TY - CONF
T1 - Effects of period and flow rate on liquid entrainment and the droplet field under forced oscillatory reflood conditions
AU - Beck, Faith R.
AU - Jin, Yue
AU - Mohanta, Lokanath
AU - Qiao, Shouxu
AU - Rau, Adam
AU - Miller, Douglas J.
AU - Cheung, Fan Bill
AU - Lowery, Brian R.
AU - Bajorek, Stephen M.
AU - Tien, Kirk
AU - Hoxie, Chris L.
N1 - Funding Information:
The work performed at the Pennsylvania State University was supported by the U.S. Nuclear Regulatory Commission under Contract Number: NRC-HQ-60-16-T-0002. We would like to acknowledge Seungjin Kim who helped to collect and process the droplet data as well as Molly Eberly Hanson for her help with performing the experiments.
Publisher Copyright:
© 2016 Association for Computing Machinery Inc. All Rights Reserved.
PY - 2017
Y1 - 2017
N2 - In a hypothetical large break loss of coolant accident (LOCA), a break occurs on one of the cold legs and the emergency core cooling system (ECCS) must provide sufficient coolant to the core to remove decay heat and prevent the cladding from exceeding 1477.6 K, the temperature at which the thermal integrity of the cladding material is compromised. During reflood, flow to the core is gravity driven, resulting in an oscillatory delivery of coolant to the core. These oscillations are attributed to vapor generation in the core and the dynamic response of the downcomer water level. Most reflood experiments have been conducted with constant forced reflood rates, and have not considered the effect of oscillations on rod bundle thermal-hydraulics. The few studies conducted for oscillating flow indicate enhanced entrainment of liquid at the quench front. While higher entrainment can provide precursory cooling ahead of the quench front, it can also expel more coolant out of the system for oscillatory reflood. The amount of liquid entrained can be significant because in an accident scenario, the quench rate will be slowed and it can take longer to fully recover the core. At the NRC-PSU Rod Bundle Heat Transfer (RBHT) Test Facility, an electrically heated 7×7, 3.66 m rod bundle array has the capabilities to perform both constant and oscillatory forced flooding rate experiments. The heavily instrumented facility is equipped with seven spacer grids to analyze the droplet and heat transfer phenomena. In this study, reflood experiments have been performed in the RBHT test facility to investigate the separate effects of the oscillation frequency (4 to 20 seconds), magnitude (2.5 to 10.2 cm/s), and nominal flooding rates (2.5 to 5.1 cm/s) on the entrained droplet dynamics and heat transfer under constant and oscillatory flow conditions. The results have been compared and analyzed for the observed phenomena.
AB - In a hypothetical large break loss of coolant accident (LOCA), a break occurs on one of the cold legs and the emergency core cooling system (ECCS) must provide sufficient coolant to the core to remove decay heat and prevent the cladding from exceeding 1477.6 K, the temperature at which the thermal integrity of the cladding material is compromised. During reflood, flow to the core is gravity driven, resulting in an oscillatory delivery of coolant to the core. These oscillations are attributed to vapor generation in the core and the dynamic response of the downcomer water level. Most reflood experiments have been conducted with constant forced reflood rates, and have not considered the effect of oscillations on rod bundle thermal-hydraulics. The few studies conducted for oscillating flow indicate enhanced entrainment of liquid at the quench front. While higher entrainment can provide precursory cooling ahead of the quench front, it can also expel more coolant out of the system for oscillatory reflood. The amount of liquid entrained can be significant because in an accident scenario, the quench rate will be slowed and it can take longer to fully recover the core. At the NRC-PSU Rod Bundle Heat Transfer (RBHT) Test Facility, an electrically heated 7×7, 3.66 m rod bundle array has the capabilities to perform both constant and oscillatory forced flooding rate experiments. The heavily instrumented facility is equipped with seven spacer grids to analyze the droplet and heat transfer phenomena. In this study, reflood experiments have been performed in the RBHT test facility to investigate the separate effects of the oscillation frequency (4 to 20 seconds), magnitude (2.5 to 10.2 cm/s), and nominal flooding rates (2.5 to 5.1 cm/s) on the entrained droplet dynamics and heat transfer under constant and oscillatory flow conditions. The results have been compared and analyzed for the observed phenomena.
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M3 - Paper
AN - SCOPUS:85052386624
T2 - 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017
Y2 - 3 September 2017 through 8 September 2017
ER -