1. NAME AND TITLE OF DATA LIBRARY

SINEX: 100-Group Neutron Reaction Cross-Section Data Generated by SUPERTOG from ENDF/B.

2. NAME AND TITLE OF RETRIEVAL PROGRAM

RESOLVE: A Program to List or Convert SINEX Data into Forms Suitable for Activity Calculations in ANISN.

3. CONTRIBUTOR

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

4. HISTORICAL BACKGROUND AND INFORMATION

Since 1968, the Radiation Shielding Information Center has provided the DLC-2 100 group, P8 expansion neutron cross section library generated with PSR-13/SUPERTOG from the latest ENDF/B library available. The nature of this library is such that all individual reaction cross sections are lumped together because their identity is not necessary for doing a neutron transport with codes such as ANISN. However, the need to calculate the spatial distribution of individual reaction rates has demonstrated the desirability of having available the individual multigroup reaction cross sections in a format consistent with the cross-section data used for the transport calculation. A recent modification to PSR-13/SUPERTOG allows the option to output these multigroup reaction cross-section data, and the result of processing the ENDF/B library has been preserved as DLC-24/SINEX. The name SINEX is an acronym for SUPERTOG Interpretation of ENDF/B X-sections.

5. APPLICATION OF THE DATA

The data can be used in combination with 100 group neutron transport calculations (using, for example, the DLC-2/100G library) to determine the spatial distribution of individual reaction rates. In particular, the retrieval program allows the preparation of dummy materials based on DLC-24/SINEX which can be used in the activity calculation option in ANISN to calculate the desired reaction rates.

6. SOURCE AND SCOPE OF DATA

DLC-24/SINEX was generated by PSR-13/SUPERTOG from nuclear data in either point-by-point or parametric representation as specified by ENDF/B. This data is averaged over each specified group width. For the top 99 groups, the explicit assumption was made that the flux (weighting function) has the shape of a fission spectrum joined at 0.0674 MeV by a 1/E tail. When resonance data were available, resolved and unresolved resonance contributions were calculated, using the infinite dilution approximation. For the thermal group (group 100), values for all materials except hydrogen were taken from the Maxwellian average values derived from the ENDF/B data. The values for hydrogen are more consistent for hydrogen in water. It should be noted that these thermal group values are in some cases different from values used in the latest version of DLC-2/100G.

The library consists of 100 group reaction cross sections for neutron interactions as follows: total, elastic, inelastic, (n,2n), fission,, (n,n'alpha), (n,n'3alpha), (n,2nalpha), absorption, (n,n'p), capture, (n,gamma), (n,p), (n,d), (n,T), (n,He3), (n,alpha), (n,2alpha), and nubar. The units are barns, except that nubar is the average number of neutrons per fission event. A table listing the reactions included for each material can be found in the packaged documentation.

The nuclides in DLC-24/SINEX are those which have been released as Category I ENDF/B by the National Neutron Cross Section Center, Brookhaven National Laboratory. The library contains data for:

H, D, He, 3He, 6Li, 7Li, 9Be, 10B, 11B, 12C, 14N, 16O, 23Na, Mg, 27Al, Si, Cl, K, Ca, V, Cr, 55Mn, Fe, 59Co, Ni, Cu, 63Cu, 65Cu, Nb, Mo, 107Ag, 109Ag, 135Xe, 133Cs, 149Sm, 151Eu, 153Eu, Gd, 164Dy, 175Lu, 176Lu, 181Ta, 182Ta, 182W, 183W, 184W, 186W, 185Re, 187Re, 197Au, Pb, 232Th, 233Pa, 234U, 235U, 238U, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 243Am, 244Cm.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

The data retrieval program can be used to list or selectively punch cards or write an unformatted tape in the ANISN cross-section formats. The purpose is to arrange the data so they can be read into ANISN as a dummy cross section material which can be used in the ANISN activity calculation to calculate the desired reaction rate distribution in a system of interest.

8. DATA FORMAT COMPUTER

BCD/EBCDIC card images; IBM 360/370.

9. TYPICAL RUNNING TIME

On an IBM 360/75 computer, SINEX required 10 seconds to process 124 reactions and produce an unformatted tape for ANISN input.

10. REFERENCES

R. Q. Wright and R. W. Roussin, "Description of the DLC-24/SINEX 100 Group One-Dimensional Cross Sections Based on ENDF/B," Informal note (February 1973).

R. W. Wright, "Input Instructions for RESOLVE, A Program for Listing or Converting DLC-24/SINEX Data into ANISN Cross Section Input Formats," Informal note (February 1973).

11. CONTENTS OF LIBRARY

Included are the referenced documents and a reel of magnetic tape which contains the cross-section library written in BCD card images, the retrieval program and sample problem input written in EBCDIC card images, plus output from the sample problem; total records 9567.

12. DATE OF ABSTRACT

February 1973; reviewed May 1984.