A new design of nuclear power plant (NPP) with pressurized water reactor “NPP-2006” was developed in Russia. It represents the evolutionary development of the designs of NPPs with VVER-1000 reactors. Horizontal steam generator PGV-1000 MKP with in-line arrangement of the tube bundles will be used in “NPP-2006”. PGV test facility was constructed at the Electrogorsk Research and Engineering Center on NPP Safety (EREC) to investigate the process of the steam separation in steam generator. The description of the PGV test facility and tests, which will be carried out at the facility in 2009, are presented in this paper. The experimental results will be used for verification of the 3D thermal-hydraulic code STEG, which is developed in EREC. STEG pretest calculation results are presented in the paper.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4353-6
PROCEEDINGS PAPER
Thermal-Hydraulic Studies of the Steam Separation in Horizontal Steam Generator at PGV Test Facility
Yuriy V. Parfenov,
Yuriy V. Parfenov
Electrogorsk Research and Engineering Center on Nuclear Power Plants Safety, Electrogorsk, Moscow Region, Russia
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Oleg I. Melikhov,
Oleg I. Melikhov
Electrogorsk Research and Engineering Center on Nuclear Power Plants Safety, Electrogorsk, Moscow Region, Russia
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Vladimir I. Melikhov,
Vladimir I. Melikhov
Electrogorsk Research and Engineering Center on Nuclear Power Plants Safety, Electrogorsk, Moscow Region, Russia
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Ilya V. Elkin
Ilya V. Elkin
Russian Research Center “Kurchatov Institute”, Moscow, Russia
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Yuriy V. Parfenov
Electrogorsk Research and Engineering Center on Nuclear Power Plants Safety, Electrogorsk, Moscow Region, Russia
Oleg I. Melikhov
Electrogorsk Research and Engineering Center on Nuclear Power Plants Safety, Electrogorsk, Moscow Region, Russia
Vladimir I. Melikhov
Electrogorsk Research and Engineering Center on Nuclear Power Plants Safety, Electrogorsk, Moscow Region, Russia
Ilya V. Elkin
Russian Research Center “Kurchatov Institute”, Moscow, Russia
Paper No:
ICONE17-75276, pp. 265-267; 3 pages
Published Online:
February 25, 2010
Citation
Parfenov, YV, Melikhov, OI, Melikhov, VI, & Elkin, IV. "Thermal-Hydraulic Studies of the Steam Separation in Horizontal Steam Generator at PGV Test Facility." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 265-267. ASME. https://doi.org/10.1115/ICONE17-75276
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