Preparation of delayed neutron parameters for space–time calculations of thermal and fast reactors

Abstract

Different representations of the delayed-neutron parameters in neutron-physical problems are examined. Relations for averaging the kinetic parameters of nuclides and physical zones to make a systematic transition to the form required for implementation in computer programs performing calculations of different types of reactors are derived. The derivation employs the group space–time differential equations of neutron transport in different approximations according to the representation of the kinetic parameters. The exposition is given in a form that simplifies the programming of the relation presented. The particulars of the preparation of the delayed-neutron parameters for thermal and fast reactors are discussed.