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A Numerical Technique for Solving Group Diffusion Equations

Eugene L. Wachspress

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 164-170

Technical Paper / dx.doi.org/10.13182/NSE60-A25792

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.