A Numerical Technique for Solving Group Diffusion Equations
- 1 August 1960
- journal article
- research article
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 8 (2) , 164-170
- https://doi.org/10.13182/nse60-a25792
Abstract
An efficient method for solving group diffusion equations is described. Application of the Perron Frobenius theory of non-negative matrices allows a direct determination of reactor criticality without calculation of neutron fluxes. Higher flux modes may also be found. Simultaneous calculation of all flux groups simplifies formulation with inelastic- and up-scattering, and also provides a convenient tool for some kinetics studies.Keywords
This publication has 2 references indexed in Scilit:
- Reactor Criticality and Nonnegative MatricesJournal of the Society for Industrial and Applied Mathematics, 1958
- THE MULTIGROUP DIFFUSION EQUATIONS OF REACTOR PHYSICSPublished by Office of Scientific and Technical Information (OSTI) ,1958