DLC-0187 ZZ-HILO86R.

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-HILO86R.

3. DESCRIPTION OF PROGRAM OR FUNCTION

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%  
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.
TEMPERATURES:
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.

4. METHOD OF SOLUTION

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.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

The conversion from ASCII to binary with the program ASC2BIN took less than 2 seconds.

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS:  BCBN: Converts ANISN card-image data to binary format.

10. REFERENCES

- 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.:
  Neutron-Photon Multigroup Cross Sections for Neutron Energies Up
  to 400 MeV: HILO86R - Revision of HILO86 Library
  JAERI-M 93-020 (February 1993)

11. MACHINE REQUIREMENTS:

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:   Japan Atomic Energy Research Institute
                Tokai-mura
                Japan

test-case data   mag tapeHILO86R.DAT Input file                     DATTP
test-case data   mag tapeDENSINFO.DAT Input file                    DATTP
source program   mag tapeBCD2BIN.FOR Source code                    SRCTP
test-case data   mag tapeADDRESS.DAT Input file                     DATTP
report                   JAERI-M 93-020 (February 1993)             REPPT