last modified: 02-JUL-1993 | catalog | categories | new | search |

NEA-1001 KORIGEN.

KORIGEN, Isotope Inventory, Radiation Heat from PWR Burnup

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1. NAME OR DESIGNATION OF PROGRAM:  KORIGEN.
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2. COMPUTERS
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Program name Package id Status Status date
KORIGEN NEA-1001/02 Tested 02-JUL-1993

Machines used:

Package ID Orig. computer Test computer
NEA-1001/02 SIEMENS 7890 DEC VAX 6000
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3. DESCRIPTION OF PROGRAM OR FUNCTION

KORIGEN calculates the nuclear  inventory - isotope and/or element concentrations, radioactivities,  heat, radiation - of nuclear fission reactor fuels and wastes, including (alpha,n)-neutrons in vitrified high-active waste, from given initial compositions, irradiation history and decay times.
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4. METHOD OF SOLUTION:  Matrix exponential method.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None.
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6. TYPICAL RUNNING TIME

Less than 30 seconds for typical fuel irradiation, fuel decay and waste decay.
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7. UNUSUAL FEATURES OF THE PROGRAM

The included data libraries on the basis of the Joint Evaluated File, Version 1, JEF1, especially allow reliable calculations for large Pressurized-Water reactors (PWR).
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8. RELATED AND AUXILIARY PROGRAMS

KORIGEN is an extension of the Oak  Ridge Isotope Generation and Depletion Code ORIGEN. The KORIGEN cross section libraries for Light-Water Reactors (LWR) include the LWR libraries of ORIGEN-2. The burnup-dependent actinide cross sections and burnup averaged cross sections for typical German PWRs  are generated with the Karlsruhe cell-burnup code KARBUS, a coupling of the UK spectral code WIMS and parts of ORIGEN.
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9. STATUS
Package ID Status date Status
NEA-1001/02 02-JUL-1993 Screened
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10. REFERENCES:
NEA-1001/02, included references:
- U. Fisher, H.W. Wiese:
  Improved and Consistent Determinationn of the Nuclear Inventory of
  Spent PWR Fuel on the Basis of Time-Dependent Cell-Calculations
  with KORIGEN
  KfK 3014 (January 1983)
- B. Duchemin and C. Nordborg:
  Decay Heat Calculation - An International Nuclear Code Comparison
  NEACRP-319 "L", NEANDC-275 "U" (April 1990)
- U. Fisher, H.W. Wiese:
  KORIGEN User's Guide
  (Sept. 1988)
- KORIGEN (Version July 1, 1990).
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11. MACHINE REQUIREMENTS

Minimum core storage: 600K bytes, eight external files are required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1001/02 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  MVS/SP2.2.1
(MVS-XA) in connection with JES 3.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  None.
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15. NAME AND ESTABLISHMENT OF AUTHORS

         H.W. Wiese
         Institut fuer Neutronenphysik und Reaktortechnik
         Kernforschungszentrum
         Postfach 3640
         D-7500 Karlsruhe, Germany
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16. MATERIAL AVAILABLE
NEA-1001/02
File name File description Records
NEA1001_02.001 Information file 67
NEA1001_02.002 FORT.MAIN KORIGEN main program (FORTRAN) 250
NEA1001_02.003 FORT.BLOCKDAT Routine source (FORTRAN) 79
NEA1001_02.004 FORT.ORIGEN Routine source (FORTRAN) 422
NEA1001_02.005 FORT.NUDATA Routine source (FORTRAN) 613
NEA1001_02.006 FORT.CHAN Routine source (FORTRAN) 43
NEA1001_02.007 FORT.CHAIN Routine source (FORTRAN) 90
NEA1001_02.008 FORT.PRIMAT Routine source (FORTRAN) 181
NEA1001_02.009 FORT.INVNUC Routine source (FORTRAN) 15
NEA1001_02.010 FORT.PHOLIB Routine source (FORTRAN) 150
NEA1001_02.011 FORT.HALF Routine source (FORTRAN) 18
NEA1001_02.012 FORT.NOAH Routine source (FORTRAN) 22
NEA1001_02.013 FORT.CVZE Routine source (FORTRAN) 70
NEA1001_02.014 FORT.TERM Routine source (FORTRAN) 236
NEA1001_02.015 FORT.DECAY Routine source (FORTRAN) 134
NEA1001_02.016 FORT.EQUIL Routine source (FORTRAN) 62
NEA1001_02.017 FORT.FLUXO Routine source (FORTRAN) 252
NEA1001_02.018 FORT.SIGBU Routine source (FORTRAN) 290
NEA1001_02.019 FORT.OUTPUT Routine source (FORTRAN) 760
NEA1001_02.020 FORT.SELECT Routine source (FORTRAN) 94
NEA1001_02.021 FORT.WRIPLO Routine source (FORTRAN) 74
NEA1001_02.022 FORT.GAMMA Routine source (FORTRAN) 576
NEA1001_02.023 FORT.ANSF Routine source (FORTRAN) 784
NEA1001_02.024 FORT.ALSPEK Routine source (FORTRAN) 77
NEA1001_02.025 FORT.DESCRI Routine source (FORTRAN) 913
NEA1001_02.026 CNTL.KORLOAD Generate KORIGEN load module 44
NEA1001_02.027 CNTL.CONVERT Generate KORIDATA library 237
NEA1001_02.028 CNTL.GENAN Generate N source data 372
NEA1001_02.029 CNTL.SAMPLE Run KORIGEN test case 94
NEA1001_02.030 DATA.ORM3 Nuclear data 1265
NEA1001_02.031 DATA.ORM4 Nuclear data 510
NEA1001_02.032 DATA.ORM5 Nuclear data 4110
NEA1001_02.033 DATA.ORM6 Nuclear data 253
NEA1001_02.034 DATA.ORM7 Nuclear data 202
NEA1001_02.035 DATA.ORM8 Nuclear data 821
NEA1001_02.036 DATA.M5JEF1 Nuclear data 5058
NEA1001_02.037 DATA.AN Nuclear data 721
NEA1001_02.038 DATA.HIBUJEF1 Nuclear data 1462
NEA1001_02.039 DATA.KFK3014 Nuclear data 1424
NEA1001_02.040 DATA.SAMPLE Test case output 3121
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, decay heat, inventories, isotopes, nuclear fuels.