No photo of Wade Karlsen

Wade Karlsen

20052019
If you made any changes in Pure these will be visible here soon.

Research Output 2005 2019

Filter
Article
2019

Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor

Anderson, K. R., Karlsen, W., Ivanchenko, M., Carter, J. J. & Smith, R. W., Jan 2019, In : Journal of Nuclear Materials. 513, p. 260-270 11 p.

Research output: Contribution to journalArticleScientificpeer-review

Zircaloy 2 (trademark)
Creep testing
zirconium alloys
Zirconium alloys
piles
2018
1 Citation (Scopus)
Open Access
bellows
Bellows
autoclaves
Materials testing
Autoclaves
2016

The VTT Centre for Nuclear Safety, up-grading Finnish nuclear safety research

Karlsen, W., 2016, In : ATS Ydintekniikka. 45, 3, p. 42-45

Research output: Contribution to journalArticleProfessional

2013
6 Citations (Scopus)

Investigations on core basket bolts from a VVER 440 power plant

Ehrnsten, U., Pakarinen, J., Karlsen, W. & Keinänen, H., 2013, In : Engineering Failure Analysis. 33, p. 55-65 11 p.

Research output: Contribution to journalArticleScientificpeer-review

Bolts
Power plants
Washers
Irradiation
Spot welding
2010
43 Citations (Scopus)

Localized deformation as a key precursor to initiation of intergranular stress corrosion cracking of austenitic stainless steels employed in nuclear power plants

Karlsen, W., Diego, G. & Devrient, B., 2010, In : Journal of Nuclear Materials. 406, 1, p. 138-151 14 p.

Research output: Contribution to journalArticleScientificpeer-review

intergranular corrosion
stress corrosion cracking
austenitic stainless steels
nuclear power plants
Stress corrosion cracking
25 Citations (Scopus)

TEM observations and finite element modelling of channel deformation in pre-irradiated austenitic stainless steels: Interactions with free surfaces and grain boundaries

Sauzay, M., Bavard, K. & Karlsen, W., 2010, In : Journal of Nuclear Materials. 406, 1, p. 152-165 14 p.

Research output: Contribution to journalArticleScientificpeer-review

austenitic stainless steels
Austenitic stainless steel
Grain boundaries
slip
critical loading
13 Citations (Scopus)

The effect of prior cold-work on the deformation behaviour of neutron irradiated AISI 304 austenitic stainless steel

Karlsen, W. & Van Dyck, S., 2010, In : Journal of Nuclear Materials. 406, 1, p. 127-137 11 p.

Research output: Contribution to journalArticleScientificpeer-review

austenitic stainless steels
Austenitic stainless steel
Neutrons
neutrons
Neutron irradiation
2009
47 Citations (Scopus)

Microstructural manifestation of dynamic strain aging in AISI 316 stainless steel

Karlsen, W., Ivanchenko, M., Ehrnstén, U., Yagodzinskyy, Y. & Hänninen, H., 2009, In : Journal of Nuclear Materials. 395, 1-3, p. 156-161 6 p.

Research output: Contribution to journalArticleScientificpeer-review

precipitation hardening
Stainless Steel
stainless steels
Stainless steel
Aging of materials
2006
8 Citations (Scopus)

Crack Initiation Mechanism in Non-ductile Cracking of Irradiated 304L Stainless Steels under BWR Water Environment

Onchi, T., Hohi, K., Navas, M. & Karlsen, W., 2006, In : Journal of Nuclear Science and Technology. 43, 8, p. 851-865 5 p.

Research output: Contribution to journalArticleScientificpeer-review

crack initiation
Crack initiation
stainless steels
fluence
Grain boundaries
1 Citation (Scopus)

Fine-particle erosion and its incidence in pulp-handling components of the paper industry

Karlsen, W., 2006, In : Tribologia. 25, 2, p. 18-31

Research output: Contribution to journalArticleScientific