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Conference Article: Nuclear power plant with pressure vessel boiling water reactor VK-300 for district heating and electricity supply

Kuznetsov, Yu.N.; Lisitsa, F.D.; Tokarev, Yu.I.; Romenkov, A.A. (Research and Development Institute of Power Engineering, Moscow (Russian Federation))

Abstract

The viability for Russia of the Boiling Water Reactor (BWR) concept has been shown by a number of feasibility studies fulfilled for perspective sites with increased energy demands. Russia has long (31 year) successful experience in operation of NPPs with the vessel-type boiling reactor VK-50 which is located in the city of Dimitrovgrad. Taking into account the large Russian district heating market, it is expedient to apply this concept (BWR) not only for electricity supply, but also for district heating. This is a way to increase of nuclear power plant competitiveness along with good safety performance. The safety and protection of nuclear heat customer is guaranteed by reliable technical means which are well checked at Russian nuclear sites.

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key words: Gas Cooled Reactor, Nuclear Technology

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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:61-64