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

3. CONTRIBUTOR

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 energies.

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 damage facility.

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 are:

H, ¹⁰B, ¹¹B, C, O, Si, Ca, Cr, Fe, Ni, Heavy Concrete.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

BCD/EBCDIC card images; IBM 360.

9. TYPICAL RUNNING TIME

Information not available.

10. REFERENCES

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

March 1985.