Ž. Štancar K. Kirov F. Auriemma H.-T. Kim M. Poradzinski R. Sharma R. Lorenzini Z. Ghani M. Gorelenkova F. Poli A. Boboc S. Brezinsek P. Carvalho F. J. Casson C. Challis E. Delabie D. Van Eester M. Fitzgerald J. M. Fontdecaba J. Garcia L. Garzotti C. Giroud A. Kappatou Y. Kazakov D. King V. Kiptily D. Kos E. Lerche E. Litherland-Smith C. Maggi P. Mantica M. J. Mantsinen M. Maslov S. Menmuir M. Nocente J. Oliver S. Sharapov P. Siren E. R. Solano H. J. Sun G. Szepesi JET Contributors
In the paper we present an overview of interpretive modelling of a database of JET-ILW 2021 D-T discharges using the TRANSP code. Our main aim is to assess our capability of computationally reproducing the fusion performance of various D-T plasma scenarios using different external heating and D-T mixtures, and understand the performance driving mec…
PublishedA. Ho J. Citrin C. D. Challis C. Bourdelle F. J. Casson J. Hobirk A. Kappatou F. Koechl E. Lerche
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 scenario exhibits a hollow Te profile attributed to core impurity accumulation, which is observed to worsen with the increasing fuel ion mass from D to T. A dynamic D simulation was validated, evolvi…
PreprintJ. Mitchell A. Parrot F. E. Eriksson F. Casson O. Bardsley M. Lennholm H. Meyer S. Aleiferis
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 Production (STEP). These trajectories are computed by solving a non-linear, multi-objective, constrained, finite-time optimal control problem. A method unique to STEP ramp-up studies that prov…
Preprint PublishedA R Field D Fajardo F J Casson C Angioni C D Challis J Hobirk A Kappatou Hyun-Tae Kim E Lerche A Loarte J Mailloux JET Contributors
Screening of high-Z (W) impurities from the confined plasma by the temperature gradient at the hot edge pedestal of fusion-grade H-mode plasmas has been demonstrated for the first time in the JET-ILW tokamak. Through careful optimisation of the hybrid-scenario, deuterium plasmas with sufficient heating power (≳ 32MW), high enough ion temperature …
PreprintH. G. Dudding F. J. Casson D. Dickinson B. Patel C. M. Roach E. A. Belli G. M. Staebler
A new quasilinear saturation model SAT3 has been developed for the purpose of calculating radial turbulent fluxes in the core of tokamak plasmas. The new model is shown to be able to better recreate the isotope mass dependence of nonlinear gyrokinetic fluxes compared to contemporary quasilinear models, including SAT2 [1], whilst performing at least…
Preprint PublishedHyun-Tae Kim Francis Casson Hendrik Meyer Geof Cunningham Rory Scannell Lucy Kogan James Harrison Seong-Cheol Kim Jeong-Won Lee Jin-Woo Gwak Yong-Su Na Xavier Litaudon Gloria Falchetto3 MAST team
This paper describes the development of electromagnetic plasma burn-through model. Full circuit equations describing the currents in solenoid, poloidal field coil, and toroidally conducting passive structure have been integrated into the differential equation system of the plasma energy and particle balances in DYON. This enables consistent calcula…
Preprint PublishedA. Loarte A. R. Polevoi M. Schneider S.D. Pinches E. Fable E. Militello Asp Y. Baranov F. Casson G. Corrigan L. Garzotti D. Harting P. Knight F. Koechl V. Parail D. Farina L. Figini H. Nordman P. Strand R. Sartori
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Power Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed in order to identify key open R&D issues. The as…
Preprint PublishedA. Loarte A. R. Polevoi M. Schneider S.D. Pinches E. Fable E. Militello Asp Y. Baranov F. Casson G. Corrigan L. Garzotti D. Harting P. Knight F. Koechl V. Parail D. Farina L. Figini H. Nordman P. Strand R. Sartori
The optimum conditions for access and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed. The assessment is performed on the basis of empirical and…
Preprint PublishedV. K. Zotta L. Garzotti F. J. Casson D. Frigione F. Koechl E. Lerche P. Lomas F. Rimini M. Sertoli D. Van Eester R. Gatto C. Mazzotta G. Pucella
The fusion performance of ELMy H-mode DT plasmas with q95 = 3 and \\beta_N = 1.8 (also referred to as medium-\\beta_N baseline scenario in the rest of this paper) are predicted with the JINTRAC suite of codes and the QuaLiKiZ transport model. The predictions are based on the analysis of DT plasmas from the first DT campaign
Preprint Published