Keyphrases
Neutron Energy
100%
240Pu
100%
Neutron-induced Fission
100%
Fission
66%
High Activity
66%
Neutron Cross Section
33%
Design Improvement
33%
Minor Actinides
33%
Flight Data
33%
Micromegas Detector
33%
Spent nuclear Fuel
33%
Flight Path
33%
Energy Region
33%
Fast Neutrons
33%
Waste Transmutation
33%
Microbulk Micromegas
33%
Time-of-flight Technique
33%
Other-correction
33%
Optimized Pulse Shape
33%
Prolonged Exposure
33%
Measuring Station
33%
Nuclear Energy
33%
High Heat Flux
33%
Thermal Reactor
33%
Monte Carlo Simulation
33%
Safety Margin
33%
Pulse Shape Analysis
33%
Design Optimization
33%
Advanced nuclear Systems
33%
Statistical Accuracy
33%
Intrinsic Activity
33%
Fast Reactor Fuel
33%
Fast Neutron Spectrum
33%
Nuclear Waste Management
33%
Algorithm Analysis
33%
Counting-loss Correction
33%
Engineering
Neutron Energy
100%
Cross Section
100%
Fast Neutron
66%
Induced Fission
66%
Time-of-Flight
66%
Nuclear Waste Management
33%
Fast Reactor
33%
Spent Nuclear Fuel
33%
Pulse Shape
33%
Flight Data
33%
Design Optimization
33%
Special Attention
33%
Safety Margin
33%
Minor Actinide
33%
Nuclear Energy
33%
Flight Path
33%
Energy Region
33%
Neutron Spectra
33%
Shape Analysis
33%
Thermal Reactor
33%
Physics
Fast Neutron
100%
Monte Carlo Method
50%
Flight Path
50%
Radioactive Waste
50%
Actinide
50%
Fast Reactor
50%
Nuclear Fuel
50%
Thermal Reactor
50%
Design Optimization
50%
Material Science
Radioactive Waste
100%
Actinide
100%
Nuclear Fuel
100%