Search Results - "Asunta, O."

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  1. 1

    Overview and status of construction of ST40 by Gryaznevich, M., Asunta, O.

    Published in Fusion engineering and design (01-11-2017)
    “…•An overview of a new generation high field spherical tokamak, ST40, is presented.•The mechanical structure, magnets, and power supplies are described.•The…”
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    Journal Article
  2. 2

    Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations by Asunta, O., Govenius, J., Budny, R., Gorelenkova, M., Tardini, G., Kurki-Suonio, T., Salmi, A., Sipilä, S.

    Published in Computer physics communications (01-03-2015)
    “…Neutral beam injection (NBI) will be one of the main sources of heating and non-inductive current drive in ITER. Due to high level of injected power the beam…”
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    Journal Article
  3. 3

    ST40 data and control by Asunta, O., Buxton, P.F., Lister, J.B., Pinkney, E., Scott, L.

    Published in Fusion engineering and design (01-09-2019)
    “…•An R0 = 0.4 m spherical tokamak, ST40, was built and operated by Tokamak Energy Ltd.•A modular Machine Control System was developed to tackle plant…”
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    Journal Article
  4. 4

    DIVIMP-B2-EIRENE modelling of (13)C migration and deposition in ASDEX Upgrade L-mode plasmas by Xuereb, A, Groth, M, Krieger, K, Asunta, O, Kurki-Suonio, T, Likonen, J, Coster, D P

    Published in Journal of nuclear materials (31-01-2010)
    “…Carbon transport and migration were studied experimentally and numerically in a high-density, low-confinement mode plasma in the ASDEX Upgrade tokamak. On the…”
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    Journal Article
  5. 5

    DIVIMP-B2-EIRENE modelling of 13C migration and deposition in ASDEX Upgrade L-mode plasmas by Xuereb, A., Groth, M., Krieger, K., Asunta, O., Kurki-Suonio, T., Likonen, J., Coster, D.P.

    Published in Journal of nuclear materials (31-01-2010)
    “…Carbon transport and migration were studied experimentally and numerically in a high-density, low-confinement mode plasma in the ASDEX Upgrade tokamak. On the…”
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    Journal Article
  6. 6

    ASCOT: Solving the kinetic equation of minority particle species in tokamak plasmas by Hirvijoki, E., Asunta, O., Koskela, T., Kurki-Suonio, T., Miettunen, J., Sipilä, S., Snicker, A., Äkäslompolo, S.

    Published in Computer physics communications (01-04-2014)
    “…A comprehensive description of methods, suitable for solving the kinetic equation for fast ions and impurity species in tokamak plasmas using a Monte Carlo…”
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    Micro ion beam analysis for the erosion of beryllium marker tiles in a tokamak limiter by Zhou, Y., Bergsåker, H., Bykov, I., Petersson, P., Paneta, V., Possnert, G.

    “…Beryllium limiter marker tiles were exposed to plasma in the Joint European Torus to diagnose the erosion of main chamber wall materials. A limiter marker tile…”
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  12. 12

    Calculating the 3D magnetic field of ITER for European TBM studies by Äkäslompolo, Simppa, Asunta, Otto, Bergmans, Thijs, Gagliardi, Mario, Galabert, Jose, Hirvijoki, Eero, Kurki-Suonio, Taina, Sipilä, Seppo, Snicker, Antti, Särkimäki, Konsta

    Published in Fusion engineering and design (01-10-2015)
    “…[Display omitted] •Implemented a combined FEM Biot-Savart law method to calculate ITER magnetic fields.•Detailed ITER 3D magnetic fields, with ferromagnetic…”
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    Journal Article
  13. 13

    Studies of Be migration in the JET tokamak using AMS with Be-10 marker by Bykov, Igor, Bergsaker, Henric, Possnert, G., Zhou, Y., Heinola, K., Pettersson, J., Conroy, S., Likonen, J., Petersson, Per, Widdowson, A.

    “…The JET tokamak is operated with beryllium limiter tiles in the main chamber and tungsten coated carbon fiber composite tiles and solid W tiles in the…”
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    Journal Article
  14. 14

    Validating fast-ion wall-load IR analysis-methods against W7-X NBI empty-torus experiment by Äkäslompolo, S, Drewelow, P, Gao, Y, Ali, A, Asunta, O, Bozhenkov, S, Fellinger, J, Ford, O. P, Harder, N. den, Hartmann, D, Jakubowski, M, McNeely, P, Niemann, H, Pisano, F, Rust, N, Sitjes, A. Puig, Sleczka, M, Spanier, A, Wolf, R. C, Team, the W7-X

    Published 20-06-2019
    “…2019 JINST 14 P07018 The first neutral beam injection (NBI) experiments in Wendelstein 7-X (W7-X) stellarator were conducted in the summer of 2018. The NBI…”
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    Journal Article
  15. 15

    Power requirements for electron cyclotron current drive and ion cyclotron resonance heating for sawtooth control in ITER by Chapman, I. T, Graves, J. P, Sauter, O, Zucca, C, Asunta, O, Buttery, R. J, Coda, S, Goodman, T, Igochine, V, Johnson, T, Jucker, M, La Haye, R. J, Lennholm, M, Contributors, JET-EFDA

    Published 19-06-2013
    “…Nuclear Fusion 53 066001 (2013) 13MW of electron cyclotron current drive (ECCD) power deposited inside the q = 1 surface is likely to reduce the sawtooth…”
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