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