TY - JOUR
T1 - Measurement of forced convection subcooled boiling flow and rod surface temperature distribution
AU - Ui, Atsushi
AU - Furuya, Masahiro
AU - Arai, Takahiro
AU - Shirakawa, Kenetsu
N1 - Funding Information:
This study was financially supported by the Agency for Natural Resources and Energy of the Ministry of Economy, Trade and Industry and conducted as part of the Infrastructure Development Project to Enhance Safety Measures at Nuclear Power Plants “Research and Development for Understanding Two-Phase Flow Behavior inside a Fuel Bundle.” The authors would like to thank to the Agency, Dr. Hiroki Takiguchi, Mr. Yoshiyuki Shiratori, Mr. Yuuki Miyazawa and Mr. Shinya Ueno of Denryoku Techno-Systems, Co. Ltd.
Publisher Copyright:
© 2021 The Author(s)
PY - 2021/9
Y1 - 2021/9
N2 - In order to obtain high-resolution data for modelling of boiling two-phase flow and its validation, we designed and constructed a test loop with a vertical annulus flow path and conducted subcooled boiling experiments to investigate subcooled bubble incipience and its development process under atmospheric condition. Three kinds of the state-of-the art measurement techniques were applied to quantify key parameters such as radial and vertical distributions of void fraction, bubble velocity, interfacial area concentration (IAC), Sauter mean diameters, high-resolution temperature distribution on rod surface, bubble transport behavior, and turbulent velocity components as well as onset of nucleate boiling (ONB), and onset of significant void (OSV).
AB - In order to obtain high-resolution data for modelling of boiling two-phase flow and its validation, we designed and constructed a test loop with a vertical annulus flow path and conducted subcooled boiling experiments to investigate subcooled bubble incipience and its development process under atmospheric condition. Three kinds of the state-of-the art measurement techniques were applied to quantify key parameters such as radial and vertical distributions of void fraction, bubble velocity, interfacial area concentration (IAC), Sauter mean diameters, high-resolution temperature distribution on rod surface, bubble transport behavior, and turbulent velocity components as well as onset of nucleate boiling (ONB), and onset of significant void (OSV).
KW - Bubble transport behavior
KW - Interfacial area concentration
KW - Temperature distribution
KW - Void fraction
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U2 - 10.1016/j.nucengdes.2021.111323
DO - 10.1016/j.nucengdes.2021.111323
M3 - Article
AN - SCOPUS:85108110378
SN - 0029-5493
VL - 381
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 111323
ER -