Abstract
The singular eigenfunction expansion method has been used to obtain the solution for the one-speed disadvantage factor in slab cells of fuel and moderator which may scatter neutrons in a highly an isotropic manner. New two-media cross-product integral relations, together with previously known one-medium orthogonality relations, have been utilized to obtain the solution. Sample calculations on slab cells of natural uranium and water show that, for cases in which the anisotropy of the scattering is quadratic or more, the disadvantage factor differs from the isotropic result by 7–27 per cent depending upon the order of the anisotropy, the effective mass of the scatterer, and the slab cell width. In all calculations, scattering in the fuel has been assumed to be isotropic.
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