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.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
