Zobrazeno 1 - 10 of 12 pro vyhledávání: '"Wade Karlsen"'
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Akademický článek
Baseline Examinations and Autoclave Tests of 65 and 100 dpa Flux Thimble Tube O-Ring Specimens
Autor: Wade Karlsen, Aki Toivonen, Pål Efsing
Publikováno v: Corrosion and Materials Degradation, Vol 2, Iss 2, Pp 248-273 (2021)
This paper describes the methods and results of analytical TEM examinations and autoclave testing of two highly-irradiated flux thimble tube materials harvested from a commercial pressurized water reactor. The materials are cold-worked 316L, and accu
Externí odkaz: https://doaj.org/article/84230a9070be4e8fb9d92ef3cfd4b828
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2
Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor
Autor: Mykola Ivanchenko, Ken Anderson, Wade Karlsen, Jesse J. Carter, Richard W. Smith
Publikováno v: Anderson, K R, Karlsen, W, Ivanchenko, M, Carter, J J & Smith, R W 2019, ' Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor ', Journal of Nuclear Materials, vol. 513, pp. 260-270 . https://doi.org/10.1016/j.jnucmat.2018.11.013
Post-irradiation examination (PIE) in the form of transmission electron microscopy (TEM) was used to characterize the microstructure of several specimens of Zircaloy-2 and Zircaloy-2 plus 1% Nb that had previously underwent in-pile creep testing in t
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f06581fe4cb4a6a8389ff05594a2585c
https://doi.org/10.1016/j.jnucmat.2018.11.013
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3
Miniature Autoclave and Double Bellows Loading Device for Material Testing in Future Reactor Concept Conditions—Case Supercritical Water
Autor: Aki Toivonen, Pekka Moilanen, Sami Penttilä, Wade Karlsen
Publikováno v: Penttilä, S, Moilanen, P, Karlsen, W & Toivonen, A 2018, ' Miniature Autoclave and Double Bellows Loading Device for Material Testing in Future Reactor Concept Conditions : Case Supercritical Water ', Journal of Nuclear Engineering and Radiation Science, vol. 4, no. 1, 021006 . https://doi.org/10.1115/1.4037897
The presented work consists of a test setup study of a new pneumatic material testing device based on double bellows (DBs) loading device and with miniature autoclaves enabling applications at temperature and pressure up to 650 °C and 35 MPa, respec
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::06d307e1a509b0a2fe6339c65985de1a
https://doi.org/10.1115/1.4037897
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4
Localized deformation as a key precursor to initiation of intergranular stress corrosion cracking of austenitic stainless steels employed in nuclear power plants
Autor: Gonzalo de Diego, Wade Karlsen, Bastian Devrient
Publikováno v: Karlsen, W, Diego, G & Devrient, B 2010, ' Localized deformation as a key precursor to initiation of intergranular stress corrosion cracking of austenitic stainless steels employed in nuclear power plants ', Journal of Nuclear Materials, vol. 406, no. 1, pp. 138-151 . https://doi.org/10.1016/j.jnucmat.2010.01.029
Cold-work has been associated with the occurrence of intergranular cracking of stainless steels employed in light water reactors. This study examined the deformation behavior of AISI 304, AISI 347 and a higher stacking fault energy model alloy subjec
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3820b18056227b7117ec7a9ca33b1d65
https://doi.org/10.1016/j.jnucmat.2010.01.029
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5
Microstructural manifestation of dynamic strain aging in AISI 316 stainless steel
Autor: Wade Karlsen, Mykola Ivanchenko, Hannu Hänninen, Yuriy Yagodzinskyy, Ulla Ehrnstén
Publikováno v: Karlsen, W, Ivanchenko, M, Ehrnstén, U, Yagodzinskyy, Y & Hänninen, H 2009, ' Microstructural manifestation of dynamic strain aging in AISI 316 stainless steel ', Journal of Nuclear Materials, vol. 395, no. 1-3, pp. 156-161 . https://doi.org/10.1016/j.jnucmat.2009.10.047
Dynamic strain aging (DSA) affects a material’s mechanical behaviour. In the current study, the deformation microstructures of AISI 316 stainless steel specimens were examined after tensile testing at several temperatures both in and out of the DSA
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::69d5864c915587a52a29cca236dadf60
https://doi.org/10.1016/j.jnucmat.2009.10.047
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7
Investigations on core basket bolts from a VVER 440 power plant
Autor: Heikki Keinänen, Ulla Ehrnstén, Wade Karlsen, Janne Pakarinen
Publikováno v: Ehrnstén, U, Pakarinen, J, Karlsen, W & Keinänen, H 2013, ' Investigations on core basket bolts from a VVER 440 power plant ', Engineering Failure Analysis, vol. 33, pp. 55-65 . https://doi.org/10.1016/j.engfailanal.2013.04.021
Non-destructive examinations using ultrasonic inspections were performed on core basket bolts at a VVER 440 unit. The four M12 bolts, manufactured from solution annealed Ti-stabilized stainless steel, had been replaced due to NDE indications. Destruc
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::96c807a25400c2016974e7ce882090ea
https://cris.vtt.fi/en/publications/fc7a08da-5578-4951-80a3-56d289254989
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8
Effect of Hot Cracks on EAC Crack initiation and Growth in Nickel-Base Alloy Weld Metals
Autor: Aki Toivonen, Tapio Saukkonen, Wade Karlsen, Anssi Brederholm, Hannu Hänninen, Ulla Ehrnstén, P. Aaltonen
Publikováno v: Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors ISBN: 9783319487601
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
The differences in the EAC susceptibility between different weld geometries and weld metals have been distinguished by the doped steam test method. Pure weld metals of Alloy 182 and 82 are clearly more susceptible to EAC than the pure weld metals of
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3d2f31f1757b4f6968438b24b56b899b
https://cris.vtt.fi/en/publications/4c38cea4-4a4d-4bc9-a8a1-a516814d5928
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9
Deformation microstructures of 30 dpa AISI 304 stainless steel after monotonic tensile and constant load autoclave testing
Autor: Ulla Ehrnstén, J. Pakarinen, Wade Karlsen, Aki Toivonen
Publikováno v: Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors ISBN: 9783319487601
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Irradiated AISI 304 stainless steel extracted from the Chooz A center filler assembly has been the subject of a number of studies. Previously the results of slow strain rate tensile and constant load autoclave tests of 30 dpa material have been repor
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4b3eeecd7fadbbf5d7123274b1a91ed6
https://doi.org/10.1002/9781118456835.ch149
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10
The effect of prior cold-work on the deformation behaviour of neutron irradiated AISI 304 austenitic stainless steel
Autor: Steven Van Dyck, Wade Karlsen
Publikováno v: Karlsen, W & Van Dyck, S 2010, ' The effect of prior cold-work on the deformation behaviour of neutron irradiated AISI 304 austenitic stainless steel ', Journal of Nuclear Materials, vol. 406, no. 1, pp. 127-137 . https://doi.org/10.1016/j.jnucmat.2010.01.028
Cold-work is intentionally employed to increase the yield strength of austenitic stainless steels and also occurs during fabrication processes, but it has also been associated with greater incidence of stress corrosion cracking. This study examined t
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a6c8b6e97e1c0ad6ff133fa49dc15ad8
https://cris.vtt.fi/en/publications/c4388bfc-6be8-4ec3-a4aa-20f954d33278
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