processing and Evaluations, NEA Data Bank, Issy‑Les‑Moulineaux, France (April 12‑14, 1999).

 R. Orsi, gThe ENEA‑Bologna Pre‑Post‑Processor Package BOT3P for the DORT and TORT Transport Codes,h JEF‑DOC/828, JEFF Working Group Meeting on Benchmark Testing, Data Processing and Evaluations, NEA Data Bank, Issy Les Moulineaux, France (May 22‑24, 2000).

 

11.        CONTENTS OF CODE PACKAGE

The package is transmitted as a GNU compressed Unix tar file on a CD. The tar file contains the source files for all programs in the auxiliary codes list plus MKSRC and COMPARE, scripts, test cases, implementation instructions, sample problems, description of sample problems, and documentation.

 

12.        DATE OF ABSTRACT

October 2005.

 

KEYWORDS:   PLOTTING; NEUTRON; GAMMA-RAY; CYLINDRICAL GEOMETRY; COMPLEX GEOMETRY; MESH GENERATION; WORKSTA­TION