Search Results - "Köchl, F."

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  1. 1

    Considerations on the DEMO pellet fuelling system by Lang, P.T., Day, Ch, Fable, E., Igitkhanov, Y., Köchl, F., Mooney, R., Pegourie, B., Ploeckl, B., Wenninger, R., Zohm, H.

    Published in Fusion engineering and design (01-10-2015)
    “…•Considerations are made for a core particle fuelling system covering all DEMO requirements.•Particle deposition beyond the pedestal top is needed to achieve…”
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    Journal Article
  2. 2

    Blower Gun pellet injection system for W7-X by Dibon, M., Baldzuhn, J., Beck, M., Cardella, A., Köchl, F., Kocsis, G., Lang, P.T., Macian-Juan, R., Ploeckl, B., Szepesi, T., Weisbart, W.

    Published in Fusion engineering and design (01-10-2015)
    “…•Operational principle of the ASDEX Upgrade Blower Gun.•Guiding tube properties for pellet guiding according to the requirements of W7-X.•Diagnostics for the…”
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    Journal Article
  3. 3

    EU DEMO transient phases: Main constraints and heating mix studies for ramp-up and ramp-down by Vincenzi, P., Ambrosino, R., Artaud, J.F., Bolzonella, T., Garzotti, L., Giruzzi, G., Granucci, G., Köchl, F., Mattei, M., Tran, M.Q., Wenninger, R.

    Published in Fusion engineering and design (01-11-2017)
    “…•Further additional dedicated ramp-up power is needed.•H-mode access determines the requested additional power.•In ramp-down radiation losses must be…”
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    Journal Article
  4. 4

    Fuelling of deuterium–tritium plasma by peripheral pellets in JET experiments by Valovič, M., Aleiferis, S., Blatchford, P., Boboc, A., Brix, M., Carvalho, P., Carvalho, I., Fontdecaba Climent, M., Dunai, D., Frassinetti, L., Garzotti, L., Köchl, F., Lowry, J.C., de la Luna, E., Maggi, C.F., Morales, R.B., Nowak, S., Olde, C., Réfy, D., Rimini, F., Silburn, S., Štancar, Ž., Tvalashvili, G., Vecsei, M.

    Published in Nuclear fusion (01-07-2024)
    “…Abstract A baseline scenario of deuterium–tritium (D–T) plasma with peripheral high-field-side fuelling pellets has been produced in JET in order to mimic the…”
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  5. 5

    Assessment of plasma power deposition on the ITER ICRH antennas by Brank, M., Pitts, R.A., Simič, G., Lamalle, P., Kocan, M., Köchl, F., Gribov, Y., Polli, V., Kos, L.

    Published in Nuclear materials and energy (01-06-2021)
    “…•Heat fluxestoITER ICRH antenna Faraday shield evaluated for Q = 10 burning plasmas.•Plasma thermal and radiative photon loads included in full 3D CAD…”
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  6. 6

    Investigation of the dependence of pe,ped on ne,sep in JET H-Mode plasmas using integrated JETTO-MISHKA-FRANTIC simulations by Simpson, J., Moulton, D., Giroud, C., Groth, M., Horvath, L., Casson, F.J., Kochl, F., Frassinetti, L., Corrigan, G., Saarelma, S., Garzotti, L., Gahle, D.S., Chankin, A.

    Published in Nuclear materials and energy (01-03-2023)
    “…Experimentally, it has been observed in high-confinement (H-Mode) plasmas with Edge Localised Modes (ELMs) on JET that the pressure pedestal (pe,ped) is…”
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  7. 7

    An examination of the Neutral Penetration Model 1/ne,ped scaling for its validity of spatially varying neutral sources by Simpson, J., Moulton, D., Giroud, C., Casson, F., Groth, M., Chankin, A., Horvath, L., Gahle, D.S., Garzotti, L., Corrigan, G., Kochl, F.

    Published in Nuclear materials and energy (01-09-2021)
    “…•EDGE2D-EIRENE simulations showed the dominant neutral source at the separatrix originates from the inner target for this specific JET H-mode…”
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  8. 8
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  10. 10

    Investigation of the dependence of p(e,ped) on n(e,sep) in JET H-Mode plasmas using integrated JETTO-MISHKA-FRANTIC simulations by Simpson, J., Moulton, D., Giroud, C., Groth, M., Horvath, L., Casson, F. J., Kochl, F., Frassinetti, Lorenzo, Corrigan, G., Saarelma, S., Garzotti, L., Gahle, D. S., Chankin, A.

    Published in Nuclear materials and energy (2023)
    “…Experimentally, it has been observed in high-confinement (H-Mode) plasmas with Edge Localised Modes (ELMs) on JET that the pressure pedestal (p(e,ped)) is…”
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    Journal Article
  11. 11

    Constructing a new predictive scaling formula for ITER's divertor heat-load width informed by a simulation-anchored machine learning by Chang, C. S, Ku, S, Hager, R, Churchill, R. M, Hughes, J, Köchl, F, Loarte, A, Parail, V, Pitts, R

    Published 05-01-2021
    “…Understanding and predicting divertor heat-load width ${\lambda}_q$ is a critically important problem for an easier and more robust operation of ITER with high…”
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  12. 12
  13. 13

    Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER by Chang, C. S, Ku, S, Loarte, A, Parail, V, Köchl, F, Romanelli, M, Maingi, R, Ahn, J. -W, Gray, T, Hughes, J, LaBombard, B, Leonard, T, Makowski, M, Terry, J

    Published 21-04-2017
    “…The XGC1 edge gyrokinetic code is used for a high fidelity prediction for the width of the heat-flux to divertor plates in attached plasma condition. The…”
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    Journal Article