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RSIC DATA LIBRARY DLC-087


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.

3. CONTRIBUTOR

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

Not applicable.

8. DATA FORMAT AND COMPUTER

BCD card images; IBM 370/3033.

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCE

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

April 1985.

KEYWORDS: ALBEDO DATA; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; INTRANUCLEAR CASCADE; MULTIGROUP CROSS SECTIONS; NEUTRON CROSS SECTIONS