Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: MSB of the CANDU SCWR at W=924  kg/s (70% of rated flow rate) and pex=25  MPa

Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: Temporal variation of axial wall temperature at W=924  kg/s (70% of rated flow rate), hin=1000  kJ/kg, Q=2226.5  MW (89% of rated power), and pex=25  MPa

Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: Constructional features of the CANDU SCWR. (a) Schematic diagram [24] and (b) schematic diagram of the pressure tube

Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: Pressure drop versus mass flow rate at various steady-state operating conditions. (a) hin=50  kJ/kg, (b) hin=500  kJ/kg, (c) hin=1500  kJ/kg, and (d) hypothetical operating condition

Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: Axial variation of various buoyancy parameters and pressure gradients at t=0  s. (a) T(z), (b) B*(z) and A*(z), (c) Bu*(z) and k*(z), (d) TR(z), and (e) pressure gradients

Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: Axial variation of various buoyancy parameters and pressure gradients at t=20.95  s. (a) T(z), (b) B*(z) and A*(z), (c) Bu*(z) and k*(z), (d) TR(z), and (e) pressure gradients

Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: Axial variation of various buoyancy parameters and pressure gradients at t=26.32  s. (a) T(z), (b) B*(z) and A*(z), (c) Bu*(z) and k*(z), (d) TR(z), and (e) pressure gradients

Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: Axial wall temperature at various operating conditions. (a) Tw determined by HTCM and (b) Tw determined by HTCS

Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: Safe and stable operating zone at W=924  kg/s (70% of rated flow rate) and pex=25  MPa

Date of download: 11/5/2017 Copyright © ASME. All rights reserved. From: Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor ASME J of Nuclear Rad Sci. 2015;1(4):041011-041011-8. doi:10.1115/1.4030199 Figure Legend: Temporal variation of axial wall temperature at W=924  kg/s (70% of rated flow rate), hin=1400  kJ/kg, Q=1918.6  MW (77% of rated power), and pex=25  MPa