Two-phase Flow Characteristics in BWRs

Reliable prediction of two-phase flow characteristics is important for safety and economy improvements of BWR plants. We have been developing two-phase flow measurement tools and techniques for BWR thermal hydraulic conditions, such as a 3D time-averaged X-ray CT system, an ultrasonic liquid film se...

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Published inJAPANESE JOURNAL OF MULTIPHASE FLOW Vol. 28; no. 2; pp. 153 - 160
Main Authors KATONO, Kenichi, AOYAMA, Goro, NAGAYOSHI, Takuji, YASUDA, Kenichi, NISHIDA, Koji
Format Journal Article
LanguageEnglish
Published Osaka City THE JAPANESE SOCIETY FOR MULTIPHASE FLOW 01.01.2014
Japan Science and Technology Agency
Subjects
3D time-averaged X-ray CT system
Boiling water reactors
BWR thermal hydraulic condition
Economics
Flow characteristics
Reactors
Sensors
Simulation
Three dimensional
Two-phase flow
Ultrasonic liquid film sensor
Wire-mesh sensor
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Abstract Reliable prediction of two-phase flow characteristics is important for safety and economy improvements of BWR plants. We have been developing two-phase flow measurement tools and techniques for BWR thermal hydraulic conditions, such as a 3D time-averaged X-ray CT system, an ultrasonic liquid film sensor and a wire-mesh sensor. We applied the developed items in experiments using the multi-purpose steam-water test facility known as HUSTLE, which can simulate two-phase thermal-hydraulic conditions in a BWR reactor pressure vessel, and we constructed a detailed instrumentation database. We validated a 3D two-phase flow simulator using the database and developed the reactor internal two-phase flow analysis system.
AbstractList Reliable prediction of two-phase flow characteristics is important for safety and economy improvements of BWR plants. We have been developing two-phase flow measurement tools and techniques for BWR thermal hydraulic conditions, such as a 3D time-averaged X-ray CT system, an ultrasonic liquid film sensor and a wire-mesh sensor. We applied the developed items in experiments using the multi-purpose steam-water test facility known as HUSTLE, which can simulate two-phase thermal-hydraulic conditions in a BWR reactor pressure vessel, and we constructed a detailed instrumentation database. We validated a 3D two-phase flow simulator using the database and developed the reactor internal two-phase flow analysis system.
Author NAGAYOSHI, Takuji
AOYAMA, Goro
NISHIDA, Koji
KATONO, Kenichi
YASUDA, Kenichi
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Cites_doi 10.2172/6871478
10.1115/ICONE21-16814
10.1299/jsmeicone.2011.19._ICONE1944_11
10.1080/00223131.2013.871589
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References [10] Minato, A., Nagayoshi, T., Misawa, M., Suzuki, A., Ninokata, H. and Koshizuka. S., Numerical Simulation Method of Complex 3D Gas-Liquid Two-Phase Flow, Proc. of 5th Int. Conf. on Multiphase Flow (ICMF'04), CD-ROM, Paper No. 170 (2004).
[9] Prasser, H.-M., Beyer, M., Carl, H., Gregor, S., Lucas, D., Pietruske, H., Schutz, P. and Weiss, F.-P., Evolution of the Structure of a Gas-Liquid Two-Phase Flow in a Large Vertical Pipe, Nucl. Eng. Des., Vol. 237, 1848-1861 (2007).
[8] Taniguchi, D., Nagayoshi, T., Katono, K., Yasuda, K. and Soneda, H., Void Fraction in a Modeled Single Cell of a Partitioned Chimney under Thermal-Hydraulic Conditions of BWRs, Proc. of 20th Int. Conf. on Nuclear Engineering (ICONE20), CD-ROM, Paper No. ICONE20 POWER2012-55117 (2012).
[1] Hitachi-GE Nuclear Energy Press Release, Hitachi-GE Nuclear Energy Installed Multi-purpose Steam Source Test Facility for Competitiveness Reinforcement of Nuclear Power Business (in Japanese), (2009).
[11] Katono, K., Minato, A. and Takii, T., Three-Dimensional Compressible Two-Fluid Model and its Application, Proc. of 13th Int. Conf. on Nuclear Engineering (ICONE13), CD-ROM, Paper No. ICONE13-50685 (2005).
[5] Bergles, A. E., Roos, J. P. and Bourne, J. G., Investigation of Boiling Flow Regimes and Critical Heat Flux, Dynatech Corp, NYO-3304-13 (1968).
[2] Hashimoto, T., Tao, H., Wada, T., Yamaguchi, K. and Fujiwara, S., Completion of the Steam Compressor for Hitachi Utility Steam Test Leading Facility, Turbomachinery, Vol. 41, 65-71 (2013).
[3] Katono, K., Nukaga, J., Nagayoshi, T. and Yasuda, K., Measurement of Three-Dimensional Time-Averaged Void Fraction Distribution in Rod Bundle in Air-Water System by X-ray CT Technique, Proc. of 21st Int. Conf. on Nuclear Engineering (ICONE21), CD-ROM, Paper No. ICONE21-16814 (2013).
[7] Aoyama, G., Watahiki, N., Nagayoshi, T., Baba, A. and Ohtsuka, M., Liquid Film Thickness Measurement in Small Square Pipe using Ultrasonic Pulse-Echo method, Proc. of 19th Int. Conf. on Nuclear Engineering (ICONE19), CD-ROM, Paper No. ICONE19-44019 (2011).
[6] Aoyama, G., Nagayoshi, T. and Baba, A., Preliminary Test of an Ultrasonic Liquid Film Sensor for High-Temperature Steam-Water Two-Phase Flow Experiments, J. Nucl. Sci. Technol., Vol. 51(3), 350-358 (2014).
[4] Ishii, M., One-Dimensional Drift-Flux Model and Constitutive Equations for Relative Motion Between Phases in Various Two-Phase Flow Regimes, Argonne National Laboratory, ANL-77-47 (1977).
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Snippet Reliable prediction of two-phase flow characteristics is important for safety and economy improvements of BWR plants. We have been developing two-phase flow...
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SubjectTerms 3D time-averaged X-ray CT system
Boiling water reactors
BWR thermal hydraulic condition
Economics
Flow characteristics
Reactors
Sensors
Simulation
Three dimensional
Two-phase flow
Ultrasonic liquid film sensor
Wire-mesh sensor
Title Two-phase Flow Characteristics in BWRs
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