Zobrazeno 1 - 10
of 21
pro vyhledávání: '"D. A. Zhurko"'
Autor:
K. I. Medvedev, D. Yu. Erak, A. A. Chernobaeva, D. A. Zhurko, V. N. Kochkin, M. A. Skundin, S. A. Bubyakin, N. V. Pal, A. A. Reshetnikov
Publikováno v:
Inorganic Materials: Applied Research. 13:1727-1735
Autor:
D. Yu. Erak, A. A. Chernobaeva, K. I. Medvedev, D. A. Zhurko, V. N. Kochkin, M. A. Skundin, S. A. Bubyakin, N. V. Pal, A. A. Reshetnikov
Publikováno v:
Voprosy Materialovedeniya. :202-215
This work presents the results of a study of the mechanical characteristics and chemical composition of metal samples cut from a non-irradiated weld seam of a WWER-440 reactor vessel after 45 years of operation. The calculated distribution of the cri
Autor:
A. M. Kryukov, A. A. Chernobaeva, D. Yu. Erak, S. V. Rogozhkin, A. A. Nikitin, V. I. Lebedinsky, V. B. Papina, D. A. Zhurko
Publikováno v:
Physics of Atomic Nuclei. 84:1676-1690
Autor:
K. I. Medvedev, D. Yu. Erak, A. A. Chernobaeva, D. A. Zhurko, A. D. Erak, S. A. Bubyakin, A. P. Bandura
Publikováno v:
Inorganic Materials: Applied Research. 12:1695-1700
Autor:
S. A. Bubyakin, D. A. Zhurko, K. I. Medvedev, D. Yu. Erak, A. D. Erak, A. P. Bandura, A. A. Chernobaeva
Publikováno v:
Voprosy Materialovedeniya. :192-199
The paper presents the research results on determining the mechanical characteristics of the metal samples cut out from the nozzles and the cylindrical shell at the nozzles zone of the VVER-440 reactor vessel after 45 years of operation.
Autor:
D. Yu. Erak, Z.V. Bukina, Evgenia Kuleshova, S.V. Fedotova, G.M. Zhuchkov, D.A. Maltsev, A.S. Frolov, D. A. Zhurko, D. V. Safonov, E. V. Krikun, M.A. Saltykov, B. A. Gurovich
Publikováno v:
Journal of Nuclear Materials. 501:261-274
This study was carried out to evaluate the possibility of 1st generation VVER-440 reactors lifetime extension by recovery re-annealing with the respect to base metal (BM). Comprehensive studies of the structure and properties of BM templates (samples
Publikováno v:
Inorganic Materials: Applied Research. 8:927-935
Before 2002, SE(B) specimens were included in surveillance specimen sets for operating VVER-1000 reactors. The transition from SE(B) specimens to CT specimens in the fracture toughness tests is caused by the necessity to reduce the scatter and the co
Autor:
Z.V. Bukina, Evgenia Kuleshova, B. A. Gurovich, D.A. Maltsev, G.M. Zhuchkov, E. V. Krikun, D. A. Zhurko, A.S. Frolov
Publikováno v:
Journal of Nuclear Materials. 490:247-259
This work summarizes and analyzes our recent research results on the effect of irradiation temperature within the range of (50–400)°C on microstructure and properties of 15Kh2NMFAA class 1 steel (VVER-1000 reactor pressure vessel (RPV) base metal)
Autor:
K. I. Medvedev, V. N. Kostromin, D. Yu. Erak, O. V. Mikhin, A. A. Chernobaeva, M. A. Skundin, D. A. Zhurko
Publikováno v:
International Journal of Pressure Vessels and Piping. 145:23-28
A database has been developed to establish a correlation between standard and mini-Charpy specimens with the scope of tests of 38 sets of specimens. A methodical procedure has been suggested and implemented which permits a twofold reduction of the sc
Autor:
A. A. Chernobaeva, M. A. Skundin, D. Yu. Erak, B. A. Gurovich, D. A. Zhurko, Evgenia Kuleshova, D.A. Maltsev, Valentina Papina
Publikováno v:
Journal of Nuclear Materials. 465:540-549
Temperature and fast neutron flux simultaneously affect the material of welded joints of reactor pressure vessels under irradiation. Understanding thermal aging effects on the weld metal allows for an explanation of the mechanisms that govern an incr