Results 31 to 40 of about 311 (75)

Flat-top plasma operational space of the STEP power plant

Nuclear Fusion
STEP is a spherical tokamak prototype power plant that is being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models to optimise fusion performance subject to satisfying various physics and engineering ...
E. Tholerus, F.J. Casson, S.P. Marsden, T. Wilson, D. Brunetti, P. Fox, S.J. Freethy, T.C. Hender, S.S. Henderson, A. Hudoba, K.K. Kirov, F. Koechl, H. Meyer, S.I. Muldrew, C. Olde, B.S. Patel, C.M. Roach, S. Saarelma, G. Xia, the STEP team   +19 more
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Extrapolations of the fusion performance in JET [PDF]

, 2015
n preparation of the forthcoming high power campaign with the reactor-relevant deuterium-tritium (DT) fuel mixture in the Joint European Torus (JET), significant efforts are being devoted to DT scenario extrapolation using computer modelling.
Challis, C., Gallart, Daniel, Garcia, J., Garzotti, L., Gutiérrez, A., Mantsinen, M.J., Sáez, X.   +6 more
core  

Gyrokinetic analysis and simulation of pedestals, to identify the culprits for energy losses using fingerprints

, 2019
Fusion performance in tokamaks hinges critically on the efficacy of the Edge Transport Barrier (ETB) at suppressing energy losses. The new concept of fingerprints is introduced to identify the instabilities that cause the transport losses in the ETB of ...
Chankin, A., Contributors, JET, Diallo, A., Giroud, C., Groebner, R., Hatch, D. R., Hillesheim, J. C., Koechl, F., Kotschenreuther, M., Liu, X., Maggi, C. F., Mahajan, S., Parail, V., Saarelma, S., Solano, E., TEAM, the DIII-D, Zheng, L.   +16 more
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Neural network surrogate of QuaLiKiz using JET experimental data to populate training space [PDF]

, 2021
Within integrated tokamak plasma modeling, turbulent transport codes are typically the computational bottleneck limiting their routine use outside of post-discharge analysis.
A. Ho, C. Bourdelle, F.J. Casson, H. Weisen, J. Citrin, JET Contributors, K.L. van de Plassche, Y. Camenen   +7 more
core  

Integrated modelling and multiscale gyrokinetic validation study of ETG turbulence in a JET hybrid H-mode scenario

, 2022
Previous studies with first-principle-based integrated modelling suggested that ETG turbulence may lead to an anti-GyroBohm isotope scaling in JET high-performance hybrid H-mode scenarios.
Angioni, C, Bonanomi, N, Bourdelle, C, Casson, F. J, Citrin, J, Contributors, JET, Fable, E, Goerler, T, Maeyama, S, Mantica, P, Mariani, A, Sertoli, M, Staebler, G, Watanabe, T   +13 more
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Modelling performed for predictions of fusion power in JET DTE2: overview and lessons learnt [PDF]

, 2023
For more than a decade, an unprecedented predict-first activity has been carried in order to predict the fusion power and provide guidance to the second Deuterium–Tritium (D–T) campaign performed at JET in 2021 (DTE2).
A. Ho, C.D. Challis, D. Gallart, D. Van Eester, D.M.A. Taylor, E. Lerche, F. Auriemma, F.J. Casson, H.-T. Kim, J. Ferreira, J. Garcia, JET Contributors, K.K. Kirov, L. Frassinetti, L. Garzotti, M. Nocente, M.J. Mantsinen, P. Huynh, S. Gabriellini, S. Saarelma, V.K. Zotta, Z. Stancar   +21 more
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Predictive density profile control with discrete pellets, applied to integrated simulations of ITER

Nuclear Fusion
Reliable core density control with pellet fueling will be necessary to achieve required fusion power output in future fusion tokamaks such as ITER.
C.A. Orrico, M. van Berkel, T.O.S.J. Bosman, L. Ceelen, W.P.M.H. Heemels, F. Koechl, D. Krishnamoorthy   +6 more
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Impact of the JET ITER-like wall on H-mode plasma fueling [PDF]

, 2017
JET ITER-like wall (ILW) experiments show that the edge density evolution is strongly linked with the poloidal distribution of the ionization source.
Brezinsek, S., García Muñoz, Manuel, Groth, M., Jet Contributors, Luna, E. de la, Wiesen, S., Wischmeier, M.   +6 more
core   +1 more source

WEST L-mode record long pulses guided by predictions using Integrated Modeling

Nuclear Fusion
A new record was set on the WEST Tokamak, designed to operate long duration plasmas in a tungsten (W) environment, with an injected energy of $1.15\,\mathrm{GJ}$ and a plasma duration $364\,\mathrm{s}$ .
T. Fonghetti, P. Manas, R. Dumont, J.-F. Artaud, C. Bourdelle, F.J. Casson, N. Cummings, L.F. Delgado-Aparicio, P. Maget, J. Morales, Y. Savoye-Peysson, M. Schneider, the WEST team   +12 more
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Plasma-wall interaction impact of the ITER re-baseline

Nuclear Materials and Energy
To mitigate the impact of technical delays, provide a more rationalized approach to the safety demonstration and move forward as rapidly as possible to a reactor relevant materials choice, the ITER Organization embarked in 2023 on a significant re ...
R.A. Pitts, A. Loarte, T. Wauters, M. Dubrov, Y. Gribov, F. Köchl, A. Pshenov, Y. Zhang, J. Artola, X. Bonnin, L. Chen, M. Lehnen, K. Schmid, R. Ding, H. Frerichs, R. Futtersack, X. Gong, G. Hagelaar, E. Hodille, J. Hobirk, S. Krat, D. Matveev, K. Paschalidis, J. Qian, S. Ratynskaia, T. Rizzi, V. Rozhansky, P. Tamain, P. Tolias, L. Zhang, W. Zhang   +30 more
doaj   +1 more source