TY - GEN
T1 - Investigation of the flow near the wall of a single impinging jet at the scaled upper plenum of HTGR using TR-PIV
AU - Alwafi, Anas
AU - Hassan, Yassin
AU - Nguyen, Thien
AU - Anand, N. K.
N1 - Publisher Copyright:
Copyright © 2019 by JSME
PY - 2019/5/18
Y1 - 2019/5/18
N2 - One of the competitive candidate of the future nuclear reactors is the High Temperature Gas-cooled Reactor (HTGR). A 1/16th scaled upper plenum of a HTGR was designed at Texas A&M University to study the flow behaviors in the upper plenum of the HTGR during a Loss-Of-Forced-Coolant Accident (LOFC). Experimental investigation was conducted to study the flow characteristics of a single isothermal jet discharging into the upper plenum by using time-resolved particle image velocimetry (TR-PIV) technique. Experimental results can be used for validating computational fluid dynamics (CFD) codes. In this paper, the velocity measurements performed close to the upper plenum top-wall at the Reynolds number of 10,622 will be present. From the TR-PIV velocity snapshots, statistical characteristics of the jet impingement, such as the mean velocity, root-mean-square fluctuating velocity, and Reynolds stress, were computed and analyzed. In addition, results of two-point spatial velocity cross-correlation and spectral analysis will be discussed.
AB - One of the competitive candidate of the future nuclear reactors is the High Temperature Gas-cooled Reactor (HTGR). A 1/16th scaled upper plenum of a HTGR was designed at Texas A&M University to study the flow behaviors in the upper plenum of the HTGR during a Loss-Of-Forced-Coolant Accident (LOFC). Experimental investigation was conducted to study the flow characteristics of a single isothermal jet discharging into the upper plenum by using time-resolved particle image velocimetry (TR-PIV) technique. Experimental results can be used for validating computational fluid dynamics (CFD) codes. In this paper, the velocity measurements performed close to the upper plenum top-wall at the Reynolds number of 10,622 will be present. From the TR-PIV velocity snapshots, statistical characteristics of the jet impingement, such as the mean velocity, root-mean-square fluctuating velocity, and Reynolds stress, were computed and analyzed. In addition, results of two-point spatial velocity cross-correlation and spectral analysis will be discussed.
KW - High Temperature Gas-cooled Reactor (HTGR)
KW - Isothermal Impinging Jet
KW - Time-resolved Particle Image Velocimetry (TR-PIV)
KW - Two-point Cross-Correlation
KW - Upper plenum
UR - https://www.scopus.com/pages/publications/85071383019
M3 - Conference contribution
AN - SCOPUS:85071383019
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Proceedings of the 27th International Conference on Nuclear Engineering, ICONE 2019 - "Nuclear Power Saves the World!"
PB - American Society of Mechanical Engineers (ASME)
T2 - 27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
Y2 - 19 May 2019 through 24 May 2019
ER -