For steam generator with straight double-walled heat transfer tube that used in sodium cooled Faster Breeder Reactor, flow instability is one of the most important items need researching. As the first step of the research, thermal hydraulics experiments with water were performed under high pressure condition in JAEA with using a circular tube. Pressure drop, heat transfer coefficients and void fraction data were derived. This paper summarizes the pressure drop characteristics under 15MPa. Several two-phase flow multiplier models were checked and Chisholm model and homogeneous model were found being the best ones for the prediction of present data. A sudden pressure drop decreasing tendency was observed when flow pattern shifts from bubbly/churn flow to annular flow. The reason for this decrease is tried interpreted.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
Thermal-Hydraulic Experiments Under High Pressure Condition
Wei Liu,
Wei Liu
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Tamai Hidesada,
Tamai Hidesada
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Kazuyuki Takase,
Kazuyuki Takase
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Hiroki Hayafune,
Hiroki Hayafune
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Satoshi Futagami,
Satoshi Futagami
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Naoyuki Kisohara
Naoyuki Kisohara
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Wei Liu
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Tamai Hidesada
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Kazuyuki Takase
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Hiroki Hayafune
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Satoshi Futagami
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Naoyuki Kisohara
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Paper No:
ICONE18-30167, pp. 1101-1109; 9 pages
Published Online:
April 8, 2011
Citation
Liu, W, Hidesada, T, Takase, K, Hayafune, H, Futagami, S, & Kisohara, N. "Thermal-Hydraulic Experiments Under High Pressure Condition." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 1101-1109. ASME. https://doi.org/10.1115/ICONE18-30167
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