1. NAME AND TITLE
ORIGEN-JR: A Code System for Calculating Radiation Sources and Analyzing Nuclide Transmutations. CCC-702/ORIGEN-ARP is recommended for new ORIGEN users.
ORIGEN-JR is based on the isotope generation and depletion code system, CCC-217/ORIGEN.
2. CONTRIBUTOR
Japan Atomic Energy Research Institute, Tokai-mura, Japan.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; FACOM 230/75.
4. NATURE OF PROBLEM SOLVED
ORIGEN-JR is a computer code for calculating radiation sources and analyzing nuclide transmutations which was based on the earlier code, ORIGEN. Calculation of neutron source spectra is extensively revised. In addition to spectrum indices adopted in ORIGEN, one-group cross-sections for each reaction can be used to treat the burnup conditions in a reactor core. Neutron and gamma-ray source data are generated in the same format as in QAD-P5, ANISN and DOT.
ORIGEN-JR solves the equations of radioactive nuclide transmutations and calculates radiation sources. Energy spectra of neutron sources in spontaneous fission and (alpha,n) reactions of eight nuclides (9Be, 10B, 11B, 13C, 14N, 17O, 18O, 19F) are available. Complex decay and transmutation schemes and one-group reaction cross sections can be treated.
ORIGEN-JR can be used as a computational module of the CCC-300/RADHEAT-V3 code system, and neutron and gamma-ray sources generated by this code can directly be applied to shielding calculation codes such as ANISN, DOT-II, and QAD-P5.
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
The program uses a matrix exponential method to solve a large system of coupled, linear, first-order ordinary differential equations with constant coefficients.
ORIGEN-JR can treat nuclear transmutations and radioactive sources because of 1) replacement of the neutron-induced cross-section by the effective value generated in the code, 2) incorporation of (alpha,n) reactions in a general form, and 3) incorporation of the neutron energy spectrum calculation in connection with spontaneous fission and (alpha,n) reactions.
6. RESTRICTIONS OR LIMITATIONS
The code will handle 850 nuclides of which no more than 500 are described as light elements, no more than 120 are actinides and their decay daughters, and no more than 500 are fission products.
Fission products are produced by fission rates of five different actinides. In addition, there may be no more than 3000 non-zero elements in the nuclear transmutation matrix. Numerical inaccuracies due to too coarse a time spacing are indicated by a warning message.
Neutron spectra due to an (alpha,n) reaction can be calculated by no more than 61 actinides and 8 light nuclides.
7. TYPICAL RUNNING TIME
Running time depends primarily on the (alpha,n) reaction calculation. A typical problem with 7 actinides and 2 light nuclides takes about 3 minutes on the FACOM 230/75.
8. COMPUTER HARDWARE REQUIREMENTS
ORIGEN-JR is operable on the FACOM 230/75 computer. It requires 680 K bytes of core storage.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required.
10. REFERENCE
ADDENDA to JAERI-M 8229.
K. Koyama, N. Yamano, and S. Miyasaka, "ORIGEN-JR: A Computer Code for Calculating Radiation Sources and Analyzing Nuclide Transmutations," JAERI-M 8229 (May 1979).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and 1 (1.2MB) DOS diskette which contains the source code and sample problem input and output.
12. DATE OF ABSTRACT
February 1982; revised February 1983, August 1991.
KEYWORDS: NEUTRON; GAMMA-RAY SOURCE; ISOTOPE INVENTORY; MULTIGROUP; ACTINIDES; FISSION PRODUCT INVENTORY