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The concept of the RUTA water-cooled water-moderated pool-type nuclear reactor is presented. The basic results of findings of the RUTA-70 pilot district heating plant in Obninsk science town, Kaluga Region, Russia, and capabilities of using this for nuclear technology research purposes are shown. The basic technical data of the reactor facility are presented and its design is described in brief. Potentials of using low-grade heat in the town's heating networks have been shown. Technical aspects of using the reactor thermal power in a thermal seawater desalination facility have been considered. Issues related to application of the nuclear reactor as a neutron source for implementing modern nuclear technologies have been discussed. 1. INTRODUCTION The efforts to develop the RUTA pool reactor launched in the late 1980s met the challenge of building an ultimately safe, structurally simple, cheap and easy-to-operate utility reactor to provide Russian cities with heating and hot water supply services. The concept of using a pool reactor as part of a nuclear district heating plant (NDHP) is based on a long-term positive experience in designing and operating pool research reactors: there are 225 research reactors in the power range from several kilowatts to 70 MW operated worldwide, including 23 NIKIET-designed reactors of which 7 are located in Russia. The simple design and low coolant parameters inherent to a pool reactor make it highly reliable with the absence of the potential of severe accidents being the assurance of radiation safety, which makes it possible to deploy facilities in the immediate proximity of consumers. The conceptual design of the RUTA-20 (reactor facility for heat supply with atmospheric pressure in the reactor) with a thermal power of 20 MW was issued in 1990. This development was given prominence at the ASMM-91 contents of small-size nuclear plant designs held in 1991-1992 under the auspices of the Russian Nuclear Society. Later on, the RUTA design options with a thermal power from 10 to 55 MW were developed at a conceptual level. The concept of using the RUTA pool reactor to desalinate seawater was developed in 1997. This included a reactor core consisting of two portions: one of these was the central part similar to that of conventional research reactors while the lateral part was formed by an assembly of modular channels capable to generate high-pressure steam to drive a small-size turbo-generator set. This facility produced up to 65 MW of thermal power and over 3 MW of electric power to operate the desalination plant pumps. When multistage distillation facilities were used, the fresh water output reached 35,000 m3/day (ROMENKOV A.A. et al., 1997). The results of using the RUTA pool reactor thermal power

Practical application of the RUTA safe pool-type nuclear reactor to demonstrate the advantages of atomic energy use