1. NAME AND TITLE OF DATA LIBRARY
NPCSL: Point Neutron Cross Sections Generated from ENDF/B-IV with the NPTXS Modules of PSR-63/AMPX-II.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAM
No retrieval program is included in the package.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
4. HISTORICAL BACKGROUND AND INFORMATION
This point cross section library, preprocessed from ENDF/B-IV using PSR-63/AMPX-II module NPTXS, contains data for neutron total, elastic scattering, capture, and fission (where appropriate) reactions. Data for 57 elements are provided in card image form. A retrieval program is supplied for conversion to unformatted form for use in the AMPX-II system.
5. APPLICATION OF THE DATA
These point data can be used to augment the input to the XLACS-2 module to skip resonance processing and/or calculate elastic scattering matrices to higher accuracy. Inverse total cross section weighting with XLACS-2 and LAPHNGAS for resonance nuclides can be accomplished using the NPCSL data. The data can also be used in the ROLAIDS module to perform an integral transport calculation and subsequently provide self-shielded multigroup cross sections.
6. SOURCE AND SCOPE OF DATA
NPTXS can "preprocess" resonance or nonresonance ENDF nuclides and make point files for the total, fission, elastic scattering, and (n,gamma) cross sections. The NPTXS-produced point data sets are as follows:
H, 6Li, 7Li, 9Be, 10B, 11B, 12C, 14N, 16O, 19F, 23Na, Mg, 27Al, Si, 31P, S, Ti, Cr, 55Mn, Fe, 59Co, Ni, Cu, 93Nb, Mo, 107Ag, 109Ag, 113In, 115In, Gd, 164Dy, 175Lu, 176Lu, Zirc-2, 181Ta, 182W, 183W, 184W, 186W, 185Re, 187Re, 197Au, Pb, 232Th, 233U, 234U, 235U, 236U, 238U, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 244Cm.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
8. DATA FORMAT AND COMPUTER
EBCDIC card images; IBM 370/3033.
9. TYPICAL RUNNING TIME
R. W. Roussin, "Description of DLC-82/NPCSL-81 Data Library Package," Informal Notes (April 1981).
"Summary of NPTXS Produced Point Data Sets," from AMPX Newsletter No. 2 (December 1977).
R. Q. Wright, "NPTXS - AMPX Module to Product Point Data for Resonance Nuclides," from ORNL/TM-3706 (March 1976).
11. CONTENTS OF LIBRARY
Included are the referenced documents and 1 tape cartridge which contains the point neutron cross sections from AMPX-II Module NPTXS for 57 elements from ENDF/B-IV, a BCD to binary conversion program (NPCONV), input data for the NPCONV sample problem written in EBCDIC card images, plus output from the sample problem.
12. DATE OF ABSTRACT
KEYWORDS: EVALUATED NEUTRON CROSS SECTIONS; NEUTRON CROSS SECTIONS