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Início Arquivos Representantes Futuras reuniões American Society of Thermal and Fluids Engineering

EFFECTS OF SYSTEM PARAMETERS ON THE TWO-PHASE FLOW AND HEAT TRANSFER BEHAVIOR IN A ROD BUNDLE

Grant Garrett
Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, State College, PA, 16802

Faith R. Beck
Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, State College, PA, 16802

Yue Jin
Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, State College, PA, 16802

Fan Bill Cheung
Department of Mechanical & Nuclear Engineering, Pennsylvania State University, State College, PA, 16802

Stephen M. Bajorek
Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission, Rockville, MD, 20852

Kirk Tien
Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission, Rockville, MD, 20852

Chris Hoxie
Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission, Rockville, MD, 20852

DOI: 10.1615/TFEC2019.mph.027609
pages 1383-1396


Palavras-chave: Two-Phase Flow, Rod Bundle Thermal Hydraulics, TRACE Validation, PWR, LOCA, Reflood

Resumo

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 7×7 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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