INIS
aging
32%
air
11%
alloys
73%
applications
34%
assessments
30%
bwr type reactors
14%
capacity
11%
charges
12%
compacts
20%
comparative evaluations
31%
computational fluid dynamics
12%
constraints
19%
crack propagation
11%
cracks
48%
curves
76%
damage
13%
data
34%
design
20%
devices
15%
ductile-brittle transitions
14%
efficiency
14%
electrokinetics
12%
embrittlement
12%
environment
34%
exercise
12%
fatigue
54%
finland
14%
fluids
12%
fracture toughness
78%
fractures
46%
hybrids
12%
impact tests
13%
interfaces
13%
investigations
11%
iron nitrides
11%
irradiation
42%
laboratories
10%
levels
12%
loading
29%
matrices
10%
mechanical properties
28%
metals
75%
microstructure
36%
mixing
12%
modeling
21%
neural networks
31%
nuclear power plants
25%
operation
44%
optimization
11%
performance
30%
plasticity
10%
prediction
24%
pressure vessels
54%
reactors
62%
reinforced concrete
12%
roughness
10%
sampling
20%
sensitivity
17%
simulation
20%
solar air heaters
18%
solutions
17%
steels
36%
strains
14%
surfaces
12%
testing
40%
tools
17%
validation
20%
values
21%
welds
99%
zones
12%
Keyphrases
Alloy 52
45%
Artificial Neural Network Method
15%
Artificial Neural Network Model
12%
ATLAS+
12%
Beltline
13%
Boiling Water Reactor
15%
Brittle Fracture
19%
Compact Tension Specimen
16%
Computational Fluid Dynamics
13%
Crystal Plasticity
10%
CT Specimen
11%
Deep Neural Network
16%
Dissimilar Weld
57%
Ductile to Brittle Transition Region
10%
Environmental Fatigue
10%
Fatigue Management
13%
Finland
18%
FRACTESUS
18%
Fracture Initiation
17%
Fracture Properties
12%
Fracture Toughness
79%
Fusion Boundary
18%
High-Ni
15%
Impact Test
13%
Induced-charge Electroosmosis
12%
J-R Curve
18%
Lessons Learned
11%
Low Alloy Steel
10%
Low Cycle Fatigue
18%
Master Curve
40%
Material Studies
12%
Mechanical Behavior
12%
Mechanical Properties
18%
Micromixer
12%
Microstructure
19%
Narrow Gap
22%
Ni-based Alloy
18%
Non-Newtonian Fluid
12%
Nuclear Power Plant
17%
Penalty Factor
14%
Pipe Material
12%
Pressure Vessel Head
10%
Reactor
10%
Reactor Components
14%
Reactor Coolant
11%
Reactor Pressure Vessel
46%
Reference Temperature
42%
Robin
19%
SA508
14%
Solar Air Heater
18%
Stainless Steel
13%
Structural Integrity Assessment
15%
Tear Resistance
13%
Temperature Effect
10%
Term Operation
27%
Thermal Aging
27%
Thermo-hydraulic Performance
10%
Transferability
10%
Vessel Material
13%
Water Environment
11%
Weld Metal
16%
Engineering
Applicability
11%
Artificial Neural Network
22%
Artificial Neural Network Model
11%
Base Alloy
20%
Boiling Water Reactor
14%
Brittle Fracture
18%
Buttering
11%
Computational Fluid Dynamics
22%
Deep Neural Network
10%
Dissimilar Metal
51%
Embrittlement
13%
Experimental Result
13%
Experimental Work
12%
Fatigue Assessment
12%
Fatigue Behavior
12%
Fatigue Life
15%
Fracture Initiation
18%
Fracture Strength
81%
Fusion Boundary
11%
Hydraulics
10%
Impact Test
14%
Impact Toughness
15%
Induced Charge
12%
Low Cycle Fatigue
18%
Master Curve
40%
Narrow Gap
15%
Network Model
12%
Newtonian Fluid
12%
Nuclear Power Plant
32%
Pressurized Water Reactor
10%
R-Curves
17%
Reactor Pressure Vessel
59%
Reference Temperature
44%
Single Edge
15%
Solar Air Heater
18%
Stainless Steel
22%
Steel Structure
12%
Structural Integrity
25%
Study Materials
13%
Tensile Test
10%
Test Temperature
10%
Transients
14%
Welds
100%