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Wade Karlsen

20052019
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Research Output 2005 2019

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
Open Access
Nuclear fuels
Aging of materials
Spent fuels
Radioactive wastes
Waste disposal
1 Citation (Scopus)
Open Access
bellows
Bellows
autoclaves
Materials testing
Autoclaves
2017

Radiological laboratory commissioning (RADLAB)

Karlsen, W., 2017, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report. VTT Technical Research Centre of Finland, p. 362-387 (VTT Technology, Vol. 294).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access
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

2015

The new VTT hot cells

Karlsen, W. & Butze, F., 2015, HOTLAB 2015. 11 p. 020

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Open Access
Mechanical testing
Nuclear power plants
2014

Miniature autoclave and double bellows loading device for LWR and SCW m aterial testing at VTT: Calibration, testing and results

Moilanen, P., Penttilä, S. & Karlsen, W., 2014, Espoo: VTT Technical Research Centre of Finland. 27 p. (Lappeenranta University of Technology: Department of Information Technology. Research report, Vol. VTT-R-02142-14).

Research output: Book/ReportReport

TEM examination of the effect of post-irradiation annealing on 7.7 dpa AISI 304L stainless steel

Karlsen, W., Ivanchenko, M., Pakarinen, J. & Karlsen, T., 2014. 14 p.

Research output: Contribution to conferenceConference articleScientificpeer-review

stainless steels
examination
transmission electron microscopy
irradiation
annealing

TEM examination of the effect of post-irradiation annealing on 7.7 dpa AISI 304 stainless steel

Karlsen, W., Ivanchenko, M., Pakarinen, J. & Karlsen, T., 2014, Proceedings of Fontevraud 8. 11 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

stainless steels
examination
transmission electron microscopy
irradiation
annealing

The new VTT Centre for nuclear safety

Karlsen, W., 2014, HOTLAB 2014: List of presentation. 18 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

safety
basements
radioactive materials
radiochemistry
materials handling
2013

Environmental influence on cracking susceptibility and ageing of nuclear materials (ENVIS)

Ehrnsten, U., Pakarinen, J., Karlsen, W., Hänninen, H., Mouginot, R., Soinila, E., Ahonen, M., Autio, J-M., Aaltonen, P. & Saukkonen, T., 2013, SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Espoo: VTT Technical Research Centre of Finland, p. 268-282 (VTT Technology; No. 201).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

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

Microstructural Characterization of Irradiated Baffle Bolts Removed from a Finnish VVER and a French PWR

Pakarinen, J., Ehrnstén, U., Keinänen, H. & Karlsen, W., 2013, Proceeding of the 16th International Conference on Environmental Degradation of Materials in Nuclear power Systems : Water Reactors. Vol. 1-3. p. 994-1007

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

bolts
baffles
fluence
cracks
washers
2011
7 Citations (Scopus)

Deformation microstructures of 30 dpa AISI 304 stainless steel after monotonic tensile and constant load autoclave testing

Karlsen, W., Pakarinen, J., Toivonen, A. & Ehrnstén, U., 2011, 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Busby, J. T., Ilevbare, G. & Andresen, P. L. (eds.). Wiley, p. 1352-1366

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Autoclaves
Stainless steel
Microstructure
Argon
Strain rate
2 Citations (Scopus)

Effect of Hot Cracks on EAC Crack initiation and Growth in Nickel-Base Alloy Weld Metals

Hänninen, H., Toivonen, A., Brederholm, A., Saukkonen, T., Karlsen, W., Ehrnstén, U. & Aaltonen, P., 2011, Proceedings of the 15th international Conference on Environmental Degradation of Materials in Nuclear power Systems - Water reactors. Ilevbare, G., Busby, J. & Andersen, P. (eds.). Springer, p. 197-224 26 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Crack initiation
Crack propagation
Welds
Nickel
Cracks
2 Citations (Scopus)

Environment-assisted cracking and hot cracking susceptibility of nickel-base alloy weld metals

Hänninen, H., Brederholm, A., Saukkonen, T., Ivanchenko, M., Toivonen, A., Karlsen, W., Ehrnstén, U. & Aaltonen, P., 2011, Espoo: VTT Technical Research Centre of Finland. 157 p. (VTT Tiedotteita - Research Notes; No. 2582).

Research output: Book/ReportReport

Open Access
Welds
Nickel
Dissimilar metals
Metals
Nondestructive examination

Grain boundary segregation in a 24 dpa 304 stainless steel after post-irradiation annealing

Karlsen, W., 2011, Proceedings of the Enlarged Halden Programme Group Meeting 2011. Halden, Norway, 14 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Influence of Material, Environment and Strain Rate on Environmentally Assisted Cracking of Austenitic Nuclear Materials (DEFSPEED): Deformation localisation and EAC in inhomogeneous microstructures of austenitic stainless steels

Ehrnsten, U., Karlsen, W., Pakarinen, J., Saukkonen, T. & Hänninen, H., 2011, SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. Espoo: VTT Technical Research Centre of Finland, p. 453-463 (VTT Tiedotteita - Research Notes; No. 2571).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access
Austenitic stainless steel
Strain rate
Microstructure
Crack initiation
Creep

Influence of Material, Environment and Strain Rate on Environmentally Assisted Cracking of Austenitic Nuclear Materials (DEFSPEED): DEFSPEED summary report

Ehrnsten, U., Karlsen, W., Pakarinen, J., Ahonen, M., Kuivalainen, P., Ivanchenko, M., Saukkonen, T. & Hänninen, H., 2011, SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. VTT Technical Research Centre of Finland, p. 440-452 (VTT Tiedotteita - Research Notes; No. 2571).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access
stress corrosion cracking
strain rate
irradiation
international cooperation
Finland
2010

Determination of the time to failure curve as a function of stress for a highly irradiated AISI 304 stainless steel after constant load tests in simulated PWR water environment

Pokor, C., Massoud, J-P., Wintergerst, M., Toivonen, A., Ehrnstén, U. & Karlsen, W., 2010, Fontevraud 7: Contribution of Materials Investigation to Improve the Safety and Performance of LWRs, Avignon, France, 26-30.9.2010. 18 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Stainless steel
Water
Irradiation
Bolts
Lithium
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

Deformation localisation and EAC in inhomogenous microstructures of austenitic stainless steels

Ehrnsten, U., Saukkonen, T., Karlsen, W. & Hänninen, H., 2009, Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. American Nuclear Society ANS, Vol. 2. p. 910-919

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Fatigue endurance of critical equipment (FATE): FATE summary report

Solin, J., Alhainen, J. & Karlsen, W., 2009, SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . Espoo: VTT Technical Research Centre of Finland, p. 339-353 (VTT Tiedotteita - Research Notes; No. 2466).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access
Durability
Fatigue of materials
Stainless steel
Martensite
Hardening

Manifestations of DSA in austenitic stainless steels and inconel alloys (1-2013)

Ivanchenko, M., Yagodzinskyy, Y., Ehrnsten, U., Karlsen, W. & Hänninen, H., 2009, 20th International Conference on Structural Mechanics in Reactor Technology, SMiRT 20: Book of abstracts. Vuori, S. & Rintamaa, R. (eds.). VTT Technical Research Centre of Finland, Vol. 1. p. 57-59 (VTT Symposium; No. 256).

Research output: Chapter in Book/Report/Conference proceedingConference abstract in proceedingsScientific

Open Access
Inconel (trademark)
austenitic stainless steels
interstitials
nitrogen
creep strength
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

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

Karlsen, W. & Van Dyck, S., 2009, Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems. American Nuclear Society ANS, Vol. 2. p. 1371-1384

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

2007
4 Citations (Scopus)

Observations of channel deformation in mildly-deformed, low-dose 304L austenitic stainless steel

Karlsen, W., Dohi, K. & Onchi, T., 2007, Proceedings: 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, 2007. Vol. 1. p. 411-422

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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

2005

Description of the mechanical behavior of irradiated stainless steel

Karlsen, W., Aaltonen, P. & Nenonen, P., 2005, Espoo: VTT Technical Research Centre of Finland. (VTT Research Report; No. BTUO73-051379).

Research output: Book/ReportReport