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NESC0387 CITATION.

CITATION, 3-D MultiGroup Diffusion with 1st Order Perturbation and Criticality Search

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1. NAME OR DESIGNATION OF PROGRAM:  CITATION.
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2. COMPUTERS
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Program name Package id Status Status date
CITATION-2 NESC0387/02 Tested 28-JUN-1982
CITATION NESC0387/06 Tested 20-NOV-1981
CITATION-2 NESC0387/09 Tested 02-AUG-1990
CITATION NESC0387/11 Tested 21-APR-1995

Machines used:

Package ID Orig. computer Test computer
NESC0387/02 CDC CYBER 174 CDC CYBER 174
NESC0387/06 IBM 3033 IBM 3033
NESC0387/09 MICROVAX DEC VAX 8810
NESC0387/11 IBM PC PC-80486
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3. DESCRIPTION OF PROBLEM OR FUNCTION

CITATION is designed to solve problems using the finite-difference representation of neutron diffusion theory, treating up to three space dimensions with arbitrary group-to-group scattering. X-y-z, theta-r-z, hexagonal-z,  and triagonal-z geometries may be treated. Depletion problems may be solved and fuel managed for multi-cycle analysis. Extensive first-order perturbation results may be obtained given microscopic data and nuclide concentrations. Statics problems may be solved and perturbation results obtained with microscopic data.
CITATION-2-3-VP2 is a vectorized version for FACOM VP-100 and VP-200 vector computers.
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4. METHOD OF SOLUTION

Explicit, finite-difference approximations in space and time have been implemented. The neutron-flux-eigenvalue problems are solved by direct iteration to determine the multiplica- tion factor or the nuclide densities required for a critical system.  CITATION-2-3-VP2: Algorithms for the inner-outer iterative calculations are adapted to vector computers. The SLOR method, which is used in the original CITATION code, and the SOR method, which is  adopted in the revised code, are vectorized by odd-even mesh ordering.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

CITATION has been designed to attack problems which can be run in a reasonable amount  of time. Storage of data is allocated dynamically to give the user flexibility in dimensioning. Typically, a finite-difference diffusion problem could have 200 depleting zones, 10,000 nuclide densities, and 30,000 space-energy point flux values.
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6. TYPICAL RUNNING TIME

The two-dimensional finite-difference diffusion theory eigenvalue problems iterate at a rate of about 0.1  millisecond per point per iteration with alternating-direction line  relaxation (two sweeps per iteration) with 8-byte words on the IBM 360/91 (0.5 on the 360/75). Since about 30 iterations are required for each succeeding eigenvalue problem, machine time for a depletion problem is about 0.003 second per point per time-step. Machine time  for most auxiliary calculations is usually insignificant. For a
representative fast breeder depletion problem, 68 percent of the machine CPU time is spent in solving eigenvalue problems. CITATION-2 (NESC0387/02): NEA-DB executed the test case on CDC CYBER 174 in 44 CP seconds.
NESC0387/11
NEA-DB executed the test case included in this package  on a PC/80486 (66MHz) in about 18 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM

CITATION is considered unusual in  that it should be relatively easy to modify the contents or to add routines. Effective techniques are incorporated to determine a critical system. More than one set of microscopic cross sections may be used and nuclide behavior can be followed on a sub-zone scale within depletion regions. The user has flexible control over the route of a calculation as well as the edit of results.
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8. RELATED AND AUXILIARY PROGRAMS

The microscopic cross section tape  for this program may be generated by various codes, but XSDRN is designed specifically for this purpose. The microscopic cross section routines, formerly an auxiliary program, were integrated into the code to permit such data to be supplied from cards or modified in the same run in which the problem is solved.
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9. STATUS
Package ID Status date Status
NESC0387/02 28-JUN-1982 Tested at NEADB
NESC0387/06 20-NOV-1981 Tested at NEADB
NESC0387/09 02-AUG-1990 Tested at NEADB
NESC0387/11 21-APR-1995 Tested at NEADB
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10. REFERENCES

- T.B. Fowler, D.R. Vondy and G.W. Cunningham:
  Nuclear Reactor Core Analysis Code CITATION,
  ORNL-TM-2496, Supplement 1 (October 1971), Supplement 2 (March
  1972), Supplement 3 (July 1972).
- N.M. Greene and C.W. Craven, Jr.:
  XSDRN, A Discrete Ordinates Spectral Averaging Code,
  ORNL-TM-2500 (July 1969).
NESC0387/02, included references:
- T.B. Fowler, D.R. Vondy and G.W. Cunningham:
  Nuclear Reactor Core Analysis Code CITATION
  ORNL-TM-2496, Revision 2 (July 1971)
- D.R. Vondy and T.B. Fowler:
  Job Stream of Cases for the Computer Code CITATION
  ORNL-TM-3793 (July 1972)
- NESC Note 81-66:
  CITATION Tape Description and Implementation Information
  (July 17, 1981)
NESC0387/06, included references:
- T.B. Fowler, D.R. Vondy and G.W. Cunningham:
  Nuclear Reactor Core Analysis Code CITATION
  ORNL-TM-2496, Revision 2 (July 1971)
- D.R. Vondy and T.B. Fowler:
  Job Stream of Cases for the Computer Code CITATION
  ORNL-TM-3793 (July 1972)
- NESC Note 81-66:
  CITATION Tape Description and Implementation Information
  (July 17, 1981)
NESC0387/09, included references:
- T.B. Fowler, D.R. Vondy and G.W. Cunningham:
  Nuclear Reactor Core Analysis Code CITATION
  ORNL-TM-2496, Revision 2 (July 1971)
- D.R. Vondy and T.B. Fowler:
  Job Stream of Cases for the Computer Code CITATION
  ORNL-TM-3793 (July 1972)
- NESC Note 81-66:
  CITATION Tape Description and Implementation Information
  (July 17, 1981)
NESC0387/11, included references:
- T.B. Fowler, D.R. Vondy and G.W. Cunningham:
  Nuclear Reactor Core Analysis Code CITATION
  ORNL-TM-2496, Revision 2 (July 1971)
- D.R. Vondy and T.B. Fowler:
  Job Stream of Cases for the Computer Code CITATION
  ORNL-TM-3793 (July 1972)
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11. MACHINE REQUIREMENTS

IBM 360/91 or equivalent with at least 128,000 32-bit words of directly-addressable main storage, 7 to 32 I/O devices depending upon the calculation, excluding input and output devices and system requirements.
NESC0387/02
(CITATION-2): 125,000 octal words are required on CDC CYBER 174 using segmentation.

NESC0387/11
Hardware requirements:
- Intel 80386 processor or equivalent (Intel 80486 should be OK,   but not tested)
- Weitek 3167 numeric coprocessor or Intel 80387 numeric   coprocessor
- All available memory will be utilized, but 1 Mbyte of extended   memory is recommended.
*******************************************************************
Systems with 80386-387 combination, or with a 80486, should be able  to  run the executable CITINTEL.EXE whereas systems equipped with a
Weitek 3167 coprocessor should be able to run the executable CITWEITK.EXE.
*******************************************************************
The sample problem was run at the NEA/DB on a PC DELL 466/L (processor 80486 , 67 MHz, base memory of 640 Kbyte and extended memory of 15648 Kbyte).
The filesizes of the two executables CITINTEL.EXE and CITWEITK.EXE created using the Lahey F77L-EM/32 compiler, are 1.04 Mbyte and 1.10 Megabyte respectively.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0387/02 FORTRAN-IV
NESC0387/06 FORTRAN+ASSEMBLER
NESC0387/09 FORTRAN-77
NESC0387/11 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  OS/360 (IBM 360). NOS 1.4-531 (CDC CYBER 174).
NESC0387/11
NEA-DB installed the program under MS-DOS 6.20.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

CITATION contains about 28,700 source statements. Without overlay, storage for the code instructions would approach 574,000 32-bit words, but with overlay the storage requirement is about 90,000 for  the program and fixed storage, 10,000 of this 90,000 is used for system library routines.
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by:
T.B. Fowler, D.R. Vondy, and G.W. Cunningham
Oak Ridge National Laboratory
P.O. Box X
Oak Ridge, Tennessee 37830
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16. MATERIAL AVAILABLE
NESC0387/02
File name File description Records
NESC0387_02.002 CITATION-2 INFORMATION 24
NESC0387_02.003 CITATION-2, SOURCE (FORTRAN-4) 28214
NESC0387_02.004 CITATION-2, SEGMENTATION DIRECTIVES 112
NESC0387_02.005 CITATION-2, INPUT FOR TEST CASE 825
NESC0387_02.006 CITATION-2, PRINTED OUTPUT OF TEST CASE 3258
NESC0387/06
File name File description Records
NESC0387_06.001 CITATION SOURCE (F4) 28521
NESC0387_06.002 ICLOCK ROUTINES (ASSEMBLER) 92
NESC0387_06.003 IDAY ROUTINES (ASSEMBLER) 63
NESC0387_06.004 ITIME ROUTINES (ASSEMBLER) 12
NESC0387_06.005 MODEL ROUTINES (ASSEMBLER) 26
NESC0387_06.006 SAMPLE PROBLEM INPUT 850
NESC0387_06.007 SAMPLE PROBLEM OUTPUT 3459
NESC0387_06.008 JCL AND INFORMATION 150
NESC0387/09
File name File description Records
NESC0387_09.001 Information file 69
NESC0387_09.002 CITATION-2 source program (FORTRAN-77) 28704
NESC0387_09.003 CITATION-2 test case input data 904
NESC0387_09.004 CITATION-2 test case printed output 3197
NESC0387/11
File name File description Records
NESC0387_11.001 CITATION Information File 203
NESC0387_11.002 Intel 80387 executable version of CITATION 0
NESC0387_11.003 Weitek 3167 executable version of CITATION 0
NESC0387_11.004 Sample input file for CITATION -test problem 850
NESC0387_11.005 Sample output file from running CIT.INP 3459
NESC0387_11.006 DOS file-names 5
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17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
  • K. Reactor Systems Analysis

Keywords: buckling, criticality searches, depletion, diffusion, fuel management, hexagonal configuration, multigroup, one-dimensional, r-theta, three-dimensional, two-dimensional, x-y-z.