1. Date of download: 12/23/2017
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From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Thermophysical properties of water within pseudocritical-point region

2. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
(a) Graphical representation of computational domain. (b) Graphical representation of the 2D mesh in the 3D space.

3. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Initial experimental, calculated, and simulated results for low-range mass and heat fluxes in the 4-m mesh

4. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Initial experimental, calculated, and simulated results for mid-range mass and heat fluxes in the 2- and 4-m meshes

5. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Control case for sensitivity analysis

6. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Pressure variation effect on bulk-fluid and wall-temperature distributions

7. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Specific heat trends with pressure variation

8. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Heat-flux variation effect on bulk-fluid temperature distributions

9. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Heat-flux variation effect on wall-temperature distributions

10. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Turbulent kinetic energy based on flow centerline for the RKE and SST models, 1–3 m

11. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Experimental, calculated, and CFD simulated results for NHT in 2-m computational domains

12. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Experimental, calculated, and simulated results for DHT in 2-m computational domains

13. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Turbulent kinetic energy based on flow centerline for the RKE and SST models, 1–3 m

14. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Uncertainty in wall temperatures for SST model

15. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Uncertainty in wall temperatures for Mokry et al. correlation [12]

16. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Uncertainty in HTCs for Mokry et al. correlation [12]

17. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Uncertainty in wall temperatures for RKE model

18. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Uncertainty in HTC values for RKE model

19. Date of download: 12/23/2017
Copyright © ASME. All rights reserved.
From: Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci. 2016;2(3): doi: /
Figure Legend:
Uncertainty in HTC values for SST model