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Neutron-photon multigroup cross sections for neutron energies less than or equal to400 MeV. Revision 1

Conference ·
OSTI ID:5872498
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 to20 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. 7 refs., 1 fig.
Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
5872498
Report Number(s):
CONF-860610-4-Rev.1; ON: DE86005083
Country of Publication:
United States
Language:
English