1. NAME AND TITLE OF DATA LIBRARY

ORYX-E: ORIGEN Yields and Cross Sections--Nuclear Transmutation and Decay Data from ENDF/B-IV.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

COLAPS: Group Collapsing Code.

UPDATE: ORIGEN Fission Product data Library Update Code.

3. CONTRIBUTOR

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 cycle economics.

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.

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.

10. REFERENCES

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:

CCC-217/ORIGEN.

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.