Search Results - "Koechl, F."

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  1. 1

    Core transport modelling of the DTT full power scenario using different fuelling strategies by Baiocchi, B., Aucone, L., Casiraghi, I., Figini, L., Koechl, F., Mantica, P.

    Published in Nuclear fusion (01-10-2023)
    “…Abstract A theory-based integrated modelling work of plasma response to deuterium fuelling in the new Divertor Tokamak Test facility (DTT) is performed, using…”
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    Journal Article
  2. 2

    Ripple-induced neoclassical toroidal viscous torque in Augmented-First Plasma operation phase in ITER by Liu, Yueqiang, Bai, Xue, Gribov, Y., Koechl, F., Loarte, A., Pinches, S.D., Schmitz, L.

    Published in Nuclear fusion (01-10-2024)
    “…Abstract A systematic calculation is performed on the ripple-induced neoclassical toroidal viscous (NTV) torque for new ITER scenarios designed for the…”
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    Journal Article
  3. 3

    Predictive JET current ramp-up modelling using QuaLiKiz-neural-network by Ho, A., Citrin, J., Challis, C.D., Bourdelle, C., Casson, F.J., Garcia, J., Hobirk, J., Kappatou, A., Keeling, D.L., King, D.B., Koechl, F., Lerche, E., Maggi, C.F., Mailloux, J.

    Published in Nuclear fusion (01-06-2023)
    “…Abstract This work applies the coupled JINTRAC and QuaLiKiz-neural-network (QLKNN) model on the ohmic current ramp-up phase of a JET D discharge. The chosen…”
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    Journal Article
  4. 4

    A comparison of the influence of plasmoid-drift mechanisms on plasma fuelling by cryogenic pellets in ITER and Wendelstein 7-X by Panadero, N., Koechl, F., Polevoi, A.R., Baldzuhn, J., Beidler, C.D., Lang, P.T., Loarte, A., Matsuyama, A., McCarthy, K.J., Pégourié, B., Turkin, Y.

    Published in Nuclear fusion (01-04-2023)
    “…Abstract Pellet injection is the most promising technique to achieve efficient plasma core fuelling, key for attaining stationary scenarios in large magnetic…”
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    Journal Article
  5. 5

    Integrated model control simulations of the electron density profile and the implications of using multiple discrete pellet injectors for control by Bosman, T.O.S.J., Koechl, F., Ho, A., de Baar, M.R., Krishnamoorthy, D., van Berkel, M.

    Published in Nuclear fusion (01-12-2023)
    “…Abstract Pellet injection is regarded as the only realistic actuator for core density control in future reactors such as ITER and DEMO. However, a control…”
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    Journal Article
  6. 6

    Neon seeding effects on two high-performance baseline plasmas on the Joint European Torus by Gabriellini, S., Garzotti, L., Zotta, V.K., Bourdelle, C., Casson, F.J., Citrin, J., Frigione, D., Gatto, R., Giroud, C., Koechl, F., Lomas, P., Marin, M., Menmuir, S., Pucella, G., Rimini, F., van Eester, D.

    Published in Nuclear fusion (01-08-2023)
    “…Abstract We present the JETTO-QuaLiKiz-SANCO fully predictive modelling of two JET-ILW high-performance baseline plasmas, a Ne seeded shot and an equivalent…”
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    Journal Article
  7. 7

    Flat-top plasma operational space of the STEP power plant by Tholerus, E., Casson, F.J., Marsden, S.P., Wilson, T., Brunetti, D., Fox, P., Freethy, S.J., Hender, T.C., Henderson, S.S., Hudoba, A., Kirov, K.K., Koechl, F., Meyer, H., Muldrew, S.I., Olde, C., Patel, B.S., Roach, C.M., Saarelma, S., Xia, G.

    Published in Nuclear fusion (01-10-2024)
    “…Abstract STEP is a spherical tokamak prototype power plant that is being designed to demonstrate net electric power. The design phase involves the exploitation…”
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    Journal Article
  8. 8
  9. 9

    Assessment of the ITER divertor bolometer diagnostic performance by Brank, M., Pitts, R.A., Kalvin, S., Zoletnik, S., Koechl, F., Meister, H., Neverov, V.S., Reichle, R., Schneider, M., Kos, L.

    Published in Nuclear materials and energy (01-12-2023)
    “…•Radiative heat fluxes to ITER divertor bolometer housings estimated from plasma radiation distribution.•Detailed 3D geometry of first wall used with plasma…”
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    Journal Article
  10. 10

    ELM and inter-ELM tungsten erosion sources in high-power, JET ITER-like wall H-mode plasmas by Kumpulainen, H.A., Groth, M., Brezinsek, S., Corrigan, G., Frassinetti, L., Harting, D., Koechl, F., Karhunen, J., Meigs, A.G., O'Mullane, M., Romazanov, J.

    Published in Nuclear materials and energy (01-10-2022)
    “…•High-power type-I ELMy JET plasmas simulated using JINTRAC and ERO2.0.•Near-perfect screening predicted for highest gross W sources at divertor targets.•W…”
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    Journal Article
  11. 11

    Validation of EDGE2D-EIRENE and DIVIMP for W SOL transport in JET by Kumpulainen, H.A., Groth, M., Corrigan, G., Harting, D., Koechl, F., Jaervinen, A.E., Lomanowski, B., Meigs, A.G., Sertoli, M.

    Published in Nuclear materials and energy (01-12-2020)
    “…Tungsten sputtering rates and density profiles predicted using the edge plasma codes EDGE2D-EIRENE and DIVIMP are found to agree within a factor of 4 with…”
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    Journal Article
  12. 12

    Coupled core-SOL modelling of W contamination in H-mode JET plasmas with ITER-like wall by Parail, V., Corrigan, G., Da Silva Aresta Belo, P., De La Luna, E., Harting, D., Koechl, F., Koskela, T., Meigs, A., Militello-Asp, E., Romanelli, M., Tsalas, M.

    Published in Journal of nuclear materials (01-08-2015)
    “…The influence of the ITER-like Wall (ILW) with divertor target plate made of tungsten (W), on plasma performance in JET H-mode is being investigated since 2011…”
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    Journal Article
  13. 13

    Preparation for the operation of ITER: EU study on the plasma control system by Cavinato, M., Ambrosino, G., Figini, L., Granucci, G., Gribov, Y., Koechl, F., Mattei, M., Parail, V., Pironti, A., Ricci, D., Saibene, G., Sartori, R., Zabeo, L.

    Published in Fusion engineering and design (01-10-2014)
    “…In view of the preparation for the operation of the ITER tokamak it is necessary to develop the plasma scenarios taking into account all engineering…”
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    Journal Article
  14. 14

    Integrated Core-SOL Simulations of ITER H-Mode Scenarios with Different Pedestal Density by Ivanova-Stanik, I., Koechl, F., Voitsekhovitch, I., Telesca, G., Zagörski, R., EU-ITM ITER Scenario Modelling group

    Published in Contributions to plasma physics (1988) (01-06-2014)
    “…Fusion performance of ITER H‐mode plasmas in presence of intrinsic (He, Be and W) and seeded (Ne) im purities is investigated in self‐consistent…”
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    Journal Article
  15. 15

    ITER operational space for full plasma current H-mode operation by Mattei, M., Cavinato, M., Saibene, G., Portone, A., Albanese, R., Ambrosino, G., Horton, L.D., Kessel, C., Koechl, F., Lomas, P.J., Nunes, I., Parail, V., Sartori, R., Sips, A.C.C., Thomas, P.R.

    Published in Fusion engineering and design (01-06-2009)
    “…Sensitivity studies performed as part of the ITER IO design review highlighted a very stiff dependence of the maximum Q attainable on the machine parameters…”
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    Journal Article Conference Proceeding
  16. 16

    Scenario trajectory optimization and control on STEP by Mitchell, J., Parrott, A., Casson, F.J., Eriksson, F.E., Koechl, F., Lennholm, M., Bardsley, O., Meyer, H.F., Aleiferis, S.

    Published in Fusion engineering and design (01-07-2023)
    “…In this paper we present optimized actuator trajectories, evolving in time and space, of non-inductive ramp-up scenarios for the Spherical Tokamak for Energy…”
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    Journal Article
  17. 17

    Divertor Tokamak Test facility project: status of design and implementation by Agguiaro, D., Andreoli, P., Angelone, M., Antonini, P., Apruzzese, G., Arena, P., Balestri, A., Bianucci, S., Bin, W., Boeswirth, B., Bonaventura, A., Boncagni, L., Bonifetto, R., Brezinsek, S., Busi, D., Candela, V., Carrelli, C., Casiraghi, I., Causa, F., Cavenago, M., Cecchini, M., Centioli, C., Cesaroni, S., Ciotti, M., Coccorese, D., Crescenzi, F., Danè, F., De Leo, V., De Luca, R., De Sano, G., Delfino, A., Dima, R., Domenichelli, A., Doria, A., Elitropi, M., Figini, L., Filippi, F., Fimiani, A., Frescura, A., Gaetani, P., Galdon Quiroga, J., Gammino, S., Gandolfo, G., Garcia Lopez, J., Giorgetti, F., Giruzzi, G., Gorini, G., Guerini, S., Lanchi, C., Loureiro, J., Maddaluno, G., Mandalà, P., Manganelli, M., Marchiori, G., Marinelli, M., Marocco, D., Martini, G., Marucci, A., Marzullo, D., Meller, P., Migliori, S., Milanesio, D., Minelli, P., Nocente, M., Nowak, S., Orsetti, V., Pacella, D., Panza, F., Parisi, M., Passarello, S., Pesenti, A., Piron, L., Placido, D., Pizzuto, A., Platania, P., Previti, A., Recchia, M., Riccardi, B., Rubino, G., Rubino, S., Salvini, P., Salvitti, A., Simonetto, A., Sirignano, A., Testoni, R., Toigo, V., Torrisi, G., Trotta, A., Tuccillo, A., Tudisco, O., Uccello, A., Vassallo, E., Verdini, L., Verona, C., Verona Rinati, G., Vianello, N., Villano, O., Vitale, V., Wu, H.S., Wyss, I.

    Published in Nuclear fusion (01-11-2024)
    “…Abstract An overview is presented of the progress since 2021 in the construction and scientific programme preparation of the Divertor Tokamak Test (DTT)…”
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    Journal Article
  18. 18

    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
  19. 19

    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
  20. 20

    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