Experiments of counter-current two-phase flow of upward steam flow and condensing downward film flow in a pipe were performed. The experiments were intended to examine water accumulation in steam generator U-tubes during intermediate and small break loss-of-coolant accidents of a pressurized water reactor. The inner diameter and the length of a test flow channel used in the experiments were 18 mm and 4 m, respectively. Experiments were performed at higher steam velocity a little than the velocity that was expected just after scram as the first trial. There was no water drainage form the test pipe to the lower plenum. All condensed water was entrained by steam to flow out from the top of the test pipe to the upper plenum. The test pipe was filled with the water lump and the water film, then these were blown up upward and the inner wall of the test pipe became dry. Again the test pipe was filled with the water lump and the water film, then these were blown up upward and the inner wall of the test pipe became dry. This process was iterated at short intervals. The flow state in the test pipe is highly chaotic and agitated. Condensed water flows up and down at high frequencies. It is indicated that to examine the time averaged void fraction and the two-phase pressure drop of the counter-current flow are required.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4595-0
PROCEEDINGS PAPER
Experimental Study on Model Development for Liquid Accumulation in Steam Generator U-Tube (First Report) Condensing Counter-Current Flow in Single Vertical Pipe
Tatsuya Yamaji,
Tatsuya Yamaji
Shinshu University, Ueda, Nagano, Japan
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Kohei Yamazaki,
Kohei Yamazaki
Kogakuin University, Hachioji, Tokyo, Japan
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Yasuo Koizumi,
Yasuo Koizumi
Shinshu University, Ueda, Nagano, Japan
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Hiroyasu Ohtake,
Hiroyasu Ohtake
Kogakuin University, Hachioji, Tokyo, Japan
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Koji Hasegawa,
Koji Hasegawa
Kogakuin University, Hachioji, Tokyo, Japan
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Shota Araki,
Shota Araki
Shinshu University, Ueda, Nagano, Japan
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Akira Ohnuki,
Akira Ohnuki
Mitsubishi Heavy Industries, Ltd., Kobe, Hyogo, Japan
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Hiroaki Nishi
Hiroaki Nishi
The Kansai Electric Power Co., Inc., Mihama, Fukui, Japan
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Tatsuya Yamaji
Shinshu University, Ueda, Nagano, Japan
Kohei Yamazaki
Kogakuin University, Hachioji, Tokyo, Japan
Yasuo Koizumi
Shinshu University, Ueda, Nagano, Japan
Hiroyasu Ohtake
Kogakuin University, Hachioji, Tokyo, Japan
Koji Hasegawa
Kogakuin University, Hachioji, Tokyo, Japan
Shota Araki
Shinshu University, Ueda, Nagano, Japan
Akira Ohnuki
Mitsubishi Heavy Industries, Ltd., Kobe, Hyogo, Japan
Hiroaki Nishi
The Kansai Electric Power Co., Inc., Mihama, Fukui, Japan
Paper No:
ICONE22-30568, V005T17A043; 5 pages
Published Online:
November 17, 2014
Citation
Yamaji, T, Yamazaki, K, Koizumi, Y, Ohtake, H, Hasegawa, K, Araki, S, Ohnuki, A, & Nishi, H. "Experimental Study on Model Development for Liquid Accumulation in Steam Generator U-Tube (First Report) Condensing Counter-Current Flow in Single Vertical Pipe." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition. Prague, Czech Republic. July 7–11, 2014. V005T17A043. ASME. https://doi.org/10.1115/ICONE22-30568
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