|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
|DLC-0187/01||Many Computers||PC Pentium III 500|
FORMAT: ANISN-ORNL, TORT-DORT and MORSE-CGA
NUMBER OF GROUPS: 66 neutron, 22 gamma-ray group cross sections for radiation transport for neutron energies up to 400 MeV
MATERIALS: H, C, N, O, Mg, Al, Si, K, Ca, Fe, Pb.
ORIGIN: ZZ-VITAMIN-E (ENDF/B-V), JENDL-3 microscopic cross section library
WEIGHTING SPECTRUM: flat
This cross-section library for multigroup transport calculations for neutron and photon energies up to 400 MeV and 20 MeV, respectively, is an upgrade of a similar library, DLC-0119, in which neutron data below 19.6 MeV is derived from ZZ-VITAMIN-E (ENDF/B-V) except for sulfur and lead. In ZZ-HILO86R only the cross sections below 19.6 Mev were replaced with data processed from the JENDL-3 microscopic cross section library. Self-shielding factors are used to produce effective cross sections for neutrons less than 19.6 MeV considering rather coarse energy meshes. ZZ-HILO86R multigroup cross sections are in the form needed for the ANISN-ORNL and TORT-DORT discrete ordinates codes and in the MORSE-CGA Monte Carlo code.
Neutron cross sections of 37 energy groups less than 19.6 MeV were collapsed from 295-neutron JSSTDL library based on JENDL3, considering self-shielding factors. Above that energy, differential elastic cross section data have been chosen so that the total, i.e., elastic + nonelastic, cross sections agree with experimental data. Photon cross sections were also condensed from the JSSTDL library using a flat weighting spectrum while secondary gamma-ray production cross sections did not change from those in HILO86. The library is P5. Data are provided for: H, C, N, O, Mg, Al, Si, K, Ca, Fe, Pb.
|Package ID||Status date||Status|
|DLC-0187/01||11-JUL-2002||Tested at NEADB|
R.G. Alsmiller et al.: Neutron Photon Multigroup Cross Sections for Neutron Energies Less than or Equal to 400 MeV (Revision 1) ORNL/TM-9801 (February 1986)
A. Hasegawa: Development of a Common Nuclear Group Constants Library System: JSSTDL 295n-104g Based on JENDL-3 Nuclear Data Library Nucl. Data Sci. and tech., pp232, Springer Verlag (1991)
Hiroshi Kotegawa et al.: Attenuation data of point isotropic neutron sources up to 400MeV in water, ordinary concrete and iron, JAERI-Data/Code 94-003 (August 1994)
|Package ID||Computer language|
Keywords: coupled neutron gamma cross sections, data library, group constants, multigroup, self-shielding, shielding.