1. NAME AND TITLE OF DATA LIBRARY
MATXS175/42-JEF87: JEF/EFF Based VITAMIN-J 175 Neutron, 42 Photon Multigroup Data Library in MATXS Format.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
BBC Computer Code for Converting Data to Binary Form and Vice Versa; available in PSR-206/TRANSX-CTR.
Swiss Federal Institute For Reactor Research, Würenlingen, Switzerland, through NEA Data Bank, Gif-sur-Yvette Cedex, France.
4. HISTORICAL BACKGROUND AND INFORMATION
The Joint European File (JEF) is a computer-readable repository of neutron and photon data in the energy range up to 20 MeV. Together with the recently Evaluated Fusion File (EFF), it is rapidly becoming the standard European data source for thermal reactors, fast reactors, fusion, shielding and controlled thermonuclear analysis. 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.
Discrete ordinate transport codes that solve the Boltzmann equation for the distribution of neutrons and photons in nuclear systems have reached a high level of development. Major users of these codes demand up-to-date, documented cross section data as input. Therefore, new multigroup nuclear data libraries based on JEF/EFF were generated for general applications. For this purpose, the NJOY (6/83) nuclear data processing system was used.
5. APPLICATION OF THE DATA
The coupled neutron-photon multigroup library was chosen to give a fine representation of the fast and epithermal neutron energy for fusion blanket and shielding analysis.
6. SOURCE AND SCOPE OF DATA
The Vitamin-J 175 neutron energy group structure has the same boundaries as the 174 group Vitamin-E (DLC-113) structure but with an additional boundary taken from the Vitamin-C structure at 12.84 MeV. The 42 photon energy group structure contains the energy boundaries of the 38 group Vitamin-E photon energy structure and the break points: 50, 30, 1.34 MeV, and 1 keV. The neutron ENDF data for the isotopes were taken from JEF-1, JEF-1.1, EFF-1, and ENDF/B-4. The original EFF-1 lead data were written in ENDF/B-VI and contains double differential scattering. The processed groupwise lead data do not include all features of the evaluated scattering laws. The ENDF/B-V photon interaction data were taken from the DLC-99/HUGO package, reconstructed with the module RECONR of NJOY (PSR-171) and put into multigroup form using GAMINR.
The GENDF's of the neutron energy structure and the 42 photon energy structure have been put into the MATXS format. NJOY (6/83) modules have been used to combine the individual isotope GENDF's for all materials and to reformat the resulting GENDF file into MATXS format. The MATXS file is a generalized cross section library in a flexible format similar to the CCCC standard cross section file ISOTXS.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAMS
The program BBC from PSR-206/TRANSX-CTR converts the data from BCD to binary form and vice versa.
8. DATA FORMAT AND COMPUTER
Card images; VAX family of computers (D00151D881000).
9. TYPICAL RUNNING TIME
P. Vontobel and S. Pelloni, "JEF/EFF Based Nuclear Data Libraries," EIR-Bericht Nr. 636, Swiss Federal Institute for Reactor Research, Würenlingen, Switzerland, December 1987.
11. CONTENTS OF PACKAGE
Included are the referenced document and the data libraries. The data library is transmitted on one DC6150 cartridge tape in TAR format.
12. DATE OF ABSTRACT
KEYWORDS: BASED ON ENDF/B-V; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; MULTIGROUP CROSS SECTIONS