1. NAME OR DESIGNATION OF PROGRAM -
DOORS3.2.
2. COMPUTER FOR WHICH PROGRAM IS DESIGNED
Program-name Package-ID Status
DOORS3.1 CCC-0650/01 Obsolete
DOORS3.2 CCC-0650/02 Arrived
Machines used:
Package-ID Orig. Computer Test Computer
CCC-0650/02 UNIX gen. W.S. UNIX gen. W.S.
3. DESCRIPTION OF PROGRAM OR FUNCTION -
The DOORS3.2 discrete ordinates transport code system includes the most recent versions of CCC-0543/TORT-DORT, CCC-0254/ANISN-ORNL, CCC-0628/GBANISN and CCC-0351/FALSTF. It also includes the ISOPLOT code from the PSR-0155/DOGS package and various utility programs listed below which were previously included in the TORT-DORT package. In this release each module is a separate executable file. Several modules, as needed, can be run in a single job by using "jdos" to call the "drv" module which interprets the sequence specified in the input. Future plans include an integrated Motif/MFC based system.
TORT calculates the flux of fluence of particles due to particles incident upon the system from extraneous sources or generated internally as a result of interaction with the system in two-or three-dimensional geometric systems, and DORT is used in one- or two-dimensional geometric systems. The principle application is to the deep-penetration transport of neutrons and photons. Reactor eigenvalue problems can also be solved. Numerous printed edits of the results are available, and results can be transferred to output files for subsequent analysis.
ANISN solves the one-dimensional Boltzmann transport equation for neutrons or gamma rays in slab, spherical, or cylindrical geometry. GBANISN is based on ANISN but was modified to allow randomizing of multibank fluxes within a group at all interfaces between dissimilar materials and a reduction in the number of outer iterations for problems involving neutron upscatter into higher energy groups. GBANISN requires fewer outer iterations than ANISN by performing "inner iterations" over energy groups within a "band" and converging those groups before moving to the next band. These "inner" iterations slightly resemble outer iterations in ANISN. Thus, a calculation with upscatter and no fission can be solved with one traditional outer iteration. GBANISN, like ANISN, inclu
des a technique for handling general anisotropic scattering, pointwise convergence criteria, and alternate step function difference equations that effectively remove the oscillating flux distributions sometimes found in discrete ordinates solutions.
ISOPLOT was modified to use the Sandia National Laboratory RSCORS graphical system. SNL's CMP system for code maintenance is used to build the Fortran source files for the target computer. DOORS reads ANISN-format cross-section libraries, which are not included in the package. Users may choose from several available in RSIC's data library collection which can be identified by the keyword "ANISN FORMAT".
The August 1996 update corrected some memory allocation problems which occurred when installing ANISN, GBANISN, and ISOPLOT on Cray systems. FALSTF was also modified to eliminate double precision on Cray. Numerous corrections and enhancements were made in DOORS 3.2, which was released in February 1998.
4. METHOD OF SOLUTION -
The Boltzmann transport equation is solved using the method of discrete ordinates to treat the directional variable and weighted finite-difference methods, in addition to Linear Nodal and Linear Characteristic methods in TORT to treat spatial variables. Energy dependence is treated using a multigroup formulation. Time dependence is not treated. Starting in one corner of a mesh, at the highest energy, and with starting guesses for implicit sources, boundary conditions and recursion relationship are used to sweep into the mesh for each discrete direction independently. Integral quantities such as scalar flux are obtained from weighted sums of the directional results. The calculation then proceeds to lower energy groups, one at a time.
Iterations are used to resolve implicitness caused by scattering between directions within a single energy group, by scattering from an energy group to another group previously calculated, by fission, and by certain types of boundary conditions. Methods are available to accelerate convergence of both inner and outer iterations. Anisotropic scattering is represented by a Legendre expansion of arbitrary order, and methods are available to mitigate the effect of negative scattering source estimates resulting from finite truncation of the expansion. Direction sets can be biased, concentrating work into directions of particular interest. Fixed sources can be specified at either external or internal mesh boundaries, or distributed within mesh cells.
Two multitasking options are available for solving the Linear Nodal method equations in TORT on UNICOS Cray platforms: Octant Parallel (OP) which concurrently performs the right-left and left-right sweeps for each in the mesh; Direction Parallel (DP) which concurrently sweeps each row in all directions within an octant. Wall-clock speedup generally scales up with problem size but is very sensitive to machine loading during execution. On a li
ghtly loaded Y/MP speedup factor of 5 was achieved using 8 tasks with a
problem as small as 104,000 cells approx.
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -
External forces and nonlinear physical effects cannot be treated. Penetration through large, non-scattering regions may become inaccurate due to ray effects. Problems with scattering ratios near unity or eigenvalue calculations with closely spaced eigenvalues may be quite time-consuming. Flexible dimensioning is used throughout so that no fixed limits on groups, problem size, etc., are applicable.
6. TYPICAL RUNNING TIME -
Central processor unit (CPU) time used by the flux sweep is roughly proportional to the number of flux calculations: spatial mesh cells * directions * energy groups *
iterations/group. Times for running all test cases in the package range from about 1 hour on an IBM RS/6000 Model 590 to several hours on slower machines.
7. UNUSUAL FEATURES OF THE PROGRAM -
8. RELATED AND AUXILIARY PROGRAMS -
The code system contains the following modules:
TORT Three-dimensional neutron/photon transport
DORT Two-dimensional neutron/photon transport
ANISN One-dimensional neutron/photon transport
GBANISN ANISN with "group band" option
JDOS Script for performing calculations
DRV DOORS driver module called by JDOS
ALC Material cross-section library maintenance
GIP Group cross-section preparation
TORSED Couple R-Z DORT to X-Y-Z TORT calculation
TORSET Couple primary TORT to secondary TORT calculation
VISA Prepare a TORSED input file from a DORT output file
GRTUNCL Uncolided flux and first collision source
FALSTF Last collision source projection to point detector
BNDRYS Convert internal boundary flux to internal boundary source
RTFLUM Convert flux moment files between various formats
ISOPLOT Display 2-D flux or response contours
XTORID Prepare 2-D flux slices from TORT for display in ISPL3D
CMP Sandia National Lab. code system maintenance and update
RSCORS Sandia National Lab. subroutine library of graphical
primitives
9. STATUS -
CCC-0650/01: 21-APR-1998 Obsolete
CCC-0650/02: 04-MAR-1999 Arrived at NEADB
10. REFERENCES -
- S.L. Thompson:
CMP Code Maintenance Package
SAND85-0825 Sandia National Laboratory Working Document (April 8,
1991)
- S.L. Thompson:
The RSCORS Graphics System
SAND99-XXXX Sandia National Laboratory Working Document (October
19, 1991)
- S.L. Thompson:
A Definition of the Basic Graphics Package (BGP) Intermediate File Format, Based on unpublished letter (March 1978)
CCC-0650/02:
- W.A. Rhoades and D.B. Simpson:
The TORT Three-Dimensional Discrete Ordinates Neutron/Photon
Transport Code
ORNL/TM-13221 (October 1997)
- W.A. Rhoades and D.B. Simpson:
The TORT Three-Dimensional Discrete Ordinates Neutron/Photon
Transport Code
ORNL/TM-13221 Draft (June 1996)
- M.B. Emmett et al.:
The DORT sections of "A User's Manual for MASH 1.0 - A Monte Carlo
Adjoint Shielding Code System
ORNL/TM-11778 (March 1992)
- R.L. Childs:
The FALSTF Last-Flight Computer Program
ORNL/TM-12675 (January 1996)
- W.W. Engle Jr.:
ANISN, A One-Dimensional Discrete Ordinates Transport Code with
Anisotropic Scattering
K-1693 (March 1967)
- W.W. Engle Jr. et al.:
DTF-III, A One-Dimensional, Multigroup Neutron Transport Program
NAA-SR-10951 (March 1966)
- R.L. Childs and D.E. Cullen:
GROUPBAND-ANISN: A Code to Perform Multiband Calculations
Informal Notes (June 1994)
- W.A. Rhoades and M.B. Emmett:
DOS: The Discrete Ordinates System
ORNL/TM-8362 (September 1982)
- C.O. Slater:
The XTORID and ISPL3D Codes for Plotting TORT Activities
ORNL Internal Memo (March 25, 1996)
- R.L. Childs:
GRTUNCL: First Collision Source Program
ORNL Informal Notes (1982)
- R.L. Childs and W.A. Rhoades:
Theoretical Basis of the Linear Nodal and Linear Characteristics
Methods in the TORT Computer Code
ORNL/TM-12246 (January 1993)
- W.A. Rhoades:
The TORSED Method for Construction of TORT Boundary Sources from
External DORT Flux Files
ORNL/TM-12359 (August 1993)
- W.A. Rhoades and D.B. Simpson:
The TORSET Method for Construction of TORT Boundary Sources from
External TORT Flux Files
ORNL Draft Document (June 1996)
- W.A. Rhoades and D.B. Simpson:
Splicing and Bootstrapping Methods for DORT/TORT-To-TORT Coupling,
(TORSET Section)
ORNL/TM-13350 (To be published)
- W.A. Rhoades:
The ALC1 Program for Cross-Section Library Management
ORNL/TM-4015 (December 1972)
11. MACHINE REQUIREMENTS -
DOORS modules run on Cray, IBM RS/6000, Sun, DEC Alpha, SGI Hewlett Packard systems and personal computers under Linux.
12. PROGRAMMING LANGUAGE(S) USED -
CCC-0650/02: FORTRAN-77
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED -
DOORS has been rigorously tested on Cray and IBM and has been installed on several other Unix systems. Some numerical errors occurred when solving difficult problems on short-word configurations. The Cray version runs under UNICOS version 8.0.3 using the CFT77 compiler version 6.0.4.10. Library calls are made to the standard UNICOS library to provide time, date, etc. DOORS was also tested on the following systems:
Cray Unicox 8.0.3 cft77 6.0.4.10 and Cray J90 Unicos 9.2.0.03, f90 3.0.1.3
IBM RS/6000, AIX 4.2, XLF 3.2.2.3
DEC Alpha 3000, Digital UNIX V3.2G - Worksystem Software
(Rev.62), Digital Fortran Version 4
SGI IP22, IRIX 5.3, F77 Ver 4.0.2
Sun SparcStation 20, OS5.6, SUN FORTRAN 77 Ver 4.2
HP 9000/715, HP-UX 10.20, HP Fortran 77 Version B.10.20
PC under RedHat 5 Linux with f2c Ver1 19970805 and gcc Ver 2.7.2.3
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -
15. NAME AND ESTABLISHMENT OF AUTHORS -
Contributed by:
Radiation Shielding Information Center
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U. S. A.
Developed by:
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U. S. A.
16. MATERIAL AVAILABLE -
CCC-0650/02: MISTP: DOC/install. doc and other info and reports
OUTTP: OUTPUTS/Developer's output for Cray and IBM
LODTP: BIN/Executables
SRCTP: DORT/ DORT, DOS and FALSTF sources and scripts
SRCTP: ISOPLOT/ ISOPLOT sources and test case
MISTP: RSCORS/ RSCORS sources
SRCTP: SLTUTIL/ CMP and other SNL utilities
SRCTP: TORT/ TORT source and scripts
REPPT: ORNL/TM-13221 Draft (June 1996)
REPPT: ORNL/TM-11778 (March 1992)
REPPT: ORNL/TM-12675 (January 1996)
REPPT: K-1693 (March 1967)
REPPT: NAA-SR-10951 (March 1966)
NOTPT: Informal Notes (June 1994)
REPPT: ORNL/TM-8362 (September 1982)
NOTPT: ORNL Internal Memo (March 25, 1996)
NOTPT: ORNL Informal Notes (1982)
REPPT: ORNL/TM-12246 (January 1993)
REPPT: ORNL/TM-12359 (August 1993)
REPPT: ORNL Draft Document (June 1996)
REPPT: ORNL/TM-4015 (December 1972)
DATTP: INSTALL/ Installation scripts
DATTP: INSTALL/ Installation scripts
REPPT : ORNL/TM-13221 (October 1997)
REPPT: ORNL/TN-13350 (to be published)
17. CATEGORIES -
C, J, K
keywords: neutron transport equation, photon transport, shielding
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