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Technological aspects of 99 Mo production from 235 U at the VVR-ts nuclear reactor are considered. The nuclear target design with which the formation of liquid and solid wastes is reduced to a minimum and the forced system for cooling of nuclear targets in experimental channels of the nuclear reactor are reported. Schemes of 99 Mo isolation from 235 U fission products and of 235 U regeneration after 99 Mo isolation are described. The 99 Mo and, correspondingly, 99m Tc produced from the regenerated 235 U fully meet the technical specification and pharmacopoeial monograph for sodium pertechnetate.