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G.P. Kobylyanskij
G.P. Kobylyanskij
Materials science
Zirconium alloy
Coolant
Microstructure
crack resistance
5
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2024
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Modelling the effects of nuclear transmutation in the study of the physical properties of zirconium alloys
2019
A. R. Belozerova
S. V. Belozerov
V. K. Shamardin
G.P. Kobylyanskij
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State of the WWER-type experimental fuel assemblies after reactor tests in regimes simulating loss of coolant accidents
1996
G.P. Kobylyanskij
V. M. Makhin
V. N. Shulimov
G. I. Maershina
A.V. Smirnov
G. D. Lyadov
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Crack resistance parameters of irradiated specimens of N-2.5 alloy channel tubes
1992
G.P. Kobylyanskij
V. I. Prokhorov
V. A. Krasnoselov
A. V. Golubenko
O. Yu. Makarov
M. E. Rodin
B.S. Rodchenkov
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Irradiation effect on crack resistance parameters of zirconium
1992
G.P. Kobylyanskij
V. K. Shamardin
V. I. Prokhorov
V. A. Krasnoselov
A. V. Golubenko
O. Yu. Makarov
V. M. Grigorev
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Technique and preliminary results for in-reactor investigation of corrosion and mechanical behaviour of zirconium alloys under non-isothermal conditions
1985
V.A. Gremyachkin
G. I. Maershina
G.P. Kobylyanskij
B.V. Samsonov
S. V. Seredkin
V. K. Shamardin
V. N. Shulimov
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