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Wade Karlsen

20052019
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Engineering & Materials Science

Austenitic stainless steel
Stainless steel
Crack initiation
Autoclaves
Microstructure
Strain rate
Irradiation
Nuclear power plants
Grain boundaries
Welds
Stress corrosion cracking
Aging of materials
Materials testing
Nickel
Water
Bolts
Creep testing
Zirconium alloys
Bellows
Neutrons
Testing
Transmission electron microscopy
Power plants
Cracks
Hardening
Argon
Metals
Crack propagation
Neutron irradiation
Piles
Light water reactors
Temperature
Dissimilar metals
Durability
Nuclear fuels
Fatigue of materials
Martensite
Mechanical testing
Nondestructive examination
Neutron flux
Shear stress
Creep
Defects
Nitrogen
Crack tips
Yield stress

Physics & Astronomy

General

austenitic stainless steels
stainless steels
examination
transmission electron microscopy
crack initiation
autoclaves
reactors
Zircaloy 2 (trademark)
grain boundaries
precipitation hardening
zirconium alloys
bellows
Inconel (trademark)
baffles
microstructure
piles
slip
fluence
safety
hardening
radiation
strain hardening
defects
stacking fault energy

Engineering

stress corrosion cracking
irradiation
bolts
annealing
nuclear power plants
critical loading
neutron irradiation
shear stress

Physics

strain rate
neutrons
light water reactors
high flux isotope reactors
temperature

Chemistry and Materials

intergranular corrosion
water
nitrogen
creep strength

Chemical Compounds

Austenitic stainless steel
Stainless Steel
Stress corrosion cracking
Creep testing
Zirconium alloys
Bolts
Neutrons
Nuclear power plants
Transmission electron microscopy
Grain boundaries
Piles
Irradiation
Power plants
Aging of materials
Hardening
Microstructure
Nitrogen
Shear stress
Neutron irradiation