S.M. Kaye J.W. Connor C.M. Roach
In this paper, we review the confinement and transport properties observed and predicted in low aspect ratio tokamaks, or spherical tokamaks (STs), which can depart significantly from those observed at higher aspect ratio. In particular, thermal energy confinement scalings show a strong, near linear dependence of energy confinement time on toroidal…
Preprint PublishedArunodaya Bhattacharya Steven J Zinkle Jean Henry Samara M Levine Philip D Edmondson MarkRGilbert Hiroyasu Tanigawa Charles E Kessel
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The performance of these steels will deteriorate during service due to neutron damage and transmutation-induced gases, such as helium/hydrogen, at elevated operating tempera…
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 …
PreprintS B L Chislett-McDonald E Surrey J Naish A Turner D P Hampshire
All high field superconductors producing magnetic fields above 12 T are brittle. Nevertheless, they will probably be the materials of choice in commercial tokamaks because the fusion power density in a tokamak scales as the fourth power of magnetic field. Here we propose using robust, ductile superconductors during the reactor commissioning phase i…
PreprintHyun-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 PublishedG. Decristoforo A. Theodorsen J. Omotani T. Nicholas O. E. Garcia
Intermittent fluctuations in the boundary of magnetically confined plasmas are investigated by numerical turbulence simulations of a reduced fluid model describing the evolution of the plasma density and electric drift vorticity in the two-dimensional plane perpendicular to the magnetic field. Two different cases are considered, one describing resi…
Preprint PublishedF. Schoofs T. N. Todd
We describe a workflow that is able to approximate basic machine parameters (including but not limited to plasma current IP, major radius R0, toroidal magnetic field B0, fusion power Pfusion) based on the choice of maximum field BTF,max on the in-boa…
Preprint PublishedO. Myatra B. Lipschultz D. Moulton K. Verhaegh B. Dudson S. Orchard A. Fil C. Cowley
Control of the detachment front between the target and the X-point is necessary for minimizing the effect of detachment on the core plasma (core radiation and loss of confinement) and maximizing the divertor functions (reduction of target heat load and sputtering, He pumping). However, such control has been difficult in experiments. The SOLPS-ITER …
PreprintC.D. Challis J. Hobirk A. Kappatou E. Lerche F. Auriemma E.Belonohy I. Coffey J. Eriksson A. Field M.Fontana J.Garcia A. Ho F. Jaulmes D. Keeling D. King K. Kirov M. Lennholm C.Maggi J.Mailloux M. Maslov S. Menmuir G. Pucella E. Rachlew F. Rimini A. Sahlberg A.Sips E. Solano C. Stuart M. Valisa
A key aim of the 2021 JET deuterium-tritium (D-T) experiments was to demonstrate steady high fusion power (10-15MW) with the ITER-like Be/W first wall. Plasmas were developed using D, repeated with T to investigate and mitigate isotope effects, and run with D-T to maximise fusion power. Compared with high current (q95~3) ‘baseline’ plasmas, …
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