Engineering
Transients
100%
Thermal Hydraulics
77%
Neutronics
68%
Computational Fluid Dynamics
46%
Fuel Assembly
34%
Molten Salt Reactor
34%
Pressurized Water Reactor
32%
Countercurrent Flow
27%
Experimental Investigation
26%
Porosity
26%
Energy Engineering
25%
Simulation Result
23%
Nuclear Power Plant
23%
Loss of Coolant Accidents
23%
High Temperature Gas Reactors
20%
Fast Reactor
20%
Analysis Code
20%
Hydrogen Production
19%
Multiscale
18%
Fits and Tolerances
18%
Reactor Dynamics
17%
Dilution
17%
Reactor Core
17%
Rod
17%
One Dimensional
16%
Fuel Rod
16%
Heat Flux
16%
Water Hammer
15%
Burnup
15%
Cross Section
15%
Volume of Fluid Method
15%
Pressure Difference
15%
Test Facility
15%
Two-Phase Flow
15%
Production System
14%
Aspect Ratio
14%
Physical Model
14%
Liquid Metal Cooled Reactor
13%
Internals
13%
Sulfur-Iodine Cycle
13%
Good Agreement
12%
Nuclear Energy
12%
Flow Condition
12%
Limitations
12%
Nuclear Reactor
12%
Systems Analysis
12%
Heat Transfer Coefficient
12%
Numerical Study
11%
Nodes
11%
Boundary Condition
11%
Keyphrases
Sensitivity Analysis
45%
Thermal-hydraulics
45%
Uncertainty Analysis
41%
Dual Fluid Reactor
35%
System Code
34%
Fuel Assembly
28%
Neutronics
28%
Pressurized Water Reactor
28%
Reactor
27%
Reactor Concept
27%
RETRAN-3D
25%
ParC
25%
Three-dimensional (3D)
25%
Countercurrent Flow Limitation
25%
SUBCHANFLOW
25%
Void Fraction
24%
Coupled Code System
23%
Bubble Rising
22%
Hot Leg
20%
ANSYS CFX
20%
Condensation
19%
Molten Salt Reactor
19%
DYN3D
18%
Numerical Investigation
18%
High-temperature Reactor
17%
Pipe Geometry
17%
Reactor Core
16%
SBLOCA
16%
Dynamic Code
16%
PWR Hot Leg
16%
Molten Salt
15%
Fuel Rod
15%
Burnup
15%
Large Diameter
15%
TRANSURANUS
15%
Reactor Dynamics
14%
Nuclear Power Plant
14%
DYNSUB
14%
Operating Conditions
14%
Fuel Salt
13%
Coolant
13%
Nuclear System
13%
Neutron Noise
13%
ATHLET
13%
Numerical Diffusion
12%
RELAP5
12%
High Burnup
12%
Physical Model
12%
Heat Transfer Coefficient
12%
TALL-3D
12%
