Reactor dosimetry issues have been analyzed in every aspect of extension of service life of non-restorable equipment of the Russian Vodo-Vodianoy Energetichesky Reactor (rus.) (VVER)-type reactors. A special attention has been focused on the role of neutron fluence and fluence rate uncertainties in prediction of the lifetime of the equipment. Results of analysis of service life justification of the first generation VVERs have been presented. A comparison of calculational and experimental dosimetry results are discussed in this paper. Usefulness of the Niobium-93 technique of fluence measurements as applied to template and trepan specimen dosimetry is especially emphasized in this paper.
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