Zobrazeno 1 - 10
of 61
pro vyhledávání: '"Povstyanko, A."'
Publikováno v:
In Fusion Engineering and Design November 2017 124:1019-1023
Autor:
Gaganidze, E., Petersen, C., Materna-Morris, E., Dethloff, C., Weiß, O.J., Aktaa, J., Povstyanko, A., Fedoseev, A., Makarov, O., Prokhorov, V.
Publikováno v:
In Journal of Nuclear Materials 1 October 2011 417(1-3):93-98
Publikováno v:
In Journal of Nuclear Materials 2008 376(3):396-400
Publikováno v:
In Journal of Nuclear Materials 2007 367 Part A:544-549
Publikováno v:
Fusion Engineering and Design. 124:1019-1023
Former investigations clearly revealed that embrittlement and hardening of reduced-activation ferritic-martensitic (RAFM) steels after neutron irradiation can be reduced remarkably by post-irradiation annealing (PIA). This study demonstrates the repe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::226066cda40ef1f355034b0993528470
https://doi.org/10.1016/j.fusengdes.2017.04.066
https://doi.org/10.1016/j.fusengdes.2017.04.066
Autor:
Ioltukhovskiy, A.G, Leonteva-Smirnova, M.V, Solonin, M.I, Chernov, V.M, Golovanov, V.N, Shamardin, V.K, Bulanova, T.M, Povstyanko, A.V, Fedoseev, A.E
Publikováno v:
In Journal of Nuclear Materials 2002 307 Part 1:532-535
Autor:
Masaki Inoue, Satoshi Ohtsuka, Takeji Kaito, A.V. Povstyanko, Andrey Novoselov, A.E. Fedoseev, Yasuhide Yano, Kenya Tanaka
Publikováno v:
Journal of Nuclear Science and Technology. 50:387-399
In order to confirm the irradiation behavior of ODS steels and thus judge their applicability to fuel claddings, fuel pin irradiation tests using 9Cr and 12Cr-ODS claddings developed by JAEA were conducted to burn-up of 11.9 at% and neutron dose of 5
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::879b4eb6ee7b8df413abe203303da1ce
https://doi.org/10.1080/00223131.2013.773165
https://doi.org/10.1080/00223131.2013.773165
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f91631fb5e480ac96bd4fc85e9df3c6d
https://doi.org/10.1016/j.jnucmat.2010.12.047
https://doi.org/10.1016/j.jnucmat.2010.12.047
Development of structural steel for fuel elements and fuel assemblies of sodium-cooled fast reactors
Autor:
A. G. Ioltukhovskii, Yu. P. Budanov, I. A. Shkabura, N. M. Mitrofanova, A. V. Tselishchev, A. V. Kozlov, M. V. Leontieva-Smirnova, A. V. Povstyanko, L. M. Zabud’ko, V. S. Ageev, V. V. Mal’tsev
Publikováno v:
Atomic Energy. 108:274-280
The main results of development work and post-reactor studies of different structural materials for fuel-element cladding and hexahedral fuel-assembly jackets for sodium-cooled fast reactors are examined. Austenitic and ferritic-martensitic steels, i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5f931e9d7134e96edf3a63925c01c7b6
https://doi.org/10.1007/s10512-010-9289-9
https://doi.org/10.1007/s10512-010-9289-9
Publikováno v:
Journal of Nuclear Science and Technology. 46:529-533
(2009). Fuel Pin Irradiation Test at up to 5 at% Burnup in BOR-60 for Oxide-Dispersion-Strengthened Ferritic Steel Claddings. Journal of Nuclear Science and Technology: Vol. 46, No. 6, pp. 529-533.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::30b1e923b01f95d46cfa87a14bdf15ef
https://doi.org/10.1080/18811248.2007.9711558
https://doi.org/10.1080/18811248.2007.9711558