1. NAME AND TITLE OF DATA LIBRARY

SCALE-LIB: A 219 Group Set From JEF-1 In The AMPX Master Library Interface Format.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

PSR-63/AMPX-II Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B.

3. CONTRIBUTORS

ENEA, Bologna, Italy, through NEA Data Bank, Gif-sur-Yvette Cedex, France.

4. HISTORICAL BACKGROUND AND INFORMATION

The OECD International Criticality Working Group suggested the validation of JEF-1 (Joint European File) data in the Paris meeting of 1986. The AMPX-II code system was chosen as the application code. A neutron library was designed at ENEA to be generated by means of the appropriate AMPX-II modules, starting from the basic JEF-1 data. JEF is administered by the Nuclear Energy Agency (NEA Data Bank). The file has evolved through several updates, the current one being called JEF-1.

5. APPLICATION OF THE DATA

The neutron cross section libraries can be read into transport codes like ANISN and XSDRNPM. The Master Library Interface (MLI) format of the neutron data is relatively problem independent. To obtain a problem-dependent library, that is a Working Library Interface (WLI), the module NITAWL in the AMPX-II system can be used. NITAWL reads the MLI format of the SCALE-LIB, performs resonance self-shielding calculations and translates the multigroup cross sections in the WLI format, which ANISN or XSDRNPM can read. Since the DLC-149 library was generated with AMPX-II, it is compatible with SCALE releases prior to version 4. Changes made in AMPX-77 and SCALE-4 related to the implementation of the Nordheim Integral Treatment in the NITAWL module prohibit the use of pre-AMPX77 libraries in the new packages. PSR-315/AMPX-77 and CCC-545/SCALE 4 releases include a utility called CORECTOL which converts the pre-AMPX77 libraries to the new format. Since SCALE-LIB is in AMPX master format, it can be used with SCALE; but there is no connection to the SCALE system other than the format.

6. SOURCE AND SCOPE OF DATA

The 219 neutron group library is based on the JEF-1 data. Before processing the data, all materials had to be translated from ENDF/B-V to the ENDF/B-IV format with the use of the CRECT/J code.

Two weighting functions were used for the cross section averaging. All the data are given at reference temperature of 300 K. Seventy eight of the 219 energy groups are assigned to the thermal range.

The AMPX-II XLACS-2 module has been used to process all materials except hydrogen (the module XLACS was used in this case). Two procedures were available in the XLACS-2 module for calculating the elastic scattering matrices. For resonance nuclides, a procedure that utilizes previously generated elastic scattering point data is recommended; therefore the NPTXS module was used for all the materials for which resonance parameters are given in JEF-1. The RADE module of AMPX-II was used to check the processing of each nuclide.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

The AMPX-II modules are available as PSR-063 from the Radiation Shielding Information Center.

8. DATA FORMAT AND COMPUTER

Card images; IBM 3090 and all computers with about 50 megabytes of disk space.

9. TYPICAL RUNNING TIME

None noted.

10. REFERENCE

E. Cuccoli, G. C. Panini, F. Siciliano, "A 219 Neutron Group Set From JEF-1 In The AMPX Master Library Interface Format," JEF-DOC-181 (May 1987).

11. CONTENTS OF LIBRARY

The package contains the referenced document, and the data library. The data library is transmitted on one 1600 or 6250 BPI tape; 601,942 records.

12. DATE OF ABSTRACT

January 1991; May 1995.