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Neutron-photon multigroup cross sections for neutron energies less than or equal to 400 MeV, Revision 1

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5580143
For a variety of applications, e.g., accelerator shielding design, neutrons in radiotherapy, radiation damage studies, etc., it is necessary to carry out transport calculations involving medium-energy (greater than or equal to 20-MeV) neutrons. A previous paper described neutron-photon multigroup cross sections in the ANISN format for neutrons from thermal to 400 MeV. In the present paper, the cross-section data presented previously have been revised to make them agree with available experimental data.
OSTI ID:
5580143
Report Number(s):
CONF-860610-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
Country of Publication:
United States
Language:
English