Keyphrases
Accident Analysis
100%
Axial Power Distribution
33%
Best Known Codes
33%
Cladding Temperature
33%
Comprehensive Comparison
33%
Conservation Equations
33%
Continuous Energy
33%
Coolant Temperature
66%
Critical Heat Flux
33%
Decay Heat
33%
Equation Model
33%
Finite Volume
33%
Fuel Channel
33%
Fuel Cladding
33%
Fuel Temperature
66%
Full Core
33%
Heat Flux Ratio
33%
Heat Generation Model
33%
Heat Model
33%
Highly Enriched Uranium
33%
Implicit numerical Scheme
33%
International Atomic Energy Agency
33%
Loss of Flow Accident
33%
Low-enriched Uranium
33%
Material Testing Reactor
33%
Monte Carlo
33%
Neutron Flux
33%
Neutron Kinetics
66%
Neutronics
33%
Nuclear Power Plant
33%
Plate-type Fuel Element
33%
Point Reactor Kinetics Equations
33%
Radial Power Distribution
33%
Reactivity Feedback
33%
Reactivity Insertion Accident
33%
Reactor Accident
100%
Reactor Core
33%
Reactor Physics
33%
Reactor Power
33%
Research Reactor
100%
Safety Analysis
33%
Safety Technology
33%
Serpent
33%
Spatial Distribution
33%
System Code
100%
System Dynamics
100%
Technological Competence
33%
Technological Maturity
33%
Temporal Distribution
33%
Thermal-hydraulic Code
33%
Thermal-hydraulics
33%
Three-dimensional (3D)
33%
Engineering
Additional Feature
50%
Conservation Equation
50%
Core Model
50%
Critical Heat Flux
50%
Energy Engineering
50%
Enriched Uranium
100%
Equation Model
50%
Fuel Channel
50%
Fuel Element
50%
Heat Generation
50%
Implicit Time
50%
Kinetic Equation
50%
Neutron Flux
50%
Neutronics
50%
Nuclear Energy
50%
Nuclear Power Plant
50%
Nuclear Reactor
100%
Numerical Scheme
50%
Past Decade
50%
Power Distribution
50%
Power Reactor
50%
Reactor Core
50%
Reactor Kinetics
50%
Reactor Plate
50%
Research Reactors
100%
Safety Analysis
50%
Spatial Distribution
50%
Thermal Hydraulics
100%