Computer Programs

NEA-1001 KORIGEN.

NEA-1001 KORIGEN.

KORIGEN, Isotope Inventory, Radiation Heat from PWR Burnup

NAME, COMPUTER, PROBLEM, SOLUTION, RESTRICTIONS, CPU, FEATURES, AUXILIARIES, STATUS, REFERENCES, LANGUAGE, OTHER RESTRICTIONS, AUTHOR, 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-1001/04	Arrived	28-JUL-2023

Machines used:

Package ID	Orig. computer	Test computer
NEA-1001/04	Linux-based PC

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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. METHODS

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 based on the Joint Evaluated File, Version 1, JEF1, especially allow reliable calculations for large Pressurized-Water reactors (PWR).

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8. RELATED OR 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-1001/04	28-JUL-2023	Masterfiled Arrived

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10. REFERENCES

NEA-1001/04, included references:

- U. Fischer, 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
ORNL-TR-5043 - 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. Fischer, H.W. Wiese:
KORIGEN short User's Guide (Sept. 1988)
- KORIGEN (Version July 1, 1990).

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-1001/04	FORTRAN-77

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

NEA Data Bank notes: Uses deprecated Fortran features, such as Alternate Returns, therefore it will not compile with GNU Fortran compilers but it does compile with Intel Fortran compilers.

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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-1001/04

\for\      KORIGEN FORTRAN files (main.f and subroutines)
\forconv\  Files and other data to prepare unformatted data files for KORIGEN
\exe\      Data files and korigen.input for a test case, and code executable
manual.pdf Reference manual for KORIGEN
1about    Short description of the code and file structure

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17. CATEGORIES

D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

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