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

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 replaceme...

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Bibliographic Details
Published inPower technology and engineering Vol. 37; no. 2
Main Authors 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.
Format Journal Article
LanguageEnglish
Published United States 15.03.2003
Subjects
BAFFLES
CAPACITY
COMMISSIONING
CONFIGURATION
CONTROL
ENGINEERING
MOISTURE
NUCLEAR POWER PLANTS
PLATES
REPAIR
STEAM GENERATORS
TESTING
WATER
WWER TYPE REACTORS
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Summary: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.
ISSN:1570-145X
1570-1468
DOI:10.1023/A:1024693011642