Zobrazeno 1 - 10
of 18
pro vyhledávání: '"K.V. Tsay"'
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 10, Pp 3398-3405 (2021)
This study observed the effect of neutron irradiation and ageing on the microstructure, hardness, and corrosion resistance of SAV-1 (Al–Mg–Si) alloy. The investigated material was irradiated with neutrons to fluences of 1021–1026 n/m2 in the WW
Externí odkaz:
https://doaj.org/article/5555fc9c0554416391c9183c8af37d4b
Autor:
K.V. Tsay
Publikováno v:
Вестник. Серия физическая, Vol 33, Iss 2, Pp 80-86 (2010)
The microstructure changes in 12Cr18Ni10Ti austenitic steel – the material of a spent fuel assembly shroud of the BN-350 reactor – after a series of post-irradiation annealings in the range of 450-1050oC were studied using the transmission electr
Externí odkaz:
https://doaj.org/article/f5e8923e52984a6fa8fe154ea662005f
Autor:
K.V. Tsay
Publikováno v:
Вестник. Серия физическая, Vol 32, Iss 1, Pp 56-66 (2010)
The stages of plastic deformation for 12Cr18Ni10Ti austenitic steel non-irradiated and irradiated with neutrons up to fluences 1.4´1019, 1.3´1020n/cm2 were determined based on the analysis of “true” deformation curves of the hardening coefficie
Externí odkaz:
https://doaj.org/article/4ae1172b94d340399231555f3a456622
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 10, Pp 3398-3405 (2021)
This study observed the effect of neutron irradiation and ageing on the microstructure, hardness, and corrosion resistance of SAV-1 (Al–Mg–Si) alloy. The investigated material was irradiated with neutrons to fluences of 1021–1026 n/m2 in the WW
Publikováno v:
Prof. Short
Much of today's research in nuclear materials relies heavily on archived, historical specimens, as neutron irradiation facilities become ever more scarce. These materials are subject to many processes of stress- and irradiation-induced microstructura
Publikováno v:
Journal of Nuclear Materials. 467:899-910
A hexagonal shroud containing a standard in-core fueled subassembly from the BN-350 reactor was examined after reaching 59 dpa maximum, followed by long-term storage underwater. Specimens were derived from both mid-face and rib-corner positions. It w
Publikováno v:
Journal of Nuclear Materials. 439:148-158
Transmission electron microscopy and microhardness measurements were used to examine changes in microstructure and associated strengthening induced in austenitic stainless steel 12Cr18Ni9Ti irradiated to ∼0.001 and ∼5 dpa in the WWR-K reactor bef
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