Computer Programs

DLC-0038 ZZ-ORYX-E.

DLC-0038 ZZ-ORYX-E.

ZZ ORYX-E, Group Constant Library from ENDF/B Fission Product Data for ORIGEN Calculation

NAME, COMPUTER, PROBLEM, SOLUTION, CPU, AUXILIARIES, STATUS, REFERENCES, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

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1. NAME

ZZ-ORYX-E.

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2. COMPUTERS

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Program name	Package id	Status	Status date
ZZ-ORYX-E	DLC-0038/01	Tested	01-JUL-1979

Machines used:

Package ID	Orig. computer	Test computer
DLC-0038/01	IBM 360 series	IBM 360 series

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3. DESCRIPTION

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
FORMAT: ORIGEN

NUMBER OF GROUPS: 124 energy groups

NUCLIDES: H, He, Li, Be, B, C, N, O, F, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po.

ORIGIN: ENDF/B-IV

WEIGHTING SPECTRUM: Maxwellian (1/E) fission spectrum with a one percent tolerance.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
ORYX-E increases the versatility of the program 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.

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4. METHODS

The data is generated from ENDF/B-IV and is formatted for input to the ORIGEN code. Applications include calculations for waste projection, decay heat, nuclear safeguards, and fuel cycle economics.

The data library is generated from the ENDF/B-IV fission product data. The capture cross section of all fission product nuclides for which capture cross section information is given (about 180 nuclides) were processed into 124 energy groups using MINX. Multigroup cross sections were generated at 0 degrees with infinite dilution and one broad thermal group. Fine group data was generated using a Maxwellian (1/E) fission spectrum with a one percent tolerance.

Table 1. Comparison of Original ORIGEN and ENDF/B-IV Fission Product Data Library

	ENDF/B-IV	ORIGEN
Number of nuclides	825	461
Radioactive	712	338
First excited state	117	83
Second excited state	7	-
Delayed neutron precursors	57	-
Alpha decay	6
Positron decay	17	11
Cross sections (LMFBR) *1-group (n,γ) cross sections	181	423*

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6. 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.

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8. RELATED OR AUXILIARY PROGRAMS

COLAPS - can be used to collapse the fine cross sections by weighting with a user-specified reference spectrum.
UPDATE - will update the ORIGEN fission product data library using the cross sections generated with COLAPS.
Both utilities are included in the data package.

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9. STATUS

Package ID	Status date	Status
DLC-0038/01	01-JUL-1979	Tested at NEADB

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10. REFERENCES

DLC-0038/01, included references:

- Master Tape List
- Update of Tritium Data Sets on DLC-38, Informal Notes
- CCC-217/ORIGENS Feedback from User
- G.W. Morrison and C.R. Weisbin (September 1975)
- Energy Structure for the 124 Group Cross Sections
- G.W. Morrison, C.R. Weisbin, 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"  Reprint from Trans. Am. Nucl. Soc..19,
487-488 (1975)
C.W. Kee, C.R. Weisbin, R.E. Schenter;
"Processing and Testing of ENDF/B-IV Fission Product and Transmutation
Data"  Reprint from Trans. Am. Nucl. Soc.., 19
398-399 (1974)
- Documentation for CCC-217/ORIGEN Computer Code Package.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
DLC-0038/01	FORTRAN-IV

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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA

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16. MATERIAL AVAILABLE

DLC-0038/01

File name	File description	Records
DLC0038_01.001	INFORMATION	5
DLC0038_01.002	LIGHT ELEMENT LIBRARY (KEE; 5/78) EBCDIC	3370
DLC0038_01.003	ORFIP-X (124 GRP X-SECTION; 7/75) EBCDIC	8689
DLC0038_01.004	ORFIP-Y (YIELD&DECAY SCHEME; 1/76) EBCDIC	4105
DLC0038_01.005	NUCLIDE LIB. - STRUCTURAL MATERIALS (5/77)	1265
DLC0038_01.006	NUCLIDE LIB. - ACTINIDES & DECAY PROD.(1/76)	505
DLC0038_01.007	SUPPLEMENTARY ACTINIDES LIB. ADDED(11/74)	505
DLC0038_01.008	FISSION PRODUCTS(PACKAGED 7/73,UPDATED 1/76)	2305
DLC0038_01.009	PHOTON LIBRARY - LIGHT ELEMENTS (7/73)	253
DLC0038_01.010	PHOTON LIBRARY - HEAVY ELEMENTS (7/73)	202
DLC0038_01.011	FISSION PRODUCTS (PHOTON)	461
DLC0038_01.012	COLAPS - SOURCE PROGRAM (F4,EBCDIC)	52
DLC0038_01.013	COLAPS - DD CARDS	8
DLC0038_01.014	COLAPS - SAMPLE PROBLEM INPUT DATA	21
DLC0038_01.015	COLAPS - SAMPLE PROBLEM PRINTED OUTPUT	184
DLC0038_01.016	UPDATE - SOURCE PROGRAM (F4,EBCDIC)	43
DLC0038_01.017	UPDATE - DD CARDS	9
DLC0038_01.018	UPDATE - 'ORFIP-Y' WRITTEN BY UPDATE	4105
DLC0038_01.019	UPDATE - PRINTED OUTPUT	822

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17. CATEGORIES

ZZZ. ARCHIVE

Keywords: ENDF/B, cross sections, data, decay, fission products, multigroup.