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Your search keyword '"Alimov, V. Kh."' showing total 34 results
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34 results on '"Alimov, V. Kh."'

10. Deuterium retention in tungsten exposed to low-energy pure and helium-seeded deuterium plasmas.

Author

Ogorodnikova, O. V., Schwarz-Selinger, T., Sugiyama, K., and Alimov, V. Kh.

Subjects
HELIUM, DEUTERIUM, TUNGSTEN, PLASMA gases, CYCLOTRONS
Abstract

Influence of helium (He) on the deuterium (D) retention in tungsten (W) under simultaneous He-D plasma exposure was investigated. Bulk polycrystalline tungsten and two W coatings on carbon substrate, namely, plasma-sprayed tungsten and combined magnetron-sputtered and ion implanted tungsten (CMSII-W) were exposed to pure and He-seeded D plasmas generated by electron-cyclotron-resonance plasma source. The D retention in each sample was subsequently analyzed by various methods such as nuclear reaction analysis for the D depth profiling up to 6 μm and thermal desorption spectroscopy for the determination of total amount of D retention. It is shown that seeding of helium into D plasma with helium ion flux fraction of 10% reduces the deuterium retention for all tungsten grades but more significant reduction was observed for polycrystalline W and less significant effect was found for W coatings. From the thermal desorption spectroscopy measurements, we conclude that the presence of He modifies the density of existing traps for D but does not modify the nature of traps. Maximum effect of a reduction in the deuterium retention due to helium seeding was observed at around 500 K for bulk polycrystalline W. Mechanisms of deuterium retention and He effect in different W materials are discussed. [ABSTRACT FROM AUTHOR]

Published
2011
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11. Helium reemission, desorption and microstructure evolution of graphites under helium ion implantation.

Author

Alimov, V. Kh., Scherzer, B. M. U., Chernikov, V. N., and Ullmaier, H.

Subjects
*HELIUM, *ION implantation, *GRAPHITE, *CARBON, *THERMAL desorption
Abstract

Presents a study that measured helium reemission, desorption and microstructure evolution of graphites under helium ion implantation. Applications of carbon-based materials; Initial reemission rate achieved; Types of graphite; Analysis of helium thermal desorption.

Published
1995
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14. Tritium Retention in Reduced-Activation Ferritic/Martensitic Steels

Author

Hatano, Y., primary, Alimov, V. Kh., additional, Spitsyn, A. V., additional, Bobyr, N. P., additional, Cherkez, D. I., additional, Abe, S., additional, Ogorodnikova, O. V., additional, Klimov, N. S., additional, Khripunov, B. I., additional, Golubeva, A. V., additional, Chernov, V. M., additional, Oyaidzu, M., additional, Yamanishi, T., additional, and Matsuyama, M., additional

Published
2015
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23. Overview of results obtained at the Globus-M spherical tokamak

Author

Gusev, V.K., primary, Aleksandrov, S.E., additional, Alimov, V. Kh, additional, Arkhipov, I.I., additional, Ayushin, B.B., additional, Barsukov, A.G., additional, Ber, B. Ya, additional, Chernyshev, F.V., additional, Chugunov, I.N., additional, Dech, A.V., additional, Golant, V.E., additional, Gorodetsky, A.E., additional, Dyachenko, V.V., additional, Kochergin, M.M., additional, Kurskiev, G.S., additional, Khitrov, S.A., additional, Khromov, N.A., additional, Lebedev, V.M., additional, Leonov, V.M., additional, Litunovsky, N.V., additional, Mazul, I.V., additional, Minaev, V.B., additional, Mineev, A.B., additional, Mironov, M.I., additional, Miroshnikov, I.V., additional, Mukhin, E.E., additional, Nikolaev, Yu A., additional, Novokhatsky, A.N., additional, Panasenkov, A.A., additional, Patrov, M.I., additional, Petrov, M.P., additional, Petrov, Yu V., additional, Podushnikova, K.A., additional, Rozhansky, V.A., additional, Rozhdestvensky, V.V., additional, Sakharov, N.V., additional, Shcherbinin, O.N., additional, Senichenkov, I. Yu, additional, Shevelev, A.E., additional, Suhov, E.V., additional, Trapesnikova, I.N., additional, Terukov, E.I., additional, Tilinin, G.N., additional, Tolstyakov, S. Yu, additional, Varfolomeev, V.I., additional, Voronin, A.V., additional, Zakharov, A.P., additional, Zalavutdinov, R. Kh, additional, Yagnov, V.A., additional, Kuznetsov, E.A., additional, and Zhilin, E.G., additional

Published
2009
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30. Tritium Trapping on the Plasma Irradiated Tungsten Surface

Author

Torikai, Y., Alimov, V. Kh., Isobe, K., Oyaidzu, M., Yamanishi, T., Penzhorn, R.-D., Ueda, Y., Kurishita, H., Philipps, V., Kreter, A., and Zlobinski, M.

Abstract

AbstractTungsten (W) specimens previously exposed to deuterium (D) plasmas both in the TEXTOR tokamak and high flux linear plasma generator (LPG) were subsequently loaded with tritium at 573 K for 3 h. Retention of tritium in the near-surface W layer was examined by imaging plate technique. On the TEXTOR-plasma-exposed W surface, tritium was mainly trapped in carbon deposits. For LPG-plasma-exposed W specimens, tritium was trapped in defects created in the near-surface layer during the course of D plasma exposure.

Published
2015
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31. Deuterium trapping at defects created with neutron and ion irradiations in tungsten.

Author

Hatano, Y., Shimada, M., Otsuka, T., Oya, Y., Alimov, V. Kh., Hara, M., Shi, J., Kobayashi, M., Oda, T., Cao, G., Okuno, K., Tanaka, T., Sugiyama, K., Roth, J., Tyburska-Püschel, B., Dorner, J., Yoshida, N., Futagami, N., Watanabe, H., and Hatakeyama, M.

Subjects
DEUTERIUM, NEUTRONS, TUNGSTEN, HIGH temperatures, THERMAL stability, ACTIVATION energy, FUSION reactors
Abstract

The effects of neutron and ion irradiations on deuterium (D) retention in tungsten (W) were investigated. Specimens of pure W were irradiated with neutrons to 0.3 dpa at around 323K and then exposed to high-flux D plasma at 473 and 773 K. The concentration of D significantly increased by neutron irradiation and reached 0.8 at% at 473K and 0.4 at% at 773 K. Annealing tests for the specimens irradiated with 20MeV W ions showed that the defects which play a dominant role in the trapping at high temperature were stable at least up to 973 K, while the density decreased at temperatures equal to or above 1123 K. These observations of the thermal stability of traps and the activation energy for D detrapping examined in a previous study (≈1.8 eV) indicated that the defects which contribute predominantly to trapping at 773K were small voids. The higher concentration of trapped D at 473K was explained by additional contributions of weaker traps. The release of trapped D was clearly enhanced by the exposure to atomic hydrogen at 473 K, though higher temperatures are more effective for using this effect for tritium removal in fusion reactors. [ABSTRACT FROM AUTHOR]

Published
2013
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34. Temperature dependence of 4He/3He Exchange in Ni

Author

Alimov, V. Kh. and Scherzer, B. M. U.

Abstract

The release of 4He implanted to saturation with an energy of 15 keV in polycrystalline Ni by subsequent 3He implantation with equal energy has been measured between 295 and 1053 K. The fraction of 4He that can be exchanged is shown to decrease with increasing temperature up to T≲800 K. At T>800 K, however, it increases drastically. The results can be interpreted by assuming He trapping in two subsystems: gas bubbles and He-vacancy complexes. At sufficiently high density of the complexes He atoms can move along interlinked chains of complexes in "relay-race" type of motion in which each individual He-atom moves only one step and an atom from the complex nearest to the surface is released into the vacuum. At T > 900 K all complexes should be thermally dissociated. In this case bubble migration may be the mechanism responsible for He re-emission.

Published
1990
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