TY - GEN
T1 - Effects of system parameters on the two-phase flow and heat transfer behavior in a rod bundle
AU - Garrett, Grant R.
AU - Beck, Faith R.
AU - Jin, Yue
AU - Cheung, Fan Bill
AU - Bajorek, Stephen M.
AU - Tien, Kirk
AU - Hoxie, Chris
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.
Publisher Copyright:
© 2019 Begell House Inc. All rights reserved.
Copyright:
Copyright 2020 Elsevier B.V., All rights reserved.
PY - 2019
Y1 - 2019
N2 - An experimental and numerical study was performed to investigate the effects of system pressure, inlet coolant velocity, and inlet coolant subcooling on the two-phase flow and heat transfer behavior of a rod bundle under reflood transient conditions. Experimental results were obtained from the NRC/PSU Rod Bundle Heat Transfer (RBHT) test facility from various test cases covering a range of system conditions. The RBHT test facility, which contains 49 vertical, 3.66 m (12 ft) long test rods (four unheated corner rods and 45 heated rods) with Inconel 600 cladding in a 7x7 geometry, having the rod diameters, rod pitches and spacer grids comparable to those in commercial PWRs, was specifically designed to obtain fundamental flow and heat transfer data during reflood transients. The thermal-hydraulic code TRAC/RELAP Advanced Computational Engine (TRACE) was used in this study by performing simulations with the same geometry and operating conditions as the RBHT facility. Results of the TRACE simulations were compared to the experimental data obtained in the RBHT tests. It was found that the trends on the effects of various system parameters on the thermal-hydraulic behavior of the rod bundle (i.e., the two-phase flow and heat transfer behavior of the rod bundle during reflood transients) predicted by the TRACE model agree well with the RBHT data.
AB - An experimental and numerical study was performed to investigate the effects of system pressure, inlet coolant velocity, and inlet coolant subcooling on the two-phase flow and heat transfer behavior of a rod bundle under reflood transient conditions. Experimental results were obtained from the NRC/PSU Rod Bundle Heat Transfer (RBHT) test facility from various test cases covering a range of system conditions. The RBHT test facility, which contains 49 vertical, 3.66 m (12 ft) long test rods (four unheated corner rods and 45 heated rods) with Inconel 600 cladding in a 7x7 geometry, having the rod diameters, rod pitches and spacer grids comparable to those in commercial PWRs, was specifically designed to obtain fundamental flow and heat transfer data during reflood transients. The thermal-hydraulic code TRAC/RELAP Advanced Computational Engine (TRACE) was used in this study by performing simulations with the same geometry and operating conditions as the RBHT facility. Results of the TRACE simulations were compared to the experimental data obtained in the RBHT tests. It was found that the trends on the effects of various system parameters on the thermal-hydraulic behavior of the rod bundle (i.e., the two-phase flow and heat transfer behavior of the rod bundle during reflood transients) predicted by the TRACE model agree well with the RBHT data.
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U2 - 10.1615/TFEC2019.mph027609
DO - 10.1615/TFEC2019.mph027609
M3 - Conference contribution
AN - SCOPUS:85081559861
T3 - Proceedings of the Thermal and Fluids Engineering Summer Conference
SP - 1383
EP - 1396
BT - 4th Thermal and Fluids Engineering Conference, TFEC 2019
PB - Begell House Inc.
T2 - 4th Thermal and Fluids Engineering Conference, TFEC 2019
Y2 - 14 April 2019 through 17 April 2019
ER -
