Finned Fuel Element Two-Phase Flow Parameter Measurements Using Real-Time Neutron Radiography

Author:

LIM In-Cheol1,HARVEL Glenn2,CHANG Jen-Shih3

Affiliation:

1. On leave from KAERI

2. School of Energy Systems and Nuclear Science, University of Ontario Institute of Technology

3. McIARS and Department of Engineering Physics, McMaster University

Publisher

Japan Society of Mechanical Engineers

Reference27 articles.

1. (1) Mitsutake, T., Morooka, S., Suzuki, K., Tsunoyama, S., and Yoshimura, K., Void Fraction Estimation within Rod Bundles Based on Three-Fluid Model and Comparison with X-Ray CT Void Data, Nuclear Engineering and Design, V120,(1990), pp. 203-212.

2. (2) Hori, K., Kawanishi, K., Hamamura, H., Ochi, M., and Akai, M. A High Speed X-Ray Computed Tomography Scanner for Multipurpose Flow Visualization and Measurement, 4th International Topical Meeting on Nuclear Thermalhydraulics, Operations, and Safety, April 6-8, (1994), Taipei, Taiwan.

3. (3) Narabayashi, T., Tobimasu, T., Nagasaka, H., and Kagawa, T., Measurement of Transient Flow Pattern by High Speed Scanning X-ray Void Fraction Meter, Measurement Techniques in Gas-Liquid Flows, (1984) pp. 259-280, Springer-Verlag,

4. (4) Narabayashi, T., Ishiyama T., Miyano H., and Nei, H., Measurement of Void Distribution in High Pressure Steam-Water Two-Phase Flow using High Speed X-ray Scanner, Proceedings of First International Conference on Multiphase Flows, Vol. 1, Sept. 24-27, Tsukuba, Japan, (1991) pp. 241-246.

5. (5) A. H. Robinson and S. L. Wang, High Speed Motion Neutron Radiography of Two-phase Flow, Neutron Radiography, J. P. Barton and P. von der Hardt (eds.), (1983) pp. 653-659.

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