Keyphrases
Reactor
100%
Deformation Behavior
100%
Creep-fatigue
100%
Cu-Cr-Zr Alloy
100%
Fatigue Deformation
100%
Mechanical Response
40%
Experimental Facility
40%
Fatigue Experiment
40%
Neutron Irradiation
40%
Number of Cycles
40%
Microstructure
20%
Irradiation
20%
Maximum Stress
20%
Stress Response
20%
Microstructural
20%
Temporal Evolution
20%
Material Behavior
20%
Stress Amplitude
20%
Neutron
20%
Cyclic Softening
20%
Strain Amplitude
20%
Belgium
20%
Microstructural Changes
20%
Cyclic Hardening
20%
Creep-fatigue Test
20%
Number of Cycles to Failure
20%
Reactor Experiments
20%
CuCrZr
20%
SEM Technique
20%
Fracture Surface Morphology
20%
Hysteresis Loop
20%
Fission Reactors
20%
Fatigue Cyclic Loading
20%
INIS
deformation
100%
alloys
100%
reactors
100%
creep
100%
fatigue
100%
microstructure
60%
irradiation
60%
doses
40%
amplitudes
40%
neutrons
40%
failures
20%
comparative evaluations
20%
surfaces
20%
morphology
20%
fission
20%
strains
20%
scanning electron microscopy
20%
loading
20%
hardening
20%
hysteresis
20%
fractures
20%
lifetime
20%
belgium
20%
neutron flux
20%
test reactors
20%
br-2 reactor
20%
Engineering
Final Report
100%
Deformation Behavior
100%
In-Reactor Creep
100%
Mechanical Response
66%
Creep
66%
Main Conclusion
33%
Maximum Stress
33%
Mols
33%
Strain Amplitude
33%
Limited Amount
33%
Test Reactor
33%
Fracture Surface
33%
Stress Amplitude
33%
Hysteresis Loop
33%
Mechanical Fatigue Test
33%
Illustrates
33%
Surface Morphology
33%
Nuclear Reactor
33%
Temporal Evolution
33%
Material Science
In-Reactor Creep
100%
Creep
66%
Neutron Irradiation
66%
Surface Morphology
33%
Scanning Electron Microscopy
33%