Keyphrases
Advanced nuclear Power Plant
10%
Boiling Correlation
31%
Boiling Heat Flux
10%
Boiling Model
15%
Boiling Test
10%
Cooling Behavior
10%
Cooling Conditions
21%
Core Melt
21%
Corium
21%
Critical Heat Flux
10%
Dispersed Flow Film Boiling
63%
Downward Facing Boiling
31%
Downward-facing
31%
Droplet Breakup
14%
Enhancement Factor
10%
Experimental Heat Transfer
15%
External Reactor Vessel Cooling
31%
Film Boiling
19%
Film Boiling Regime
78%
Flooding Rate
15%
Heat Flux
10%
Heat Transfer
53%
Heat Transfer Enhancement
14%
Heat Transfer Test
17%
Heater
13%
In-vessel
10%
In-vessel Retention
31%
Inlet Subcooling
15%
Inverted Annular Film Boiling
63%
Liquid Column
15%
Local Nusselt number
15%
Local Variation
10%
Long-term Cooling
10%
New Correlation
31%
Nucleate Boiling
31%
Nusselt number
28%
Reactor Pressure Vessel
31%
Reactor Vessel
10%
Reflood
30%
Reflood Transients
70%
Rod Bundle
74%
Scaling Analysis
10%
Severe Accident
10%
Spacer Grid
94%
Steady-state Data
10%
Steam Cooling
35%
Subcooling
15%
Thermal-hydraulic Analysis
31%
Thermal-hydraulics
63%
Viable Approach
10%
Engineering
Annular Film
63%
Boundary Layer
7%
Bundle Heat
68%
Convective
26%
Cooling Condition
15%
Cooling Data
6%
Cooling System
10%
Droplet Size
26%
Enhancement Factor
12%
Experimental Investigation
31%
Film Boiling Regime
94%
Heat Transfer Data
6%
Heat Transfer Enhancement
26%
Heat Transport
6%
Injection Rate
26%
Liquid Column
15%
Local Nusselt Number
18%
Loss of Coolant Accidents
21%
Mm Diameter
7%
Momentum Transport
6%
Nuclear Power Plant
7%
Nucleate Boiling
31%
Nusselt Number
29%
Outer Surface
7%
Reactor Core
10%
Reactor Pressure Vessel
23%
Reactor Vessel
31%
Reynolds' Number
12%
Rod
20%
Rod Bundle
100%
Severe Accident
7%
Square Array
15%
Steam Cooling
42%
Subchannel
6%
Test Facility
26%
Test Section
7%
Thermal Hydraulics
94%
Transients
57%
Void Fraction
7%
