Gamma ray dose calculations using Monte Carlo methods

Photon transport studies are of great importance to nuclear engineers in shielding analysis and in other allied areas. Often shielding problems cannot be dealt by analytical methods because of irregular shapes in source and shield geometries. In practice some of the shielding problems can be handled by mathematical methods. Investigations through a cylindrical duct from a finite source placed at the centre of a 5 m.f.p. shield using analogue Monte Carlo method are presented. The results obtained for different source and finite shield geometries are presented. (author). 7 figs., 9 refs