F.Eriksson E.Tholerus G.Corrigan Y.Baranov X.Bonnin D.Farina L.Figini L.Garzotti S.H.Kim F.Koechl A.Loarte E.Militello Asp C.Olde V.Parail S.D.Pinches A.Polevoi P.Strand
To design a safe termination scenario for a burning ITER plasma is a challenge that requires extensive core plasma and divertor modelling. The presented work consists of coupled core/edge/SOL/divertor simulations, performed with the JINTRAC code, studying the Q=10 flat-top phase and exit phase of the ITER 15MA/5.3T DT scenario. The modelling uti…
PreprintT. Gheorghiu F. Militello J. Juul Rasmussen
Shear flows in turbulent fluids have been known to act as transport barriers for some time. An example of a shear flow generating mechanism is the E×B shear in plasma, which has a substantial impact on the dynamics of magnetic confinement fusion devices. The influence of this may be seen in the scrape-off layer (SOL) where blobs or filaments may b…
Preprint PublishedS. Mijin D. Power R. Holden W. Hornsby D. Moulton F. Militello
In this manuscript we present the recently developed flexible framework for building both fluid and electron kinetic models of the tokamak Scrape-Off Layer in 1D - ReMKiT1D (Reactive Multi-fluid and Kinetic Transport in 1D). The framework can handle systems of non-linear ODEs, various 1D PDEs arising in fluid modelling, as well as PDEs arising from…
Preprint PublishedD. Power S. Mijin F. Militello R. Kingham
Tokamak edge (scrape-off layer) plasmas can exhibit non-local transport in the direction parallel to the magnetic field due to steep temperature gradients.This effect along with its consequences has been explored at equilibrium fora range of conditions, from sheath-limited to detached, using the 1D kinetic electron code SOL-KiT, where the electrons…
PreprintNick Walkden Fabio Riva James Harrison Fulvio Militello Tom Farley John Omotani
Fusion power plant designs based on magnetic confinement, such as the tokamak design, offer a promising route to sustainable fusion power but require robust exhaust solutions capable of tolerating intense heat and particle fluxes from the plasma to material surfaces. Turbulent plasma transport in the divertor volume – the region where the plasma-…
Preprint PublishedT. E. G. Nicholas J. Omotani F. Riva F. Militello B. Dudson
There exists a large body of previous work using reduced two-dimensional models of the SOL, which model fluctuations in the drift-plane but approximate parallel transport with effective loss terms. Full size three-dimensional simulations of SOL turbulence in experimental geometries are now possible, but are far more computationally expensive than …
Preprint PublishedH. J. Sun R. J. Goldston A. Huber X. Q. Xu J. Flanagan D. C. McDonald E. de la Luna M. Maslov J. R. Harrison F. Militello J. Fessey S. Cramp JET Contributors
A study of a dataset of JET H-mode plasma with the Be/W ITER-like wall (JET-ILW) shows that reaching the edge MHD ballooning limit leads to confinement degradation. However, unlike JET plasmas with a carbon wall (JET-C), the JET-ILW plasmas stay in a marginal dithering phase for a relatively long period, associated with a higher (20%) H-mode den…
Preprint PublishedYulin Zhou Benjamin Dudson Fulvio Militello Kiven Verhaegh Omkar Myatra
The role of neutral and charged hydrogenic molecules in detached regimes of tokamak plasmas is investigated using simplified 1D parallel numerical models. Using MAST-Upgrade like conditions, simulations are implemented to study the rollover of target flux in upstream density scan and target temperature scan. It is found that if H2 and H2+ are cons…
PreprintE. Tholerus L. Garzotti Y. Baranov G. Corrigan F. Eriksson D. Farina L. Figini D.M. Harting F. Koechl A. Loarte E. Militello Asp H. Nordman V. Parail S.D. Pinches A.R. Polevoi R. Sartori P. Strand
An important part of the ITER Research Plan [1] is the Pre-Fusion Power Operation (PFPO) phase, which includes demonstration of H-mode plasma operation and the commissioning of ELM control systems. However, since hydrogen or helium are the main ion species in PFPO plasmas, the L–H power threshold PL–H is expected to be cons…
PreprintJ. R. Harrison T. Farley G. M. Fishpool A. Kirk B. Lipschultz J. Lovell F. Militello D. Moulton P. Ryan R. Scannell A. J. Thornton K. Verhaegh L. Xiang
The benefits of an optimised Super-X divertor configuration in mitigating the steady-state power and particle fluxes to the surfaces of the MAST Upgrade divertor have been quantified by performing a detailed comparison with a conventional divertor for the first time. In otherwise identical plasmas with conventional and Super-X divertor configu…
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