Some neutron induced reaction cross-section calculations on 89Y

Abstract

With the increasing energy demand, the nuclear power plants, where the working principle depends on the fission principle, becomes more important on the solution of energy production. To be able to run these facilities in steady conditions, many control and operation principles needed to be followed and one of them is the moderation of neutrons. In this study, reaction cross-section calculations have been performed by using two most known and verified calculation programs, which are TALYS and EMPIRE, for some neutron induced reactions on 89Y and the obtained results have been compared with the exist experimental data obtained from EXFOR database. The selection of the material as 89Y was due to its possible usage of neutron moderator material at fission reactors