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CCC-0343 LEOPARD-MICRO.

LEOPARD-MICRO, Spectrum-Dependent Non-Spatial Fuel Depletion

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1. NAME OR DESIGNATION OF PROGRAM:  LEOPARD-MICRO.
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2. COMPUTERS
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Program name Package id Status Status date
LEOPARD-MICRO CCC-0343/01 Tested 02-AUG-1990

Machines used:

Package ID Orig. computer Test computer
CCC-0343/01 IBM PC IBM PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

LEOPARD determines fast and thermal spectra, using only basic geometry and temperature data, based on a modified MUFT-SOFOCATE model. The code optionally computes fuel depletion effects for a dimensionless reactor and recomputes the spectra before each discrete burnup step.
LEOPARD will automate the spectra calculations defined by Strawbridge in WCAP-3269-25 and will account for the variation of neutron spectra with fuel depletion. The latter task is achieved by  performing the spectra calculations, calculating fuel depletion for  a given time increment, recalculating spectra, etc. The burnup calculations are non-spatial.
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4. METHOD OF SOLUTION

The user supplies the reactor geometry, compositions and temperatures. The code temperature corrects the input data and computes number densities and three epithermal cross  sections (for the fuel pellet, the clad and moderator, and the homogenized cell) to be used in the spectrum calculations.
LEOPARD assumes that every reactor contains a large array of unit fuel cells arranged in either a square lattice or a hexagonal lattice. Each unit cell contains one cylindrical fuel rod, a metallic clad around the fuel rod, and a moderator. In a real reactor this geometry is adequate within a large fuel bundle, but commonly several percent of the core is taken up by control rod followers, water slots, assembly cans, structure, etc. LEOPARD accounts for this by allowing a fictitious region to be defined and  described in a manner entirely analogous to the description of the "real" regions within the unit fuel cell. Spectrum calculations are  then done on an "equivalent" unit cell.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.
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6. TYPICAL RUNNING TIME

The sample input problem LEOIN took 2 minutes on the IBM PC/XT; the sample burnup problem PS7 took about 20 minutes.
CCC-0343/01
NEA-DB compiled the program and ran the test cases included in this package on an IBM PC/at personal computer and for comparison reasons also on a DEC VAX 8810. Results obtained on both  machines were consistent with each other. On the PC: the program compiled (with MS FORTRAN 5.0) in 10m33s, and executed in 59s (case  1) and 11m5s (case 2).
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:  LEOPARD (NESC0279).
CCC-0343/01
SPS                 SPOTS4 source routine
SGDL                SPOTS4 Group Data Library
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9. STATUS
Package ID Status date Status
CCC-0343/01 02-AUG-1990 Tested at NEADB
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10. REFERENCES:
CCC-0343/01, included references:
- B.R. Leonard, Jr. et al.:
  Cross-Section Standardization for Thermal Power Reactors
  EPRI 221 (July 1975).
- R.F. Barry:
  LEOPARD - A Spectrum Dependent Non-Spatial Depletion Code for the
  IBM-7094
  WCAP-3269-26 (September 1963).
- Jung-Do Kim and Jong Tai Lee:
  SPOTS4 - Group Data Library and Computer Code Preparing ENDF/B-4
  Data for Input to LEOPARD
  IAEA-NDS-36 Rev. 0 (September 1981).
- Jung-Do Kim and Jong Tai Lee:
  Benchmark Test and Adjustment of an Updated Library from ENDF/B-IV
  (A draft of a paper submitted for publication in Journal of Korean
  Nuclear Society) (May 1981).
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11. MACHINE REQUIREMENTS:  The code is operable on IBM PC.
CCC-0343/01
IBM PC/AT or compatible. The program executes in 196K of RAM.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0343/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

A FORTRAN IV compiler is required. The IBM PC version uses the Microsoft FORTRAN  Version 4.1 compiler and can be compiled with or without a math coprocessor. The executable file distributed by RSIC does not require the coprocessor.
CCC-0343/01
MS-DOS 3.20 with compiler Microsoft FORTRAN VERSION 5.0
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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:
              Electric Power Research Institute
              Palo Alto, California

              Westinghouse Electric Corporation
              Pittsburgh, Pennsylvania

              Battelle Pacific Northwest Laboratories
              Richland, Washington

              Korea Advanced Energy Research Institute
              through the:
              Nuclear Data Services of the
              International Atomic Energy Agency
              Vienna, Austria
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16. MATERIAL AVAILABLE
CCC-0343/01
File name File description Records
CCC0343_01.001 Information file 142
CCC0343_01.002 ACCUM.FOR Source file for PC and VAX 204
CCC0343_01.003 BURN.FOR Source file for PC and VAX 196
CCC0343_01.004 FUNCT.FOR Source file for PC and VAX 78
CCC0343_01.005 INGR.FOR Source file for PC and VAX 276
CCC0343_01.006 INPUT.FOR Source file for PC 258
CCC0343_01.007 MAIN.FOR Source file for PC 142
CCC0343_01.008 MASSED.FOR Source file for PC and VAX 226
CCC0343_01.009 MUFT.FOR Source file for PC 177
CCC0343_01.010 OUTPUT.FOR Source file for PC and VAX 250
CCC0343_01.011 RESINT.FOR Source file for PC and VAX 107
CCC0343_01.012 SLOW.FOR Source file for PC and VAX 148
CCC0343_01.013 THRMAL.FOR Source file for PC 122
CCC0343_01.014 WORKS.FOR Source file for PC and VAX 272
CCC0343_01.015 LEOLIB Binary library for MS Fortran 1009
CCC0343_01.016 LEO.EXE Executable file 1599
CCC0343_01.017 LEOIN Sample input for case-1 13
CCC0343_01.018 PS7 Sample input for case-2 26
CCC0343_01.019 TEST1DB.OUT Sample output for case-1 337
CCC0343_01.020 TEST2DB.OUT Sample output for case-2 4304
CCC0343_01.021 COMPILE.BAT Batch file for comp&link (MS) 3
CCC0343_01.022 RUN.BAT Batch file for execution (MS) 3
CCC0343_01.023 INPUTVX.FOR Source file for VAX 270
CCC0343_01.024 MAINVX.FOR Source file for VAX 145
CCC0343_01.025 MUFTVX.FOR Source file for VAX 183
CCC0343_01.026 THRMALVX.FOR Source file for VAX 130
CCC0343_01.027 LEOLIB.COD Formatted library 7970
CCC0343_01.028 LEOLIB.BIN Binary library for VAX 67
CCC0343_01.029 READLIB.FOR Source file for reading binary 74
CCC0343_01.030 WRITELIB.FOR Source file for writing binary 77
CCC0343_01.031 CL.COM Command file for comp&link(VAX) 3
CCC0343_01.032 RUN.COM Command file for execution(VAX) 3
CCC0343_01.033 DOS file-names 32
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, depletion, spectra.