CCC-0519 AUS.
AUS, Neutron Transport and Gamma Transport System for Fission Reactors and Fusion Reactors
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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To submit a request, click below on the link of the version you wish to order.
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| AUS87 | CCC-0519/01 | Tested | 29-JAN-1990 |
| AUS98 | CCC-0519/02 | Arrived | 23-MAR-2001 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| CCC-0519/01 | IBM 360 series | IBM 360 series |
| CCC-0519/02 | UNIX W.S. |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
AUS is a neutronics code system which may be used for calculations of a wide range of fission reactors, fusion blankets and other neutron applications. The present version, AUS98, has a nuclear cross section library based on ENDF/B-VI and includes modules which provide for reactor lattice calculations, one-dimensional transport calculations, multi-dimensional diffusion calculations, cell and whole reactor burnup calculations, and flexible editing of results. Calculations of multi-region resonance shielding, coupled neutron and photon transport, energy deposition, fission product inventory and neutron diffusion are combined within the one code system.
The major changes from the previous release, AUS87, are the inclusion of a cross-section library based on ENDF/B-VI, the addition of the POW3D multi-dimensional diffusion module, the addition of the MICBURN module for controlling whole reactor burnup calculations, and changes to the system as a consequence of moving from IBM mainframe computers to UNIX workstations.
AUS is a neutronics code system which may be used for calculations of a wide range of fission reactors, fusion blankets and other neutron applications. The present version, AUS98, has a nuclear cross section library based on ENDF/B-VI and includes modules which provide for reactor lattice calculations, one-dimensional transport calculations, multi-dimensional diffusion calculations, cell and whole reactor burnup calculations, and flexible editing of results. Calculations of multi-region resonance shielding, coupled neutron and photon transport, energy deposition, fission product inventory and neutron diffusion are combined within the one code system.
The major changes from the previous release, AUS87, are the inclusion of a cross-section library based on ENDF/B-VI, the addition of the POW3D multi-dimensional diffusion module, the addition of the MICBURN module for controlling whole reactor burnup calculations, and changes to the system as a consequence of moving from IBM mainframe computers to UNIX workstations.
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4. METHOD OF SOLUTION
AUS98 is a modular system in which the modules are complete programs linked by a path given in the input stream. A simple path is simply a sequence of modules, but the path is actually preprocessed and compiled using the Fortran 77 compiler. This provides for complex module linking if required. Some of the modules included in AUS98 are:
MIRANDA Cross-section generation in a multi-region resonance subgroup calculation and preliminary group condensation.
ANAUSN One-dimensional discrete ordinates calculation.
ICPP Isotropic collision probability calculation in one dimension and for rod clusters.
POW3D Multi-dimensional neutron diffusion calculation including feedback-free kinetics.
AUSIDD One-dimensional diffusion calculation.
EDITAR Reaction-rate editing and group collapsing following a transport calculation.
CHAR Lattice and global burnup calculation.
MICBURN Control of global burnup calculation and fuel management using microscopic nuclide cross sections.
BURNMAC Global burnup calculation and fuel management using macroscopic material cross sections.
AUSED Cross-section editing and maintenance.
ORNL Forming cross sections for standard transport codes such as DORT and KENO.
MERGEL Merging of cross sections files.
PLOTXS Interactive plotting of cross section files.
AUSPLOT Interactive plotting of fluxes and reaction rates following a transport calculation.
AUS98 is a modular system in which the modules are complete programs linked by a path given in the input stream. A simple path is simply a sequence of modules, but the path is actually preprocessed and compiled using the Fortran 77 compiler. This provides for complex module linking if required. Some of the modules included in AUS98 are:
MIRANDA Cross-section generation in a multi-region resonance subgroup calculation and preliminary group condensation.
ANAUSN One-dimensional discrete ordinates calculation.
ICPP Isotropic collision probability calculation in one dimension and for rod clusters.
POW3D Multi-dimensional neutron diffusion calculation including feedback-free kinetics.
AUSIDD One-dimensional diffusion calculation.
EDITAR Reaction-rate editing and group collapsing following a transport calculation.
CHAR Lattice and global burnup calculation.
MICBURN Control of global burnup calculation and fuel management using microscopic nuclide cross sections.
BURNMAC Global burnup calculation and fuel management using macroscopic material cross sections.
AUSED Cross-section editing and maintenance.
ORNL Forming cross sections for standard transport codes such as DORT and KENO.
MERGEL Merging of cross sections files.
PLOTXS Interactive plotting of cross section files.
AUSPLOT Interactive plotting of fluxes and reaction rates following a transport calculation.
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8. RELATED AND AUXILIARY PROGRAMS
Auxiliary Programs : BCDBINXS : Changer of cross section library from ASCII to binary.
BCDBINFP : Changer of fission product decay library from ASCII to binary.
Related Data Libraries : AUS98 includes a cross-section library with 200 neutron and 37 photon groups and a fission product decay library with 869 fission products. Both libraries are based on ENDF/B-VI.
Auxiliary Programs : BCDBINXS : Changer of cross section library from ASCII to binary.
BCDBINFP : Changer of fission product decay library from ASCII to binary.
Related Data Libraries : AUS98 includes a cross-section library with 200 neutron and 37 photon groups and a fission product decay library with 869 fission products. Both libraries are based on ENDF/B-VI.
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| Package ID | Status date | Status |
|---|---|---|
| CCC-0519/01 | 29-JAN-1990 | Screened |
| CCC-0519/02 | 23-MAR-2001 | Masterfiled Arrived |
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CCC-0519/01, included references:
- G. S. Robinson :Notes on Implementing the AUS87 Code Package
Infomal Notes (1987)
- G. S. Robinson :
A Guide to the AUS Modular Neutronics Codes System
AAEC/E645 (April 1987)
- G. S. Robinson :
EDITAR : A Module for Reaction Rate Editing and Cross-Section
Averaging Within the AUS Neutronics Code System
AAEC/E621 (March 1986)
- G. S. Robinson :
ICPP : A Collection Probability Module for the AUS Neutronics
Code System
AAEC/E620 (October 1985)
- G. S. Robinson :
CHAR and BURMAC : Burnup Modules of the AUS Neutronics Code System
AAEC/E624 (March 1986)
- G. S. Robinson :
MIRANDA : Module Based on Multiregion Resonance Theory for
Generating Cross Sections within the AUS Neutronics Code System
AAEDC/E626 (December 1985)
- G. S. Robinson :
Extension of the AUS Reactor Neutronics System for Application to
Fusion Blanket Neutronics
AAEC/E583 (March 1984)
- B. E. Clancy :
ANAUSN : A One-Dimensional Multigroup Transport Theory Module for
the AUS Reactor Neutronics System
AAEC/E539 (May 1982)
- B. V. Harrington :
AUS Module AUSED : An Editing Program for AUS Cross-Section Data
Pools
AAEC/E389 (May 1976)
CCC-0519/02, included references:
- G.S.Robinson and B.V. HarringtonAUS98 - The 1998 Version of the AUS Modular Neutronics Code System
ANSTO/E734 (July 1998)
- B.V. Harrington, J.P. Pollard and J.M. Barry
POW3D - Neutron diffusion Module of the AUS System, A User's Manual
ANSTO/E726 (November 1996)
- G.S. Robinson
Generation and Validation of a Cross Section Library Based on ENDF/B-VI for the
AUS Neutronics Code System
ANSTO/E712 (December 1993)
- G.S. Robinson
AUS Module MIRANDA - A Data Preparation Code Based on Multiregion Resonance
Theory.
ANSTO/E410 (July 1977)
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| Package ID | Computer language |
|---|---|
| CCC-0519/01 | FORTRAN-77 |
| CCC-0519/02 | FORTRAN-77, C-LANGUAGE |
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED
Compilation of AUS98 requires a fortran 77 compiler and an ANSI C standard compiler. Execution also requires a Fortran 77 compiler. The AUSPLOT module, which is a useful but not essential part of AUS98, requires a Tcl interpreter with Tk such as WISHX and the GNUPLOT interactive plotting program.
Compilation of AUS98 requires a fortran 77 compiler and an ANSI C standard compiler. Execution also requires a Fortran 77 compiler. The AUSPLOT module, which is a useful but not essential part of AUS98, requires a Tcl interpreter with Tk such as WISHX and the GNUPLOT interactive plotting program.
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CCC-0519/02
C519tar1.gz: source code, script, data, test case input & outputC519tar1.lis list of files
readme.cd readme file
readme.rsi readme file
CCC-0519/01
| File name | File description | Records |
|---|---|---|
| CCC0519_01.001 | SVC Source (OS Supervisor call) | 91 |
| CCC0519_01.002 | FORTLIB (Subroutine Library) | 12854 |
| CCC0519_01.003 | AELINK1 Source (Aelink Program) | 496 |
| CCC0519_01.004 | FORTCL (Compile and Load Module) | 249 |
| CCC0519_01.005 | AUSED source (Module) | 3508 |
| CCC0519_01.006 | ANAUSN Source (Module) | 5489 |
| CCC0519_01.007 | AUSIDD Source (Module) | 868 |
| CCC0519_01.008 | AUSYS Source (AUS Supervisor) | 1107 |
| CCC0519_01.009 | BURNMAC Source (Module) | 1216 |
| CCC0519_01.010 | CHAR Source (Char) | 2400 |
| CCC0519_01.011 | EDITAR Source (Module) | 5554 |
| CCC0519_01.012 | EXPAND Source (Module) | 496 |
| CCC0519_01.013 | ICPP Source (Module) | 9455 |
| CCC0519_01.014 | JOINER Source (Module) | 137 |
| CCC0519_01.015 | MERGEL Source (Module) | 210 |
| CCC0519_01.016 | MIRANDA Source (Module) | 10156 |
| CCC0519_01.017 | ORNL Source (Module) | 211 |
| CCC0519_01.018 | AUSEDCOM | 69 |
| CCC0519_01.019 | CATPROC | 123 |
| CCC0519_01.020 | LINKLIB Source (Load Standard Ausys Input) | 76 |
| CCC0519_01.021 | RUN1 (Input for Test Case 1) | 45 |
| CCC0519_01.022 | RUN2 (Input for Test Case 2) | 76 |
| CCC0519_01.023 | RUN3 (Input for Test Case 3) | 27 |
| CCC0519_01.024 | RUN4 (Input for Test Case 4) | 52 |
| CCC0519_01.025 | RUN5 (Input for Test Case 5) | 33 |
| CCC0519_01.026 | OUT1 (Output from Test Case 1) | 609 |
| CCC0519_01.027 | OUT2 (Output from Test Case 2) | 1717 |
| CCC0519_01.028 | OUT3 (Output from Test Case 3) | 130 |
| CCC0519_01.029 | OUT4 (Output from Test Case 4) | 1260 |
| CCC0519_01.030 | OUT5 (Output from Test Case 5) | 448 |
| CCC0519_01.031 | ENDFB (128-Group Library) | 445 |
| CCC0519_01.032 | ENDF200G (200+37)-Group Library | 1450 |
| CCC0519_01.033 | Information file | 108 |
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- B. Spectrum Calculations, Generation of Group Constants and Cell Problems
- C. Static Design Studies
- D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
- K. Reactor Systems Analysis
- M. Data Management
- X. Magnetic Fusion Research
Keywords: CTR, cell calculation, diffusion, multigroup, neutron.