Abstract
The paper is in two parts. First a solution of the multigroup diffusion equation using a weighted residual technique is described. The implementation enables high-order polynomial approximations to be made to the flux. Secondly the neutron transport equation is solved by expanding the flux in a series of unnormalized spherical harmonics, obtaining second-order diffusion-like equations for the coefficients in that series and applying the algorithm previously outlined.
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.
