TY - GEN
T1 - High-energy x-ray ct measurement of void fraction distribution around part length rods in a rod bundle at high pressure and temperatures
AU - Arai, Takahiro
AU - Ui, Atsushi
AU - Furuya, Masahiro
AU - Okawa, Riichiro
AU - Iiyama, Tsugumasa
AU - Ueda, Shota
AU - Shirakawa, Kenetsu
AU - Kito, Kazuaki
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 Behaviour inside a Fuel Bundle." The authors would like to thank Takio Endo, Yoshiyuki Shiratori, Yuki Miyazawa, Shinya Ueno, and Takumi Yasuoka of Electric Power Engineering Systems Co., Ltd., for helping with these experiments.
Publisher Copyright:
© 2020 American Society of Mechanical Engineers (ASME). All rights reserved.
PY - 2020
Y1 - 2020
N2 - A boiling experiment was conducted to acquire a threedimensional void fraction distribution in a rod bundle with part length rods. The test section was a 5 × 5 heated rod bundle that partially simulated a BWR rod bundle, and three PLRs were arranged together in the corner. The heated length of the fulllength rod was 3.71 m, which is equal in length to an actual fuel rod in BWRs, whereas the heated length of the PLR was 1.85 m. The rod bundle exhibited an axially and radially uniform heat flux. Further, the local void fraction was quantified by normalizing the intensities in the CT images of the boiling twophase flow with those obtained under the liquid-phase and gasphase conditions. The cross-sectional void fraction distribution was acquired at six height levels. The experimental results exhibited the void distribution around PLRs with respect to a wide range of flow conditions, inlet temperatures, inlet flow rates, bundle thermal powers, and system pressures.
AB - A boiling experiment was conducted to acquire a threedimensional void fraction distribution in a rod bundle with part length rods. The test section was a 5 × 5 heated rod bundle that partially simulated a BWR rod bundle, and three PLRs were arranged together in the corner. The heated length of the fulllength rod was 3.71 m, which is equal in length to an actual fuel rod in BWRs, whereas the heated length of the PLR was 1.85 m. The rod bundle exhibited an axially and radially uniform heat flux. Further, the local void fraction was quantified by normalizing the intensities in the CT images of the boiling twophase flow with those obtained under the liquid-phase and gasphase conditions. The cross-sectional void fraction distribution was acquired at six height levels. The experimental results exhibited the void distribution around PLRs with respect to a wide range of flow conditions, inlet temperatures, inlet flow rates, bundle thermal powers, and system pressures.
KW - 5×5 rod bundle
KW - Boiling two-phase flow
KW - Linear accelerator-driven high-energy X-ray computed tomography
KW - Part length rod
KW - Void fraction distribution
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M3 - Conference contribution
AN - SCOPUS:85096039553
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Student Paper Competition; Thermal-Hydraulics; Verification and Validation
PB - American Society of Mechanical Engineers (ASME)
T2 - 2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
Y2 - 4 April 2020 through 5 April 2020
ER -