1. NAME AND TITLE

KORIGEN: A Modification of the Isotope Generation and Depletion Code System ORIGEN.

CCC-702/ORIGEN-ARP is recommended for new ORIGEN users.

DATA LIBRARIES

KORIDATA: Reactor-specific effective cross-section library.

ORFI3: Light element cross-section library.

ORFI4: Heavy element cross-section library.

ORFI5: Fission product cross-section library.

ORFI6: Light element photon library.

ORFI7: Heavy element photon library.

ORFI8: Fission product photon library.

2. CONTRIBUTOR

Karlsruhe Nuclear Research Center, Karlsruhe, Federal Republic of Germany.

3. CODING LANGUAGE AND COMPUTER

Fortran IV, Assembler Language; IBM 3033/370-168.

4. NATURE OF PROBLEM SOLVED

KORIGEN is a modification of the isotope generation and depletion code system CCC-217/ORIGEN. ORIGEN solved the equations of radioactive growth and decay allowing continuous first order chemical processing and a neutron flux described by a three-region spectrum. Complex decay and transmutation schemes were treated. Note that this package has not been updated in many years; and all new ORIGEN users are advised to request the CCC-702/ORIGEN-ARP package, which is a PC application for Windows 95/NT or later.

5. METHOD OF SOLUTION

ORIGEN used a matrix exponential method to solve a large system of coupled, linear, first-order ordinary differential equations with constant coefficients. KORIGEN contains the following modifications to ORIGEN: 1) it uses reactor-physical effective cross sections for important nuclides, including burnup-dependent for actinides; 2) the spectral indices can be changed during irradiation; 3) it considers nuclide-specific fission energy release and the energy release resulting from (N,gamma)-reactions; 4) it provides an improved calculation of the neutron emission of irradiated fuel considering both the spontaneous fission of the transactinide nuclei and (alpha,n)-reactions; 5) gamma power is calculated directly from the gamma spectra and the infinite neutron multiplication factor is calculated during irradiation; 6) decay data, Q-values, fission yields, etc., are updated for nearly 1400 nuclides; 7) output options are improved allowing for more flexibility; 8) annual maximum permissible radiotoxicity values valid for the Federal Republic of Germany are included; 9) input is reproduced for validation purposes.

6. RESTRICTIONS OR LIMITATIONS

KORIGEN will handle 1400 nuclides of which 300 can be light element nuclides, 150 actinide and decay daughter nuclides, and 950 fission product nuclides. In addition, there may be no more than 6100 non-zero elements in the nuclear transmutation matrix.

7. TYPICAL RUNNING TIME

CPU times for the seven input examples are as follows:

1. PWR 34 sec

2. PWR (no time available)

3. PWR with U and MOX Fuel 74 sec

4. FBR 20 sec

5. PWR 47 sec

6. PWR 19 sec

7. PWR 14 sec

8. COMPUTER HARDWARE REQUIREMENTS

KORIGEN is operable on the IBM 3033/370-168 computer. Sample problem 1 was calculated with a load module with a REGION of 1 MB without application of OVERLAY.

9. COMPUTER SOFTWARE REQUIREMENTS

Fortran IV and Assembler Language compilers are required.

10. REFERENCE

U. Fischer and H. W. Wiese, "Improved and Consistent Determination of the Nuclear Inventory of Spent PWR Fuel on the Basis of Cell-Burnup Methods Using KORIGEN," KFK-3014; ORNL-tr-5043 (January 1983).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one (1.2MB) DOS diskette which contains the source code, sample problem, and library input and output.

12. DATE OF ABSTRACT

May 1984.

KEYWORDS: ISOTOPE INVENTORY; FISSION PRODUCT INVENTORY; MULTIGROUP; NEUTRON; GAMMA-RAY SOURCE