CROSS-SECTION CALCULATIONS FOR NEUTRON-INDUCED REACTIONS UP TO 50 MEV

In the field of accelerator development, medium-energy reaction cross- section data for structural materials of accelerator and shielding com ponents are required, especially for radiation protection purposes. Fo r a d + Li stripping reaction neutron source used in materials researc h, neutron reaction cross sections up to 50 MeV are necessary for the design study of neutron irradiation facilities. The current version of SINCROS-II is able to calculate neutron- and proton-induced reaction cross sections up to similar to 50 MeV with some modifications and ext ensions of the cross-section calculation code. The production of isoto pes when structural materials and other materials are bombarded with n eutrons or protons is calculated using a revised code in the SINCROS-I I system. The parameters used in the cross-section calculations are ma inly examined with proton-induced reactions because the experimental d ata for neutrons above 20 MeV are rare. The status of medium mass nucl ide evaluations for aluminum, silicon, chromium, manganese, and copper is presented. These data are useful to estimate the radiation and tra nsmutation of nuclei in the materials.