Zobrazeno 1 - 10
of 42
pro vyhledávání: '"N. Shatil"'
Autor:
V. Vasiliev, D. Stepanov, V. M. Amoskov, M. S. Larionov, S. E. Sytchevsky, A. Ustinov, A. Bursikov, Yu. Ilyin, V. P. Kukhtin, A. A. Mednikov, E. A. Lamzin, V. Vadatursky, V. A. Belyakov, A. A. Firsov, A. Nezhentzev, N. Shatil, B. S. Lim, Igor Rodin, M. Burkanov
Publikováno v:
Fusion Engineering and Design. 130:94-103
A measurement-based numerical reconstruction technique is proposed to control winding geometry of the poloidal coils manufactured for ITER. A detailed coil model is parameterized in terms of the magnetic characteristics. Deviations from the specified
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::18145ceb551f2828b918ab0944ae15fd
https://doi.org/10.1016/j.fusengdes.2018.02.076
https://doi.org/10.1016/j.fusengdes.2018.02.076
Akademický článek
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Autor:
D. Arslanova, Luigi Serio, V. A. Belyakov, S. E. Sytchevsky, A. Alekseev, N. Shatil, M. Kaparkova, Ilya Gornikel, V. Kalinin, Denis Bessette, V. Vasiliev, Neil Mitchell
Publikováno v:
Fusion Engineering and Design. 121:1-6
Active mitigation of pulsed heat load is foreseen for the ITER superconducting magnets during cyclic plasma scenarios to ensure stable operation of the cryoplant. The paper addresses a promising feedback control to smooth heat pulses in the primary c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c6a628a9a23fe5aec57f99fd5c3b884d
https://doi.org/10.1016/j.fusengdes.2017.05.092
https://doi.org/10.1016/j.fusengdes.2017.05.092
Autor:
Denis Bessette, N. Shatil, M. Kaparkova, D. Arslanova, S. Sychevsky, V. A. Belyakov, V. Vasiliev, V. Kalinin, I.V. Gornikel
Publikováno v:
Fusion Engineering and Design. 88:1486-1490
Normal operation of the ITER TF coils at 15 MA reference scenario is simulated with the use of the VENECIA code. The developed numerical model adopts a full scale quasi 3D approach for thermal hydraulic and thermal diffusion analysis of TF coils at t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::988ee50ee824bc8065ff71bf70790d50
https://doi.org/10.1016/j.fusengdes.2013.02.047
https://doi.org/10.1016/j.fusengdes.2013.02.047
Autor:
Y. Takahashi, Koji Yoshida, Denis Bessette, Neil Mitchell, N. Shatil, Yoshihiro Nabara, M. Edaya
Publikováno v:
IEEE Transactions on Applied Superconductivity. 17:2426-2429
Stability and quench analyses of the ITER TF coils are performed with a combination of three computer codes to obtain an accurate prediction. A one-dimensional code ldquoGandalfrdquo with an adaptive mesh is used mainly for these analyses. The overal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34af3cec7c3331b3d0b9ef4a1e921c7a
https://doi.org/10.1109/tasc.2007.899878
https://doi.org/10.1109/tasc.2007.899878
Publikováno v:
Fusion Engineering and Design. 81:2589-2595
The main ITER cryogenic users are the superconducting magnets together with the 80 K thermal shields. The key requirements that drive the design of the ITER cryogenic system are the intrinsically pulsed heat deposition in the magnets due to electroma
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4bc2c22b4d4c6a8e6ca5159be51d65bf
https://doi.org/10.1016/j.fusengdes.2006.07.003
https://doi.org/10.1016/j.fusengdes.2006.07.003
Publikováno v:
IEEE Transactions on Applied Superconductivity. 16:795-798
Time-dependent thermal-hydraulic analyses of the ITER Toroidal Field (TF) Coils have been performed with a quasi-3D model based on the VINCENTA code. Two primary cooling loops are considered for the case and the winding pack respectively, each of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6fd808e3e5b64656bfa355eb56c791dd
https://doi.org/10.1109/tasc.2006.873258
https://doi.org/10.1109/tasc.2006.873258
Autor:
A. Belov, N. Shatil, O. Filatov, V. Kukhtin, S. E. Sytchevsky, V. Kalinin, V. A. Belyakov, O. Ilyasov, M. Kaparkova, V. Amoskov, V. Vasiliev
Publikováno v:
Plasma Devices and Operations. 14:47-59
The problem of complex thermohydraulic simulation of the magnet system of the International Thermonuclear Experimental Reactor using VINCENTA modelling is discussed. The results of validation of the VINCENTA modelling are presented on the basis of an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2f87dc68ee6277753cd265f13dac34c8
https://doi.org/10.1080/10519990500518001
https://doi.org/10.1080/10519990500518001
Autor:
A. Alekseev, V. Kokotkov, A. Malkov, A. Belov, E.A. Lamzin, L. Chvartatskaya, S. E. Sytchevsky, O. Filatov, A. Arneman, V. Kukhtin, N. Shatil, T. Belyakova
Publikováno v:
Plasma Devices and Operations. 10:269-284
Ways of nodal loads generating are considered. It is shown that the method based on the use of the shape function most adequately describes the volume forces spatial distribution. Based on this approach, the novel code NFORCE allows the calculation o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c545b970ad5d7426727ffcf8d28d3d16
https://doi.org/10.1080/1051999021000078378
https://doi.org/10.1080/1051999021000078378
Publikováno v:
IEEE Transactions on Appiled Superconductivity. 10:1074-1077
In the framework of the re-design of the ITER magnets, with the objective of reducing the dimensions and therefore the cost of the machine, the reduction of the nuclear shielding thickness at the critical inboard side of the plasma appears as a usefu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::64885b34a21b724741f800565ebac43c
https://doi.org/10.1109/77.828418
https://doi.org/10.1109/77.828418