1. NAME AND TITLE OF DATA LIBRARY
LIB123: AMPX-II P3 123-Group Neutron Cross Section Master Interface Library.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
AIM: Program to Convert the Mode (BCD to Binary); available in PSR- 63/AMPX-II.
Comitato Nazionale Energia Nucleare, Rome, Italy, through the NEA Data Bank, Gif-sur-Yvette Cedex, France.
4. HISTORICAL BACKGROUND AND INFORMATION
Nuclear criticality safety analysis requires fine group cross sections for precise criticality assessments in hot facilities. In order to obtain such cross section data, CNEN undertook the task of producing and testing a fine group neutronics library.
5. APPLICATION OF THE DATA
The cross section data can be used for criticality calculations. They have been tested with the KENO-IV Monte Carlo code.
6. SOURCE AND SCOPE OF DATA
The program AMPX-II (PSR-63) was used to generate the data. The P3 123-group neutron cross section library of various nuclides used in criticality calculations were generated from ENDF/B-IV data. The XLACS-2 module of AMPX-II generated the fine group cross section data in AMPX Master Interface format. Subsequent run by the NITAWL module produces cross section libraries in AMPX working format and/or ANISN format for use by Monte Carlo codes such as KENO-IV and MORSE or the discrete ordinates codes ANISN and DOT.
The 123 neutron energy group structure consists of the GAM-II boundaries with a 30-group THERMOS structure below 1.86 eV. Assuming 3.05 eV as a cutoff between fast and thermal hydrogen ENDF/B data, there are 91 epithermal groups with an upper cutoff of 14.9183 MeV. The fission-neutron energy range is covered by 60 groups ranging from 14.9183 MeV to 7.1 KeV. This grouping covers most of the cross section structure for light and intermediate nuclides and also takes into account inelastic scattering and fission thresholds for some heavy nuclides. The remaining 31 groups ranging between 7.1 KeV to 3.05 eV account for the resonance levels of various intermediate and heavy nuclides. The thermal range is covered by 32 groups.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAMS
The AIM module of PSR-63/AMPX-II can be used for mode conversion of the data.
8. DATA FORMAT AND COMPUTER
Card images; IBM 3090 (D00153ALLCP00).
9. TYPICAL RUNNING TIME
P. A. Landeyro, F. Siciliano, T. Abbas "AMPX-II 123 Multigroup Neutronic Library Validation for Fuel Storage Pools," CNEN-RT/ING(80)17, CNEN, Rome, Italy, 1980.
F. Siciliano, T. Abbas, "AMPX-II 123 Group Neutron Cross Section Library Validation for 4.29WT.% U-235 Enriched UO2 Fuel Storage Under Water," CNEN-RT/ING(80)18, CNEN, Rome, Italy, 1980.
F. Siciliano, G. Lai "A Complete AMPX-II 123 Group Neutron Cross Section Library Production and Testing for Criticality Safety Calculations," CNEN-RT/ING(82)10, CNEN, Rome, Italy, 1982.
F. Siciliano, T. Abbas, "AMPX-II 123 and 219 Group Neutron Cross Section Libraries Production and Validation For Criticality Safety Studies," CNEN-RT/ING(80)20, CNEN, Rome, Italy, 1980.
11. CONTENTS OF PACKAGE
The package contains referenced documents, and the data library. The data library is transmitted on one DC6150 cartridge tape in TAR format.
12. DATE OF ABSTRACT
KEYWORDS: AMPX INTERFACE FORMAT; MULTIGROUP CROSS SECTIONS; MULTIGROUP CROSS SECTIONS BASED ON ENDF; NEUTRON CROSS SECTIONS