Zobrazeno 1 - 8
of 8
pro vyhledávání: '"L. I. Chyrko"'
Autor:
V. M. Revka, L. I. Chyrko
Publikováno v:
Âderna Fìzika ta Energetika, Vol 25, Iss 1, Pp 58-65 (2024)
The paper considers the generalized temperature dependence of the stress intensity factor KJC in the WWER-1000 reactor pressure vessel metal, which was derived based on the surveillance test data for fracture toughness. The consistency of the shape o
Externí odkaz:
https://doaj.org/article/ad60b45a377340299da35dab31778af8
Autor:
L. I. Chyrko, V. M. Revka, Yu. V. Chaikovskyi, M. G. Goliak, O. V. Trygubenko, O. V. Shkapyak
Publikováno v:
Âderna Fìzika ta Energetika, Vol 21, Iss 4, Pp 323-327 (2020)
The comparison of experimental values of the critical brittle temperature ΔTF and reference temperature ΔT0 of VVER-1000 reactor vessel weld metal with an elevated content of manganese and nickel is performed. ΔTF and ΔT0 values are defined proce
Externí odkaz:
https://doaj.org/article/3a403d6cdb4c46f3873ded4f9e79a8ad
Autor:
L. I. Chyrko, V. M. Revka, Yu. V. Chaikovskyi, M. G. Goliak, O. V. Trygubenko, O. V. Shkapyak
Publikováno v:
Âderna Fìzika ta Energetika, Vol 21, Iss 3, Pp 245-248 (2020)
The paper presents the statistical analysis of experimental results of radiation-induced critical brittle temperature ΔTF shifts and reference temperatures ΔT0 obtained respectively from the impact bend and fracture toughness tests of the reactor v
Externí odkaz:
https://doaj.org/article/a8cdb77eb8314289980708da004a9987
Autor:
Yu. S. Gulchuk, L. I. Chyrko
Publikováno v:
Âderna Fìzika ta Energetika, Vol 20, Iss 3, Pp 243-247 (2019)
The paper presents the procedure developed at the Department of Radiation Material Science of INR NAS of Ukraine for longitudinal radiometric scanning of surveillance specimens of the Ukrainian reactor vessels and its joint application with macrostru
Externí odkaz:
https://doaj.org/article/139f8f33534d443c8c6f84da44b01c6d
Autor:
M. G. Holiak, G. P. Grynchenko, V. M. Revka, O. V. Trygubenko, Yu. V. Chaykovskyi, L. I. Chyrko, O. V. Shkapyak
Publikováno v:
Âderna Fìzika ta Energetika, Vol 20, Iss 3, Pp 248-257 (2019)
The results of surveillance-specimens testing of re-irradiated after recovery annealing reactor pressure vessel (RPV) metal of Rivne NPP unit 1 are presented. The radiation strengthening and shift of critical temperature of brittleness for RPV base m
Externí odkaz:
https://doaj.org/article/c76777f962874b03b0ee1c45c0b410cb
Publikováno v:
Âderna Fìzika ta Energetika, Vol 14, Iss 1, Pp 38-41 (2013)
The surveillance test data for the nuclear power plant which is under operation in Ukraine have been used to estimate WWER-1000 reactor pressure vessel (RPV) material embrittlement. The beltline materials (base and weld metal) were characterized usin
Externí odkaz:
https://doaj.org/article/3b396e2222864f229f597021d36e8b74
Publikováno v:
Âderna Fìzika ta Energetika, Vol 8, Iss 1(19), Pp 83-88 (2007)
The lifetime of WWER-1000-type reactor vessels is finally conditioned by the fracture toughness (crack growth resistance) of RPV materials. Up to now in line with the regulations the fracture toughness is characterized by the critical temperature o
Externí odkaz:
https://doaj.org/article/741341d0cd094caebb4a825b55e8b7e4
Publikováno v:
Âderna Fìzika ta Energetika, Vol 12, Iss 3, Pp 272280-280 (2011)
On the basis of the “hot” cells of the Institute for Nuclear Research of National Academy of Sciences of Ukraine reconstitution technique of VVER reactor vessel metal surveillance specimens, and the main provisions of the reactor vessel radiati
Externí odkaz:
https://doaj.org/article/c0e3230e7a6d40cfb5dd0e85b727d4f0