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Abstract
The concept of the RUTA water-cooled, water-moderated pool-type nuclear reactor is presented. The basic findings of the RUTA-70 pilot district-heating plant in the science town of Obninsk, Kaluga Region, Russia, and its capabilities for nuclear technology research purposes, are shown. The basic technical data of the reactor facility are presented and its design is described in brief. The potential of using low-grade heat in the town's heating networks is shown. The technical aspects of using the reactor's thermal power in a thermal seawater desalination facility are considered. Issues related to the application of the nuclear reactor as a neutron source for implementing modern nuclear technologies are discussed.
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