Computer Programs

NEA-1001 KORIGEN.

NEA-1001 KORIGEN.

KORIGEN, Isotope Inventory, Radiation Heat from PWR Burnup

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: KORIGEN.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

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		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.