1. NAME AND TITLE OF DATA LIBRARY
HELLO: 47 Neutron, 21 Gamma-Ray Group Cross Sections for Radiation Transport for
Neutron Energies up to 60 MeV.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAM
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
4. HISTORICAL BACKGROUND AND INFORMATION
The advantages of using a beam of deuterons on a lithium target to produce the intense source of
neutrons needed for radiation damage studies in the fusion research materials program have been
discussed in the past. The energy distribution of the neutrons produced by high-energy (~ 40 MeV)
deuterons on a lithium target extends to well above 15 MeV and thus to design a Li(D,n) radiation
damage facility it is necessary to have differential particle production cross section data at these higher
5. APPLICATION OF THE DATA
Calculated results of the dose equivalent vs. depth from an isotropic point source at the center of
a spherical shell heavy-concrete shield are presented to illustrate the use of the cross sections. The
energy distribution of the source neutrons is approximately that from a Li(D,n) neutron radiation
6. SOURCE AND SCOPE OF DATA
The sources of all of the cross section data used are given and discussed and the transport
calculations are described and the results presented. To test the adequacy of the neutron group
structure at the higher energies (> 14.9 MeV) calculated results obtained with the basic group
structure and with the number of neutron groups above 14.9 MeV doubled are presented. To test the
adequacy of the P5 angular expansion at the higher energies calculated results obtained using a P3
expansion at all energies are also presented. To indicate the importance of elastic scattering at energies
> 14.9 MeV for the sample problem considered here calculated results are also given with elastic
scattering from all elements, other than hydrogen neglected at energies > 14.9 MeV. The elements
H, 10B, 11B, C, O, Si, Ca, Cr, Fe, Ni, Heavy Concrete.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
8. DATA FORMAT AND COMPUTER
BCD/EBCDIC card images; IBM 360.
9. TYPICAL RUNNING TIME
Information not available.
R. G. Alsmiller, Jr. and J. Barish, "Neutron-Photon Multigroup Cross Sections for Neutron Energies < 60 MeV," ORNL/TM-6486 (August 1978).
LIBGEN: A Special Version of the ANISN Library Generation Routine which Converts a Card
Image FIDO Format Cross Section Tape into an Unformatted ANISN Library Tape.
11. CONTENTS OF LIBRARY
Included are the referenced documents and one (1.2MB) DOS diskette which contains the cross
section data, the retrieval program, plus output from the sample problem.
12. DATE OF ABSTRACT
KEYWORDS: ANISN FORMAT; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; MULTIGROUP CROSS SECTIONS