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Conference Article: Equipment and materials for coupling interfaces of a nuclear reactor with desalination and heating plants based on floating NHPS

Panov, Yu.K.; Polunichev, V.I. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))

Abstract

Intensive design activity is currently underway in Russia on floating nuclear installations, relying on proven marine NSSSs of KLT-40-type, which are capable of generating electricity, producing potable water and heat for industrial and district heating purposes. In particular, design work of the first floating power unit for a pilot nuclear co-generation station, which is due to be situated at the Pevek port area in the Chukotsky national district (extreme north-east of Russia), is approaching completion, and preparatory work is being carried out for fabrication of its most labour-intensive components. Work is also in progress together with 'CANDESAL Inc. (Canada)' on the conceptual design of a floating power-desalination complex. Most suitable options of floating power-desalination complexes are being sought, addressing requirements of potential customers. Earlier, at the IAEA technical committee meeting (1993) it was shown that a complex, which combines a highly effective condensation turbine and a modem reverse-osmosis desalination facility, could be considered as most preferable from the view point of efficient utilisation of thermal energy generated by nuclear reactors for co-production of potable water and electricity. The prospective technology for sea water desalination by a reverse-osmosis method is being developed in particular by 'CANDESAL Inc.'. It was also pointed out that another sufficiently efficient installation for potable water and electricity co-production is a dual-purpose complex which integrates both condensation and back-pressure turbines and a distillation desalination facility. Similar flow configurations were adopted for the nuclear desalination complex at Aktau (Kazakhstan) which has been in operation since 1972. 'SverdNIIKhimMash' institute (Ekaterinburg) is a Russian leading designer of modem distillation desalination facilities. This paper presents heat and fluid diagrams of floating complexes, brief description of their key components, used materials, radiological safety provision and instrumentation.

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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:249-262