ARC 11.2892: Code System for Analysis of Nuclear Reactors.
DIF3D 11.2892: Solves 1-D, 2-D, and 3-D finite-difference diffusion theory problems. VARIANT 11.2892: Solves VARIational Anisotropic Nodal Transport problems
Argonne National Laboratory, Argonne, Illinois.
Fortran 90 source code for Linux PCs, MacOSX and SUN, (C00824MNYCP02).
The ARC system comprises a consistent compilation of DIF3D, PERSENT, REBUS-3, VARI3D, DIF3D_TO_VTK, and the associated utilities. DIF3D is the diffusion and transport theory solver for neutroncs and gammas. PERSENT and VARI3D are perturbation & sensitivity analysis tools built around DIF3D. REBUS-3 is a generic fuel cycle analysis code built around DIF3D.
Related and Auxiliary Programs: DIF3D reads and writes the standard interface files specified by the Committee on Computer Code Coordination (CCCC). Additional utilities are provided to allow users to better use the existing software package including a basic visualization capability called DIF3D_TO_VTK which generates input files for VISIT or Paraview. For PERSENT, additional utility programs are provided to allow users to verify their results with direct eigenvalue perturbations by manual adjustments to the cross section data. The FTU program is used to extract interface files from the STACK file REBUS generates during execution.
Given conventional assembly homogenized cross section data, ARC can be used to perform fuel cycle analysis with follow on perturbation and sensitivity calculations.
6. RESTRICTIONS OR LIMITATIONS
Problem dimensions are all variable. Enough memory must be assigned to contain all the information for at least one energy group. All non - U.S. government funded license requests should be redirected to firstname.lastname@example.org
VARI3D is provided as is with no warranty of multiple platform usability. It carries out perturbation calculations on all geometries of the finite difference diffusion option of DIF3D. It also carries out sensitivity calculations on the R-Z finite difference diffusion option of DIF3D. Only basic support will be provided for VARI3D. All input options of VARI3D have not been tested.7. TYPICAL RUNNING TIME
The test cases take a combined hour to run in serial noting that the benchmark calculations for each individual program can be run simultaneously to reduce the total time to 30 minutes. The existing coding only operates on a single core with no parallelism or threading noting that we are working towards using limited threading for DIF3D 12.0
External data storage must be available for a large number of output files if a large number of perturbation/sensitivity calculations are to be done. If insufficient memory resources are available then large random access scratch files may be created which are associated with the individual response matrices and vectors used for the solution. We strongly recommend mounting a separate hard drive as /tmp and running all jobs from that location to prevent network drive issues. The remaining binary files are sequential access files with formatted or unformatted record types.
9. COMPUTER SOFTWARE REQUIREMENTS
No special requirements are made on the operating system. The included installation procedure requires a Fortran 90 (or newer) compiler and we impose compile-time fixed memory sizes (see installation README.txt) in several of the older codes. We note that ARC was originally built to allow limited dynamic memory sizing (up to 2 GB) which was eliminated due to multi-platform issues. Although developed on the Cray and IBM 30xx, the current version is tailored for execution on Linux and MacOSX platforms.
K. L. Derstine, DIF3D: A Code to Solve One-, Two-, and Three-Dimensional Finite-Difference Diffusion Theory Problems, ANL-82-64, Argonne National Laboratory, Argonne, IL (1984).
R. D. Lawrence, The DIF3D Nodal Neutronics Option for Two- and Three-Dimensional Diffusion Theory Calculations in Hexagonal Geometry, ANL-83-1, Argonne National Laboratory, Argonne, IL (1983).83).
G. Palmiotti, E. E. Lewis, and C. B. Carrico, VARIANT: VARIational Anisotropic Nodal Transport for Multidimensional Cartesian and Hexagonal Geometry Calculation, ANL-95/40, Argonne National Laboratory, Argonne, IL (October 1995).
C. H. Adams, et.al., The Utility Subroutine Package Used by Applied Physics Division Export Codes, ANL-83-3, Argonne National Laboratory, Argonne, IL (May 1992).
D. O’Dell, “Standard Interface Files and Procedures for Reactor Physics Codes, Version IV,” LA-6941-MS, Los Alamos Scientific Laboratory (September 1977).
B. J. Toppel, "The Fuel Cycle Analysis Capability REBUS-3," ANL-83-2 (March 1983 revised October 26, 1990) also included in PDF/REBUS-3_document.pdf.
R. P. Hosteny, "The ARC System Fuel Cycle Analysis Capability, REBUS-2," ANL-7721 (October 1978).
M. A. Smith, C. Adams, W. S. Yang, and E. E. Lewis, "VARI3D & PERSENT: Perturbation and Sensitivity Analysis", ANL/NE-13/8, Argonne National Laboratory, Argonne, IL (2013).
Included is a Unix tar file which includes source code, code documentation (in pdf format), sample problem input and output, code dependent BCD and binary card image file descriptions, python scripts, a README installation file.
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KEYWORDS: PERTURBATION; SENSITIVITY; TRANSPORT, MULTIGROUP; CRITICALITY CALCULATIONS; CCCC INTERFACE FORMAT; REACTOR PHYSICS