Publications of O. V. Ogorodnikova
All genres
Journal Article (33)
21.
Journal Article
T138, 014053 (5pp) (2009)
Deuterium retention in different tungsten grades. Physica Scripta 22.
Journal Article
390-391, pp. 1 - 9 (2009)
Recent analysis of key plasma wall interactions issues for ITER. Journal of Nuclear Materials 23.
Journal Article
395 (1-3), pp. 150 - 155 (2009)
Deuterium retention in self-damaged tungsten. Journal of Nuclear Materials 24.
Journal Article
373 (1-3), pp. 254 - 258 (2008)
Pre-implantation and pre-annealing effects on deuterium retention in tungsten. Journal of Nuclear Materials 25.
Journal Article
103 (3), 034902 (10pp) (2008)
Ion-driven deuterium retention in tungsten. Journal of Applied Physics 26.
Journal Article
50 (10), 103001 (20pp) (2008)
Tritium inventory in ITER plasma-facing materials and tritium removal procedures. Plasma Physics and Controlled Fusion 27.
Journal Article
363-365, pp. 893 - 897 (2007)
Deuterium retention in rhenium-doped tungsten. Journal of Nuclear Materials 28.
Journal Article
74, pp. 751 - 755 (2005)
Development of an actively cooled periscope head suitable for divertor observation during quasi-continuous operation of the W7-X stellarator. Fusion Engineering and Design 29.
Journal Article
341, pp. 175 - 183 (2005)
Thermo-stress analysis of actively cooled diagnostic windows for quasi-continuous operation of the W7-X stellarator. Journal of Nuclear Materials 30.
Journal Article
75, pp. 4258 - 4260 (2004)
Development of cooled UV, visible and IR windows for quasicontinuous operation of the W7-X stellarator. Review of Scientific Instruments 31.
Journal Article
75, pp. 4258 - 4260 (2004)
Development of Cooled UV, Visible and IR Windows for Quasicontinuous Operation of the W7-X Stellarator. Review of Scientific Instruments 32.
Journal Article
313-316, pp. 469 - 477 (2003)
Deuterium retention in tungsten in dependence of the surface conditions. Journal of Nuclear Materials 33.
Journal Article
290-293, pp. 459 - 463 (2001)
Surface effects on plasma-driven tritium permeation through metals. Journal of Nuclear Materials Conference Paper (5)
34.
Conference Paper
340, pp. 27 - 33 (2014)
Electron microscopy observations of radiation damage in irradiated and annealed tungsten. 20th International Workshop on Inelastic Ion-Surface Collisions (IISC-20), Wirrina Cove, February 16, 2014 - February 21, 2014. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 35.
Conference Paper
451 (1-3), pp. 379 - 386 (2014)
Annealing of radiation-induced damage in tungsten under and after irradiation with 20 MeV self-ions. 16th International Conference on Fusion Reactor Materials (ICFRM-16), Beijing, October 20, 2013 - October 26, 2013. Journal of Nuclear Materials 36.
Conference Paper
455 (1-3), pp. 561 - 567 (2014)
Retention of deuterium in damaged low-activation steel Rusfer (EK-181) after gas and plasma exposure. 16th International Conference of Fusion Reactor Materials (ICFRM-16), Beijing, October 20, 2013 - October 26, 2013. Journal of Nuclear Materials 37.
Conference Paper
Deuterium Retention in EUROFER steel at gas and plasma exposure. In: Proceedings of the 21st International Conference on Ion-Surface Interactions (ISI-2013), pp. 473 - 475 (Eds. Zykova, E. Y.; Karaseov, P. A.; Titov, A. I.; Yurasova, V. E.). 21st International Conference on Ion-Surface Interactions (ISI-2013), Yaroslavl, August 22, 2013 - August 26, 2013. (2013)
38.
Conference Paper
Deuterium Retention in self damaged tungsten after atomic and plasma exposure. In: Proceedings of the 21st International Conference on Ion-Surface Interactions (ISI-2013), pp. 256 - 258 (Eds. Zykova, E. Y.; Karaseov, P. A.; Titov, A. I.; Yurasova, V. E.). 21st International Conference on Ion-Surface Interactions (ISI-2013), Yaroslavl, August 22, 2013 - August 26, 2013. (2013)
Talk (38)
39.
Talk
Electron microscopy observations of radiation damage in irradiated and annealed tungsten. 20th International Workshop on Inelastic Ion-Surface Collisions (IISC-20), Wirrina Cove (2015)
40.
Talk
Hydrogen Isotopes Retention in Low‐activated Structural Materials. 12th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-12), Toyama (submitted)