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Keyphrases
Advanced Test Reactor
100%
Validation Protocol
100%
Wire Measurement
100%
Experiment Validation
100%
Neutron Flux
60%
Fixed Source
40%
Eigenvalues
40%
Computational Model
30%
Burnup
30%
Flux Trapping
30%
Fissile Materials
30%
Irradiation
30%
Source Model
30%
Fast Neutron Flux
20%
Thermal Neutron Flux
20%
Power Density
20%
Fission Power
20%
Four-wire
20%
Fission
10%
Nuclear Fuel
10%
Computationally Efficient
10%
Statistical Uncertainty
10%
Nuclear Materials
10%
Reactor Core
10%
Neutron Transport Code
10%
Reactor Experiments
10%
Reactor Model
10%
Post-irradiation Examination
10%
Reactor Safety
10%
Cobalt
10%
Fast Neutrons
10%
Power Distribution
10%
Energy Range
10%
Evaluation Model
10%
Guide Tube
10%
Number of Experiments
10%
ATF1
10%
Trap Position
10%
Flux Measurement
10%
Aluminum Alloy Wire
10%
In-core Instrumentation
10%
Source Case
10%
Cycle Flux
10%
Localized Effect
10%
Nickel-aluminum Alloys
10%
Measurement Capability
10%
Calculated Model
10%
Two-wire
10%
I-positions
10%
Nickel Wire
10%
Number of Tests
10%
Instance Modeling
10%
Limited Measurements
10%
Vessel number
10%
Engineering
Test Reactor
100%
Neutron Flux
90%
Eigenvalue
40%
Burnup
30%
Fast Neutron
30%
Source Model
30%
Thermal Neutron
20%
Power Density
20%
Good Agreement
10%
Rod
10%
Nuclear Material
10%
Nuclear Fuel
10%
Nuclear Reactor
10%
Reactor Core
10%
Neutron Transport
10%
Power Distribution
10%
Reactor Safety
10%
Limited Number
10%
Localised Effect
10%
Range (Statistical)
10%
Model Type
10%