A multi-elbow piping system is adopted for the Japan sodium-cooled fast reactor (JSFR) cold-legs. Flow-induced vibration (FIV) is considered to appear due to complex turbulent flow with very high Reynolds number in the piping. In this study, pressure measurement for a single elbow flow is conducted to elucidate pressure fluctuation characteristics originated from turbulent motion in the elbow, which lead potentially to the FIV. Two different scale models, 1/7- and 1/14-scale simulating the JSFR cold-leg piping, are tested experimentally to confirm whether a scale effect in pressure fluctuation characteristics exists. A distinguishing peak can be seen in each power spectrum density (PSD) profile of pressure fluctuation obtained in and downstream of the flow separation region for both scaled models. When nondimensionalized, the PSD profiles show good correspondence regardless of scale model and even of Reynolds number simulated in this study.

1.
Shimakawa
,
Y.
,
Kasai
,
S.
,
Konomura
,
M.
, and
Toda
,
M.
, 2002, “
An Innovative Concept of the Sodium-Cooled Reactor to Pursue High Economic Competitiveness
,”
Nucl. Technol.
0029-5450,
140
, pp.
1
17
.
2.
Kotake
,
S.
,
Sakamoto
,
Y.
,
Mihara
,
T.
,
Kubo
,
S.
,
Uto
,
N.
,
Kamishima
,
Y.
,
Aoto
,
K.
, and
Toda
,
M.
, 2010, “
Development of Advanced Loop-Type Fast Reactor in Japan
,”
Nucl. Technol.
0029-5450,
170
, pp.
133
147
.
3.
Nakamura
,
T.
,
Shiraishi
,
T.
,
Ishitani
,
Y.
,
Wakatabe
,
H.
,
Sago
,
H.
,
Fujii
,
T.
,
Yamaguchi
,
A.
, and
Konomura
,
M.
, 2005, “
Flow-Induced Vibration of a Large-Diameter Elbow Piping Based on Random Force Measurement Caused by Conveying Fluid (Visualization Test Results)
,”
Proceedings of the 2005 ASME Pressure Vessels and Piping Division Conference
, ASME, New York, Paper No. PVP2005-71277.
4.
Shiraishi
,
T.
,
Wakatabe
,
H.
,
Sago
,
H.
,
Konomura
,
M.
,
Yamaguchi
,
A.
, and
Fujii
,
T.
, 2006, “
Resistance and Fluctuating Pressures of a Large Elbow in High Reynolds Numbers
,”
ASME J. Fluids Eng.
0098-2202,
128
, pp.
1063
1073
.
5.
Hirota
,
K.
,
Ishitani
,
Y.
,
Nakamura
,
T.
,
Shiraishi
,
T.
,
Sago
,
H.
,
Yamano
,
H.
, and
Kotake
,
S.
, 2008, “
Flow-Induced Vibration of a Large-Diameter Elbow Piping in High Reynolds Number Range; Randam Force Measurement and Vibration Analysis
,”
Proceedings of the Ninth International Conference on Flow-Induced Vibrations (FIV2008)
, Paper No. 264.
6.
Shiraishi
,
T.
,
Wakatabe
,
H.
,
Sago
,
H.
, and
Yamano
,
H.
, 2009, “
Pressure Fluctuation Characteristics of the Short-Radius Elbow Pipe for FBR in the Postcritical Reynolds Regime
,”
J. Fluid Sci. Technol.
1880-5558,
4
(
2
), pp.
430
441
.
7.
Yamano
,
H.
,
Tanaka
,
M.
,
Kimura
,
N.
,
Ohshima
,
H.
,
Kamide
,
H.
, and
Wakatabe
,
O.
, 2009, “
Unsteady Hydraulic Characteristics in Large-Diameter Pipings With Elbow for JSFR (1) Current Status of Flow-Induced Vibration Evaluation Methodology Development for the JSFR Pipings
,”
Proceedings of the 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13)
, Paper No. N13P1186.
8.
Iwamoto
,
Y.
,
Yasuda
,
K.
,
Sogo
,
M.
,
Yamano
,
H.
, and
Kotake
,
S.
, 2008, “
Study on Flow-Induced-Vibration Evaluation of Large-Diameter Pipings in a Sodium-Cooled Fast Reactor (4) Experiments on the 1/10-Scale Hot Leg Test Facility in Reynolds Number of 50,000 and 320,000
,”
Proceedings of the Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6)
, Paper No. N6P1010.
9.
Yuki
,
K.
,
Hasegawa
,
S.
,
Sato
,
T.
,
Hashizume
,
H.
,
Aizawa
,
K.
, and
Yamano
,
H.
, 2009, “
Unsteady Hydraulic Characteristics in Large-Diameter Pipings With Elbow for JSFR (3) Flow Structure in a 3-Dimensionally Connected Dual Elbow Simulating Cold-Leg Piping in JSFR
,”
Proceedings of the 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13)
, Paper No. N13P1167.
10.
Aizawa
,
K.
,
Nakanishi
,
S.
,
Yamano
,
H.
,
Kotake
,
S.
,
Hayakawa
,
S.
,
Watanabe
,
O.
, and
Fujimata
,
K.
, 2008, “
Study on Flow-Induced-Vibration Evaluation of Large-Diameter Pipings in a Sodium-Cooled Fast Reactor (1) Sensitive Analysis of Turbulent Flow Models for Unsteady Short-Elbow Pipe Flow
,”
Proceedings of the Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6)
, Paper No. N6P1053.
11.
Eguchi
,
Y.
,
Murakami
,
T.
,
Ohshima
,
H.
,
Yamano
,
H.
, and
Kotake
,
S.
, 2008, “
Study on Flow-Induced-Vibration Evaluation of Large-Diameter Pipings in a Sodium-Cooled Fast Reactor (2) A Large-Eddy Simulation of Turbulent Flow in a Short-Elbow Pipe
,”
Proceedings of the Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6)
, Paper No. N6P1003.
12.
Hirota
,
K.
,
Ishitani
,
Y.
,
Nishida
,
K.
,
Sago
,
H.
,
Xu
,
Y.
,
Yamano
,
H.
,
Nakanishi
,
S.
, and
Kotake
,
S.
, 2008, “
Study on Flow-Induced-Vibration Evaluation of Large-Diameter Pipings in a Sodium-Cooled Fast Reactor (3) Random Vibration Analysis Method Based on Turbulence Energy Calculated by CFD
,”
Proceedings of the Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6)
, Paper No. N6P1033.
13.
Aizawa
,
K.
,
Yamano
,
H.
,
Kotake
,
S.
, and
Fujimata
,
K.
, 2008, “
Numerical Calculation of Fluid Flow Within a Large-Diameter Piping With a Short-Radius Elbow in JSFR
,”
Proceedings of the Seventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7)
, Paper No. 039.
14.
Kawamura
,
T.
,
Nakao
,
T.
, and
Takahashi
,
M.
, 2002, “
Reynolds Number Effect on Turbulence Downstream From Elbow Pipe
,”
Trans. Jpn. Soc. Mech. Eng., Ser. B
0387-5016,
68
, pp.
645
651
.
15.
Idelchik
,
I. E.
, 1986,
Handbook of Hydraulic Resistance
, 2nd ed.,
Hemisphere
,
Washington, DC
, Chap. 6.
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