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Keyphrases
Reactivity-initiated Accident
100%
Bison
86%
Transient Reactor Test Facility
57%
In-pile
57%
Critical Heat Flux
54%
Thermal-hydraulics
40%
Rodlet
38%
Reactor Experiments
34%
Transient Test
33%
Fuel Performance Code
33%
Sensitivity Analysis
32%
Fuel Performance
30%
Coolant
29%
Light Water Reactor
27%
Thermal Conductivity Measurement
27%
RELAP5-3D
26%
Transient Boiling
26%
Energy Deposition
25%
Reactor
25%
Pulse Width
24%
Loss of Coolant Accident
24%
Transient Critical Heat Flux
22%
Heat Transfer
22%
Idaho National Laboratory
21%
Irradiation
21%
Static Environment
21%
Light Water Reactor Fuel
20%
Thermal Conductivity
20%
Thermal Properties
19%
Power Pulse
18%
Heater
18%
Water Capsule
18%
Pellet-cladding Interaction
18%
Accident Condition
18%
Sensitivity Study
17%
Fuel Rod
15%
Thermal-hydraulic Performance
15%
Design of Experiments
15%
Accident Tolerant Fuel
15%
Pool Boiling
14%
Irradiation Experiment
14%
Thermocouple
14%
High Burnup
14%
High Burnup Fuel
13%
Reactivity Insertion Accident
13%
Effective Thermal Conductivity
13%
Boiling Phenomena
13%
Departure from nucleate Boiling
13%
Guard
12%
Nuclear Fuel
12%
Engineering
Thermal Hydraulics
71%
Heat Flux
70%
Test Facility
67%
Light Water Reactors
48%
Rod
45%
Loss of Coolant Accidents
44%
Test Reactor
37%
Code Performance
37%
Pulse Duration
28%
Burnup
28%
Thermal Conductivity
28%
Thermocouple
22%
Conductivity Measurement
21%
Nuclear Fuel
18%
Test Apparatus
18%
Sensitivity Study
17%
Mechanical Interaction
16%
Fuel Rod
15%
Stainless Steel
15%
Nuclear Reactor
14%
Test Vehicle
13%
Centerline Plane
12%
Nucleate Boiling
12%
Measurement System
12%
Boiling Condition
12%
Design of Experiments
12%
Figure of Merit
10%
Outer Surface
10%
Fuel System
10%
Design Basis Accident
10%
Reactor Safety
10%
Probe Beam
10%
Concentrated Solar Power
10%
Temperature Response
10%
Parametric Study
10%
Fuel Assembly
10%
Room Temperature
10%
Commissioning Test
10%
Safety Engineering
9%
United States
9%
Effective Thermal Conductivity
9%
Control Rod
9%
Transients
8%
Fuel Pellet
7%
Boiling Water Reactor
7%
Safety Testing
6%
Reflectance
6%
Nuclear Material
6%
Volumetric Heat Capacity
6%
Experimental Design
6%
