Keyphrases
In-core
98%
Advanced Test Reactor
73%
Advanced Reactors
49%
Fuel Cycle
49%
Short Time Scale
36%
Fuel Burnup
32%
Fuel Element
29%
Reactor
28%
Irradiation
24%
U-10Mo
24%
Isothermal Flow
24%
3D Mapping
24%
Distributed Sensor Network
24%
Real-time 3D
24%
Griffin
24%
Optical Fiber
24%
Simulation Monitoring
24%
Forward Sensitivity Analysis
24%
Simulation Operation
24%
Element Design
24%
LEU Conversion
24%
Element Analysis
24%
3D Reconstruction
24%
Transient Simulation
24%
Requalification
24%
Life Cycle Assessment
24%
Reactor Dynamics
24%
Reactor Kinetics
24%
Simulation Optimization
24%
Performance Optimization
24%
Operating Conditions
24%
Behavioral Modeling
24%
Emulation
24%
Scaling Behavior
24%
TRIGA Reactor
24%
Transient Reactor Test Facility
24%
Transient Model
24%
Long Time Scale Dynamics
20%
Kinetic Behavior
20%
Point Kinetics Equations
20%
Sensitivity Analysis
19%
Nuclear Power System
16%
Burnup Equations
12%
Unique Capabilities
12%
Nuclear Reactor
12%
Nonlinear Equation Solvers
12%
Energy Deposition
12%
Kinetic Equation
12%
High Enrichment
9%
Neutron Source
9%
Engineering
Test Reactor
100%
Fuel Cycle
49%
Transients
49%
Kinetic Equation
36%
Burnup
36%
Fuel Element
29%
Energy Systems
24%
Nuclear Energy
24%
Discretization
24%
One Dimensional
24%
Isothermal Flow
24%
Reactor Dynamics
24%
Scale Dynamic
24%
Fiber Optics
24%
Physical Parameter
24%
Reactor Kinetics
24%
Test Facility
24%
Fast Neutron
24%
Neutron Spectra
24%
Thermal Neutron
24%
Control Cylinder
24%
Neutron Source
19%
Fluid Flow
12%
Step Size α
12%
Flow Equation
12%
Nuclear Reactor
12%
Small Modular Reactor
12%
Benchmark Problem
12%
Thermal Hydraulics
12%
Computational Cost
12%
Sensitivity Result
12%
System Behavior
12%
Flow Problem
12%
Relative Sensitivity
12%
Input Parameter
12%
Nuclear Safety Analysis
12%
Uncertainty Quantification
12%
Design Process
9%
Neutron Flux
9%
Department of Energy
6%