[en] Numerous disposal concepts have been investigated for the disposal of high-level wastes from reprocessing as well as direct disposal of spent fuel elements. This research and development work included the evaluation of the radiation exposure of the repository workers as a result of direct as well as scattered radiation experienced while handling the sources during emplacement in a repository. The transport and disposal underground were assumed to be either in POLLUX casks or in the case of consolidated fuel rods (cut to length to fit) in thick walled canisters, similar in dimensions to the canisters for vitrified HLW. These canisters and casks are to be transported underground in a transfer cask and disposed of in boreholes. The ''Active Handling Experiment with Neutron Sources (AHE)'' is a demonstration test to investigate the above mentioned radiological aspects of handling spent fuel and vitrified high-level active waste. Neutron dose rates are measured resulting from direct radiation and from neutrons scattered by the surrounding host rack (rock salt). The MORSE-SCG computer code and model calculations are verified by these demonstration tests. Thus, an experimentally validated tool will be available for future detailed repository design with emphasis on minimizing the radiation exposure of the operating personnel