Zobrazeno 1 - 10
of 75
pro vyhledávání: '"V.I. Prokhorov"'
Autor:
A.E. Fedoseev, O. J. Weiß, Ermile Gaganidze, Jarir Aktaa, V.I. Prokhorov, A.V. Povstyanko, C. Dethloff, C. Petersen, E. Materna-Morris, O. Makarov
Publikováno v:
Journal of Nuclear Materials. 417:93-98
Mechanical properties of Reduced Activation Ferritic/Martensitic (RAFM) steels were studied after irradiation in BOR-60 reactor to a neutron displacement damage of 70 dpa at 330–340 °C. Yield stress and Ductile-to-Brittle-Transition-Temperature of
Publikováno v:
Journal of Nuclear Materials. 402:157-161
Hafnium control rods in the form of plates 6 mm thick were examined after a 9-year operation in the RBT-6 research reactor in water coolant at 68–86 °С to a maximal fluence 7.5 × 1025 m−2 (Е 0.8 MeV). The Hf crystalline lattice volume increas
Publikováno v:
Journal of Nuclear Materials. :299-302
In the irradiation project ‘Associated Reactor Irradiation in BOR 60’, named ‘ARBOR 1’, tensile and low cycle fatigue specimens of reduced activation ferritic/martensitic steels have been irradiated in a fast neutron flux (>0.1 MeV) of 1.8 10
Publikováno v:
Journal of Nuclear Materials. :277-280
Type 316L austenitic steels are widely used for the in-vessel internal structures of fission reactors (core, core support, etc.) and for experimental irradiation facilities. The modifications of 316L Type steel (316L, 316L(N), US 316, J 316, JPCA, et
Publikováno v:
Journal of Nuclear Materials. :544-549
In an energy generating fusion reactor, structural materials will be exposed to very high levels of irradiation damage of about 100 dpa. These damage conditions can be realized - in reasonable times - only in fast reactors. For this purpose a coopera
Autor:
G. Kalinin, B.S. Rodchenkov, Yu.S. Strebkov, O.Yu. Makarov, V.I. Prokhorov, V.K. Shamardin, O.A Golosov
Publikováno v:
Journal of Nuclear Materials. :1166-1170
The main options for the manufacturing of high heat flux (HHF) components is hot isostatic pressing (HIP) using either solid pieces or powder. There was no database on the radiation behaviour of these materials, and in particular stainless steel (SS)
Autor:
V.I. Prokhorov
Publikováno v:
Proceedings OCEANS.
Autor:
Ermile Gaganidze, C. Petersen, V.I. Prokhorov, A.V. Povstyanko, Jarir Aktaa, E. Diegele, R. Lässer
Publikováno v:
Nuclear Fusion. 51:083012
This paper focuses on the low cycle fatigue (LCF) behaviour of reduced activation ferritic/martensitic steels irradiated to a displacement damage dose of up to 70 dpa at 330–337 °C in the BOR 60 reactor within the ARBOR 2 irradiation programme. Th
Autor:
L. I. Sytov, V. M. Ilyasov, I.G. Lebedev, V.D. Balashov, Z. E. Ostrovskii, V. P. Vyskubov, S.N. Votinov, V. I. Kuz'min, O. D. Kazachkovskii, V.I. Prokhorov, V. N. Syuzev, L. M. Tuchnin
Publikováno v:
Soviet Atomic Energy. 24:164-171
Publikováno v:
Soviet Atomic Energy. 27:1299-1303