A description is given of a number of methods of calculating the trans¬port of neutrons and γ-rays, mainly in reactor shields. Emphasis has been laid on the Monte-Carlo technique. All the methods described have been pro¬grammed for the electronic computer GIER at Riso, and some of them also for the IBM 7090 computer at the Danish Technical University, Lyngby.nA simple bulk shield programme system has been developed which calculates the penetration of neutrons as well as γ-rays throughout a reactor shield. The neutrons are treated according to the removal-diffusion theory with one removal and one diffusion group. The γ-ray calculation relies on the build-up concept.
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