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Keyphrases
Thermal-hydraulics
100%
Versatile Test Reactor
100%
Keff
100%
Multiphysics Model
100%
MOOSE Framework
100%
Fuel Centerline Temperature
66%
Neutronic Calculations
66%
United States
33%
Advanced nuclear
33%
Modeling Approach
33%
Multiphysics
33%
Fuel Performance
33%
Physics-based Model
33%
Sodium Fast Reactor
33%
Temperature Profile
33%
Nuclear Materials
33%
Neutronics
33%
Reactor Physics
33%
Core Physics
33%
Multiphysics Simulation
33%
Sodium-cooled Fast Reactor
33%
Thermal Conductivity
33%
Fuel Performance Code
33%
Thermomechanical
33%
Bison
33%
Fuel Thermal Conductivity
33%
Simulation Environment
33%
Object-oriented Simulation
33%
Tight Coupling
33%
System Code
33%
Traditional Models
33%
Performance Calculation
33%
Fast Reactor Core
33%
Eigenvalues
33%
Quantifying Impact
33%
Griffin
33%
Conductivity Uncertainty
33%
Engineering
Test Reactor
100%
Neutronics
100%
Thermal Conductivity
66%
Centerline Plane
66%
United States
33%
Nuclear Material
33%
Reactor Core
33%
Sodium-Cooled Fast Reactor
33%
Boundary Condition
33%
Temperature Profile
33%
Code Performance
33%
Simulation Environment
33%
Figure of Merit
33%
Eigenvalue
33%
Sodium Fast Reactor
33%
Physics
Neutronics
100%
Physics
66%
Fast Reactor
66%
Thermal Conductivity
66%
Boundary Condition
33%
Reactor Physics
33%
Temperature Profile
33%