Experimental Substantiation, Testing, and Commissioning of a Novel Separation System for Steam Generators of Nuclear Power Plants with VVER-1000 Reactors

Journal Article · Sat Mar 15 00:00:00 EST 2003 · Power Technology and Engineering (Print)

DOI:https://doi.org/10.1023/A:1024693011642· OSTI ID:21072593

Nigmatulin, B I; Ageev, A G; Blinkov, V N; Vasil'eva, R V; Korol'kov, B M; Dragunov, Yu G; Trunov, N B; Nekrasov, A V; Ilyushin, V F ^[1]

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1. Research Institute for Operation of Nuclear Power Plants (ENITs VNIIAES), Elektrogorsk, Elektrogorsk Research Center for Safety of Nuclear Power Plants of the All-Russian (Russian Federation)

The separation system of a PGV-1000 steam generator is modernized on the basis of bench tests of model PGV-1000 steam generators, full-scale tests of steam generators, and computational analysis of the results of these tests. The changes concern the configuration of the submerged plate and replacement of the louver separator by a receiver baffle. These measures increase the marginal evaporative capacity and the permissible range of variation of the water level, decrease the moisture content at the outlet from the steam generator, and improve the conditions for control and repair of its internal surface.

• OSTI ID: 21072593
• Journal Information: Power Technology and Engineering (Print), Vol. 37, Issue 2; Other Information: DOI: 10.1023/A:1024693011642; Copyright (c) 2003 Plenum Publishing Corporation; Country of input: International Atomic Energy Agency (IAEA); ISSN 1570-145X
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
BAFFLES
CAPACITY
COMMISSIONING
CONFIGURATION
CONTROL
MOISTURE
NUCLEAR POWER PLANTS
PLATES
REPAIR
STEAM GENERATORS
TESTING
WATER
WWER TYPE REACTORS