1. NAME AND TITLE OF DATA LIBRARY
ORYX-E: ORIGEN Yields and Cross Sections--Nuclear Transmutation and Decay Data from
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
COLAPS: Group Collapsing Code.
UPDATE: ORIGEN Fission Product data Library Update Code.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
4. HISTORICAL BACKGROUND AND INFORMATION
ORYX-E increases the versatility of CCC-217/ORIGEN, the isotope generation and depletion code
package, by providing basic cross section and decay information for light element, fission-product,
and actinide nuclides. This data library package results from data compiled for ORNL Chemical
Technology Division's work with ORIGEN and from a 2-year effort of the Cross Section Evaluation
Working Group (CSEWG) Fission Product Task Force.
5. APPLICATION OF THE DATA
The data is generated from ENDF/B-IV and is formatted for input to the ORIGEN (CCC-217)
code. Applications include calculations for waste projection, decay heat, nuclear safeguards, and fuel
6. SOURCE AND SCOPE OF DATA
The data library is generated from the ENDF/B-IV fission product data which includes decay and
cross-section information as described in the following table. The capture cross-section information
of all fission product nuclides for which capture cross-section information is given (~180 nuclides)
was processed into 124 energy groups using MINX. Multigroup cross sections were generated at 0
with infinite dilution and one broad thermal group. Fine group data was generated using a Maxwellian
1/E fission spectrum with a 1% tolerance.
|Table 1. Comparison of Original ORIGEN and ENDF/B-IV Fission Product Data Library|
|Number of nuclides||825||461|
|First excited state||117||83|
|Second excited state||7||--|
|Delayed neutron precursors||57||--|
|Cross sections (LMFBR)||181||423*|
|*1-group (n,gamma) cross sections.|
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
A utility routine, COLAPS, can be used to collapse the fine cross sections by weighting with a user-specified reference spectrum.
A second utility routine, UPDATE, will update the ORIGEN fission product data library using the
cross sections generated with COLAPS. Both utility codes are included in the data package.
8. DATA FORMAT AND COMPUTER
EBCDIC card images; IBM 360.
9. TYPICAL RUNNING TIME
To collapse the cross sections, update the ORIGEN data tape, and run an ORIGEN sample problem
took about one minute on the IBM 360/91 (CPU) for about 10 time steps.
a. Included in the documentation:
G. W. Morrison, C. R. Weisbin, and C. W. Kee, "Decay Heat Analysis for an LMFBR Fuel Assembly Using ENDF/B-IV Data," Proceedings of Conference on Nuclear Cross Sections and Technology, Washington, D. C. (March 1975), to be published.
C. W. Kee,"A Revised Light Element Library for the ORIGEN Code," ORNL-TM-4896 (May 1975).
G. W. Morrison, C. R. Weisbin, and C. W. Kee, "Projected CRBRP Spent Fuel Characteristics and Their Impact on NDA Techniques," Trans. Am. Nucl. Soc., 19, (1975) 487-488.
C. W. Kee, C. R. Weisbin, and R E. Schenter, "Processing and Testing of ENDF/B-IV Fission
Product and Transmutation Data," Trans. Am. Nucl. Soc., 19 (1974) 398-399.
b. Background information:
11. CONTENTS OF LIBRARY
Included are the referenced documents (10.a) and one (1.2MB) DOS diskette which contains the
light element, nuclide, fission products, and photon libraries and the source and sample data for
COLAPS and UPDATE, plus output from COLAPS and UPDATE.
12. DATE OF ABSTRACT
September 1975; updated January 1976, March 1985.
KEYWORDS: MULTIGROUP CROSS SECTIONS; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B; NEUTRON CROSS SECTIONS; RADIOACTIVE DECAY SPECTRA; REACTION CROSS SECTIONS