Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213

In the frame of Tacis Project R2.01/99, which was running from 2003 to 2005, the bubble condenser system of Kola NPP (unit 3) was qualified at the integral test facility BC V-213. Three LB LOCA tests, two MSLB tests, and one SB LOCA test were performed. The appropriate test scenarios for BC V-213 te...

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Main Authors: Vladimir N. Blinkov, Oleg I. Melikhov, Vladimir I. Melikhov, Mikhail V. Davydov, Holger Wolff, Siegfried Arndt
Format: Article
Language:English
Published: Wiley 2012-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2012/275693
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author Vladimir N. Blinkov
Oleg I. Melikhov
Vladimir I. Melikhov
Mikhail V. Davydov
Holger Wolff
Siegfried Arndt
author_facet Vladimir N. Blinkov
Oleg I. Melikhov
Vladimir I. Melikhov
Mikhail V. Davydov
Holger Wolff
Siegfried Arndt
author_sort Vladimir N. Blinkov
collection DOAJ
description In the frame of Tacis Project R2.01/99, which was running from 2003 to 2005, the bubble condenser system of Kola NPP (unit 3) was qualified at the integral test facility BC V-213. Three LB LOCA tests, two MSLB tests, and one SB LOCA test were performed. The appropriate test scenarios for BC V-213 test facility, modeling accidents in the Kola NPP unit 3, were determined with pretest calculations. Analysis of test results has shown that calculated initial conditions and test scenarios were properly reproduced in the tests. The detailed posttest analysis of the tests performed at BC V-213 test facility was aimed to validate the COCOSYS code for the calculation of thermohydraulic processes in the hermetic compartments and bubble condenser. After that the validated COCOSYS code was applied to NPP calculations for Kola NPP (unit 3). Results of Tacis R2.01/99 Project confirmed the bubble condenser functionality during large and small break LOCAs and MSLB accidents. Maximum loads were reached in the LB LOCA case. No condensation oscillations were observed.
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institution Kabale University
issn 1687-6075
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language English
publishDate 2012-01-01
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series Science and Technology of Nuclear Installations
spelling doaj-art-944a5e8e82d04b1ba0e616c37bb885d32025-02-03T06:12:33ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832012-01-01201210.1155/2012/275693275693Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213Vladimir N. Blinkov0Oleg I. Melikhov1Vladimir I. Melikhov2Mikhail V. Davydov3Holger Wolff4Siegfried Arndt5Thermo-Hydraulics Division, Electrogorsk Research and Engineering Center for Safety of Nuclear Power Plants, Saint Constantine Street 6, Electrogorsk, Moscow 142530, RussiaThermo-Hydraulics Division, Electrogorsk Research and Engineering Center for Safety of Nuclear Power Plants, Saint Constantine Street 6, Electrogorsk, Moscow 142530, RussiaThermo-Hydraulics Division, Electrogorsk Research and Engineering Center for Safety of Nuclear Power Plants, Saint Constantine Street 6, Electrogorsk, Moscow 142530, RussiaThermo-Hydraulics Division, Electrogorsk Research and Engineering Center for Safety of Nuclear Power Plants, Saint Constantine Street 6, Electrogorsk, Moscow 142530, RussiaGesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Kurfürstendamm 200, 10719 Berlin, GermanyGesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Kurfürstendamm 200, 10719 Berlin, GermanyIn the frame of Tacis Project R2.01/99, which was running from 2003 to 2005, the bubble condenser system of Kola NPP (unit 3) was qualified at the integral test facility BC V-213. Three LB LOCA tests, two MSLB tests, and one SB LOCA test were performed. The appropriate test scenarios for BC V-213 test facility, modeling accidents in the Kola NPP unit 3, were determined with pretest calculations. Analysis of test results has shown that calculated initial conditions and test scenarios were properly reproduced in the tests. The detailed posttest analysis of the tests performed at BC V-213 test facility was aimed to validate the COCOSYS code for the calculation of thermohydraulic processes in the hermetic compartments and bubble condenser. After that the validated COCOSYS code was applied to NPP calculations for Kola NPP (unit 3). Results of Tacis R2.01/99 Project confirmed the bubble condenser functionality during large and small break LOCAs and MSLB accidents. Maximum loads were reached in the LB LOCA case. No condensation oscillations were observed.http://dx.doi.org/10.1155/2012/275693
spellingShingle Vladimir N. Blinkov
Oleg I. Melikhov
Vladimir I. Melikhov
Mikhail V. Davydov
Holger Wolff
Siegfried Arndt
Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213
Science and Technology of Nuclear Installations
title Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213
title_full Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213
title_fullStr Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213
title_full_unstemmed Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213
title_short Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213
title_sort experimental studies for the vver 440 213 bubble condenser system for kola npp at the integral test facility bc v 213
url http://dx.doi.org/10.1155/2012/275693
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