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Conference Article: Project of demonstration nuclear heating plant using pool-type water reactor

Baranaev, Yu.D.; Osennikh, G.M.; Sergeev, Yu.A. (State Research Center of Russian Institute of Physics and Power Engineering (SRC RF-IPPE), Obninsk (Russian Federation)); Mikhan, V.I.; Romenkov, A.A. (Research and Development Institute of Power Engineering (RDIPE), Moscow (Russian Federation))

Abstract

Since 1976 the first NPP equipped with a 10 MWt water-graphite reactor AM has been used for district heating and hot water supply. Development and enhancement of this experience is essentially actual and important scientific and economic task for the SRC RF-IPPE especially after the AM reactor is decommissioned in the nearest future. As one of possible variants of proceeding in this direction, construction of an NPP with a pool-type reactor RUTA is being considered. Development of a series of RUTA reactors of 10 through 50 MWt, and NHPs using a RUTA is being performed aiming at an autonomous nuclear power source for supplying heat to small settlements or cities/districts. A pool-type reactor RUTA possesses self-evident and transparent safety characteristics based on simplicity and reliability of the design, and inherent safety features using laws of nature. The NHP RUTA at the STC RF-IPPE could play a role of demonstration and could provide a more active inculcation of this reactor type to the market. The estimations performed on this basis indicate that if a 30 MWt (approx 25 Gcal/h) NHP RUTA is coupled with the local heating system, the NHP can secure up to 85% of yearly heat production. Taking into account highly developed site infrastructures, the expenditures for the NHP RUTA project (development and construction) at the SRC RF-IPPE could be approximately estimated as US$ 10-15 million.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Advisory group meeting and consultancy on experience with nuclear heat applications: district heating, process heat and desalination, 13-15 December 1995 and 7-9 February 1996.
Advisory group meeting on technology, design and safety aspects of non-electrical application of nuclear energy, 20-24 October 1997.
Advisory group meeting on operational modes of nuclear desalination plants, 3-5 November 1997.
Advisory group meeting on materials and equipment for the coupling interfaces of nuclear reactors with desalination and district heating plants, 21-23 April 1998.
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1056, pp:45-54