1. NAME AND TITLE OF DATA LIBRARY
HILO86R: 66 Neutron, 22 Gamma-Ray Group Cross Sections for Radiation Transport for Neutron Energies Up to 400 MeV.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
BCBN: Converts ANISN card-image data to binary format.
Japan Atomic Energy Research Institute, Tokaimura, Japan.
4. HISTORICAL BACKGROUND AND INFORMATION
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-119, in which neutron data below 19.6 MeV is derived from DLC-113/VITAMIN-E (ENDF/B-V) except for sulfur and lead. In 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.
5. APPLICATION OF THE DATA
For a variety of applications (accelerator shielding, the use of neutrons in radiotherapy, radiation damage studies, etc.) It is necessary to carry out transport calculations involving medium-energy neutrons. HILO86R multigroup cross sections are in the form needed for the CCC-254/ANISN-ORNL and CCC-543/TORT-DORT discrete ordinates codes and in the CCC-474/MORSE-CGA Monte Carlo code.
6. SOURCE AND SCOPE OF DATA
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 than 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.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
BCBN will convert the data in ANISN format from card image to binary form.
8. DATA FORMAT AND COMPUTER
ASCII card images; All computers (D00187/ALLCP/00).
9. TYPICAL RUNNING TIME
On a PC 386, the program BCD2BIN converted the HILO86 BCD data into binary form in about 7 minutes.
a. Documentation available with library:
Hiroshi Kotegawa, Yoshihiro Nakane, Akira Hasegawa, and Shun-ichi Tanaka, "Neutron-Photon Multigroup Cross Sections for Neutron Energies Up to 400 MeV: HILO86R - Revision of HILO86 Library," JAERI-M 93-020 (February 1993).
b. Other useful documentation:
R. G. Alsmiller, Jr., J. M. Barnes, and J. D. Drischler, "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., pp 232, Springer Verlag (1991).
11. CONTENTS OF LIBRARY
Included are the referenced document in (10a) and one DS/HD 3.5-in. (1.44MB) DOS diskette which contains the cross sections, the BCD to binary conversion program, and input for the BCD-binary program in BCD card images.
12. DATE OF ABSTRACT
KEYWORDS: ALBEDO DATA; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; INTRANUCLEAR CASCADE; MICROCOMPUTER; MULTIGROUP CROSS SECTIONS; NEUTRON CROSS SECTIONS