TY - GEN
T1 - A modified model for the net vapor generation point and its application on chf prediction in subcooled flow boiling
AU - Rafiq Akand, Md Abdur
AU - Kitahara, Kei
AU - Matsumoto, Tatsuya
AU - Liu, Wei
AU - Morita, Koji
N1 - Publisher Copyright:
© 2021 American Society of Mechanical Engineers (ASME). All rights reserved.
PY - 2021
Y1 - 2021
N2 - Critical heat flux (CHF) is one of the most significant thermal criteria for nuclear reactor design and safety in subcooled flow boiling. The accurate prediction capabilities of the characteristic size of departure bubbles are crucial for predicting the net vapor generation point (NVG) and CHF. An experimental research facility was designed to determine the bubble departure diameter and subcooling at the net vapor generation point, not only for vertical flow boiling but also in any orientation between vertical and downward-facing horizontal. An improved force-balanced model is proposed to calculate the bubble departure diameter at the net vapor generation point to predict CHF in vertical subcooled flow boiling. The force-balance equation was solved numerically through iteration to calculate the bubble departure diameter using a novel MATLAB script. The net vapor generation point was modified using the bubble departure diameter obtained from the proposed model. The model agrees well with the experimental data. Finally, the modified departure diameter and NVG were applied to the liquid sublayer dryout model to predict the CHF on upward subcooled flow boiling. It was found that the model predicts the experimental CHF data with an average relative error of 7.17%.
AB - Critical heat flux (CHF) is one of the most significant thermal criteria for nuclear reactor design and safety in subcooled flow boiling. The accurate prediction capabilities of the characteristic size of departure bubbles are crucial for predicting the net vapor generation point (NVG) and CHF. An experimental research facility was designed to determine the bubble departure diameter and subcooling at the net vapor generation point, not only for vertical flow boiling but also in any orientation between vertical and downward-facing horizontal. An improved force-balanced model is proposed to calculate the bubble departure diameter at the net vapor generation point to predict CHF in vertical subcooled flow boiling. The force-balance equation was solved numerically through iteration to calculate the bubble departure diameter using a novel MATLAB script. The net vapor generation point was modified using the bubble departure diameter obtained from the proposed model. The model agrees well with the experimental data. Finally, the modified departure diameter and NVG were applied to the liquid sublayer dryout model to predict the CHF on upward subcooled flow boiling. It was found that the model predicts the experimental CHF data with an average relative error of 7.17%.
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U2 - 10.1115/ICONE28-64022
DO - 10.1115/ICONE28-64022
M3 - Conference contribution
AN - SCOPUS:85117720875
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics
PB - American Society of Mechanical Engineers (ASME)
T2 - 2021 28th International Conference on Nuclear Engineering, ICONE 2021
Y2 - 4 August 2021 through 6 August 2021
ER -