The method for predicting countercurrent flow limitation (CCFL) and its uncertainty in an actual pressurizer surge line of a pressurized water reactor (PWR) using 1/10-scale air–water experimental data, one-dimensional (1D) computations, and three-dimensional (3D) numerical simulations was proposed. As one step of the prediction method, 3D numerical simulations were carried out for countercurrent air–water flows in a 1/10-scale model of the pressurizer surge line to evaluate capability of the 3D simulation method and decide uncertainty of CCFL characteristics evaluated for the 1/10-scale model. The model consisted of a vertical pipe, a vertical elbow, and a slightly inclined pipe with elbows. In the actual 1/10-scale experiment, air supplied into the lower tank flowed upward to the upper tank and water supplied into the upper tank gravitationally flowed downward to the lower tank through the pressurizer surge line. In the 3D simulation, however, water was supplied from the wall surface of the vertical pipe to avoid effects of flooding at the upper end (the 3D simulation largely underestimated falling water flow rates at the upper end). Then, the flow pattern in the slightly inclined pipe was successfully reproduced, and the simulated CCFL values for the inclination angle of (slope of 1/100) agreed well with the experimental CCFL data. The uncertainty among air–water experiments, 1D computations, and 3D simulations for the 1/10-scale model was for the CCFL constant of . The effects of ( deg) on CCFL characteristics were simulated and discussed.
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e-mail: utanohara@inss.co.jp
e-mail: kusunoki.takayoshi@inss.co.jp
e-mail: d.lucas@hzdr.de
e-mail: tomiyama@mech.kobe-u.ac.jp
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July 2016
Research Papers
Prediction Method of Countercurrent Flow Limitation in a Pressurizer Surge Line and Its Evaluation for a 1/10-Scale Model
Michio Murase,
Michio Murase
1
Mem. ASME
e-mail: murase@inss.co.jp
Institute of Nuclear Safety System, Inc.
, 64 Sata, Mihama-cho, Mikata-gun
, Fukui 919-1205
, Japan
e-mail: murase@inss.co.jp
1Corresponding author.
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Yoichi Utanohara,
e-mail: utanohara@inss.co.jp
Yoichi Utanohara
Institute of Nuclear Safety System, Inc.
, 64 Sata, Mihama-cho, Mikata-gun
, Fukui 919-1205
, Japan
e-mail: utanohara@inss.co.jp
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Takayoshi Kusunoki,
e-mail: kusunoki.takayoshi@inss.co.jp
Takayoshi Kusunoki
Institute of Nuclear Safety System, Inc.
, 64 Sata, Mihama-cho, Mikata-gun
, Fukui 919-1205
, Japan
e-mail: kusunoki.takayoshi@inss.co.jp
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Dirk Lucas,
e-mail: d.lucas@hzdr.de
Dirk Lucas
Helmholtz-Zentrum Dresden-Rossendorf
, P.O. Box 510 119, Dresden 01314
, Germany
e-mail: d.lucas@hzdr.de
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Akio Tomiyama
e-mail: tomiyama@mech.kobe-u.ac.jp
Akio Tomiyama
Kobe University
, 1-1 Rokkodai, Nada-ku, Kobe-shi
, Hyogo 657-8501
, Japan
e-mail: tomiyama@mech.kobe-u.ac.jp
Search for other works by this author on:
Michio Murase
Mem. ASME
e-mail: murase@inss.co.jp
Institute of Nuclear Safety System, Inc.
, 64 Sata, Mihama-cho, Mikata-gun
, Fukui 919-1205
, Japan
e-mail: murase@inss.co.jp
Yoichi Utanohara
Institute of Nuclear Safety System, Inc.
, 64 Sata, Mihama-cho, Mikata-gun
, Fukui 919-1205
, Japan
e-mail: utanohara@inss.co.jp
Takayoshi Kusunoki
Institute of Nuclear Safety System, Inc.
, 64 Sata, Mihama-cho, Mikata-gun
, Fukui 919-1205
, Japan
e-mail: kusunoki.takayoshi@inss.co.jp
Dirk Lucas
Helmholtz-Zentrum Dresden-Rossendorf
, P.O. Box 510 119, Dresden 01314
, Germany
e-mail: d.lucas@hzdr.de
Akio Tomiyama
Kobe University
, 1-1 Rokkodai, Nada-ku, Kobe-shi
, Hyogo 657-8501
, Japan
e-mail: tomiyama@mech.kobe-u.ac.jp
1Corresponding author.
Manuscript received July 16, 2015; final manuscript received May 10, 2016; published online June 17, 2016. Editor: Igor Pioro.
ASME J of Nuclear Rad Sci. Jul 2016, 2(3): 031021 (9 pages)
Published Online: June 17, 2016
Article history
Received:
July 16, 2015
Revision Received:
May 10, 2016
Accepted:
May 10, 2016
Citation
Murase, M., Utanohara, Y., Kusunoki, T., Lucas, D., and Tomiyama, A. (June 17, 2016). "Prediction Method of Countercurrent Flow Limitation in a Pressurizer Surge Line and Its Evaluation for a 1/10-Scale Model." ASME. ASME J of Nuclear Rad Sci. July 2016; 2(3): 031021. https://doi.org/10.1115/1.4033629
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