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CCC-0653 REBUS3/VARIANT8.0.

REBUS3/VARIANT8.0, Code System for Analysis of Fast Reactor Fuel Cycles

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1. NAME OR DESIGNATION OF PROGRAM:  REBUS3/VARIANT8.0.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
REBUS3/VARIANT8.0 CCC-0653/02 Arrived 04-JAN-2002

Machines used:

Package ID Orig. computer Test computer
CCC-0653/02 SUN W.S.,IBM RISC6000 WS
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3. DESCRIPTION OF PROGRAM OR FUNCTION

REBUS-3 is a system of codes designed for the analysis of fast reactor fuel cycles. Two basic types of analysis problems are solved: 1) the infinite-time, or equilibrium, conditions of a reactor operating under a fixed fuel management scheme, or 2) the explicit cycle-by-cycle, or nonequilibrium operation of a reactor under a specified periodic or non-periodic fuel management program. For the equilibrium type problems, the code uses specified external fuel supplies to load the reactor. Optionally, reprocessing may be included in the specification of the external fuel cycle and discharged fuel may be recycled back into the reactor. For non-equilibrium cases, the initial composition of the reactor core may be explicitly specified or the core may be loaded from external feeds and discharged fuel may be recycled back into the reactor as in equilibrium problems.

Four types of search procedures may be carried out in order to satisfy user-supplied constraints: 1) adjustment of the reactor burn cycle time to achieve a specified discharge burnup, 2) adjustment of the fresh fuel enrichment to achieve a specified multiplication constant at a specified point during the burn cycle, 3) adjustment of the control poison density to maintain a specified value of the multiplication constant throughout the reactor burn cycle, and 4) adjustment of the reactor burn cycle time to achieve a specified value of the multiplication constant at the end of the burn step.

REBUS will handle both equilibrium and non-equilibrium problems using a number of different core geometries including triangular and hexagonal mesh. The neutronics solution may be obtained using finite difference, nodal diffusion-theory and variational nodal transport methods. Fixed source depletion may be done with the three solution methods. Other features include: fully automatic restart capability, no restrictions on number of neutron energy groups, and general external cycle with no restrictions on number of external feeds, reprocessing plants, etc. Fuel management is completely general for nonequilibrium problems. Microscopic cross sections are permitted to vary as a function of the atom density of various reference isotopes in the problem as appropriate for soft spectrum systems. The user may specify control rod positions at each time node in the problem. A number of relational database datasets containing various types of summary results are available for use in tailoring reports.

This is a standalone and expanded version of the modular REBUS-3 code system described in Ref. 1 and 2. REBUS-3 is fully compatible with the CCCC coding standards and interface data sets. It utilizes the DIF3D nodal option of DIF3D and VARIANT 8.0 (CCC-649) codes to obtain the neutronics solution. However, this CCC-653 distribution does not include the DIF3D main program which is in the CCC-649 DIF3D package.
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4. METHODS

The total reactor burn cycle time is divided into one or more subintervals, the number of which is specified by the user. An explicit burnup is performed in each region of the reactor over each of these subintervals using the average reaction rates over the subinterval. These average reaction rates are based on fluxes obtained from an explicit 1-, 2-, or 3-dimensional diffusion theory neutronics solution computed at both the beginning and end of the subinterval. The transmutation equations are solved by the matrix-exponential technique. The isotopes to be considered in the burnup equations, as well as their transmutation reactions, are specified by the user.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.
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6. TYPICAL RUNNING TIME

Three to thirty minutes or longer depending on size and complexity of problem and machine utilized.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
CCC-0653/02 04-JAN-2002 Masterfiled Arrived
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10. REFERENCES

- R. D. O'Dell:
  Standard Interface Files and Procedures for Reactor Physics Codes,
  Version IV," UC-32 (September 1977).
CCC-0653/02, included references:
- B.J. Toppel:
The Fuel Cycle Analysis Capability REBUS-3
ANL-83-2 (March 1983 revised October 26, 1990)
- R. P. Hosteny:
The ARC System Fuel Cycle Analysis Capability, REBUS-2
ANL-7721 (October 1978)
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11. HARDWARE REQUIREMENTS

The modular version of the code is in production use at Argonne National Laboratory on Unix Workstations Sun SPARCStation. External data storage must be available for approximately 40 scratch and interface files. Fourteen of these files are random access scratch files (grouped into 6 file groups), and the remainder are sequential access files with formatted or unformatted record types.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0653/02 FORTRAN-77, C-LANGUAGE
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13. SOFTWARE REQUIREMENTS

No special requirements are made on the operating system (SOLARIS 2.6 and 2.7 for SPARCStations and AIX 4.3.3 on the IBM). The included installation procedure requires Fortran 77 and C compilers. With modifications the program can be executed entirely in FORTRAN. Optional dynamic memory allocation and timing routines supplied from host machine libraries or code in "C" may be used on Unix workstations. Although developed on the Cray and IBM 30xx, the current version is tailored to Sun SparcStations and IBM AIX RS/6000.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                Radiation Safety Information Computational   
                Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:   Argonne National Laboratory
                Argonne, Illinois, U.S.A.
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16. MATERIAL AVAILABLE
CCC-0653/02
README.TXT Installation instructions
benchlib/  Directory with ASCII input/output files and binary files
src_rs6000/  REBUS3 Source code directory for two subroutines
PDF/  Directory with documentation files in PDF or HTML format
file_desc/  Directory with binary and ASCII (BCD) file descriptions
src/   REBUS3 Source code directory
BUILD.sh   Bourne Shell script
REBUS3_DISCLAIMER   REBUS3 disclaimer
VERIFY.sh  Bourne Shell script to run twenty-three REBUS3 test cases
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, criticality, diffusion, fast reactors, fuel cycle, fuel management, geometry.