1. NAME AND TITLE OF DATA LIBRARY
HILO: 66 Neutron, 21 Gamma-Ray Group Cross Sections for Radiation Transport for
Neutron Energies up to 400 MeV.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
No retrieval program is included in the package.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
4. HISTORICAL BACKGROUND AND INFORMATION
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. Neutron-photon multigroup cross sections in ANISN format for neutron energies from
thermal to 60 MeV were presented in a previous paper. In the present paper similar multigroup cross
sections are presented for several additional elements and the energy range of the cross section for all
elements considered is extended to 400 MeV.
5. APPLICATION OF THE DATA
At the higher energies considered here, medium-energy protons are produced. When the cross
section data described here are used in transport calculations, the neutron that will be produced by
these medium-energy protons is not included and thus an approximation is being made.
6. SOURCE AND SCOPE OF DATA
Below 15 MeV, the library consists of data derived from DLC-41/VITAMIN-C. Above that
energy, differential elastic cross section data from optical model calculations and nonelastic data from
the intranuclear-cascade-evaporation model are used. The library is P5 above 15 MeV, P3 below, in
ANISN format, with a retrieval code for BCD to binary conversion. Data are provided for:
H, 10B, 11B, C, N, O, Na, Mg, Al, Si, S, K, Ca, Cr, Fe, Ni, W, Pb.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
8. DATA FORMAT AND COMPUTER
BCD card images; IBM 370/3033.
9. TYPICAL RUNNING TIME
R. G. Alsmiller, Jr. and J. Barish, "Neutron Photon Multigroup Cross Sections for Neutron
Energies < 400 MeV," ORNL/TM-7818 (June 1981).
11. CONTENTS OF LIBRARY
Included are the referenced document and one (1.2MB) DOS diskette which contains the cross
sections for neutron energies up to 400 MeV, plus output from the conversion run.
12. DATE OF ABSTRACT
KEYWORDS: ALBEDO DATA; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; INTRANUCLEAR CASCADE; MULTIGROUP CROSS SECTIONS; NEUTRON CROSS SECTIONS