Ian Chapman William Morris
Fusion power could be one of very few sustainable options to replace fossil fuels as the world’s primary energy source. Fusion offers the potential of predictable, safe power with no carbon emissions, and fuel sources lasting for millions of years. However, it is notoriously difficult to achieve in a controlled, steady-state fashion. The most pro…
Preprint PublishedJames Harrison C. Theiler B. Lipschultz A. Perek R. Maurizio B. Linehan W. A. J. Vijvers B. P. Duval B. Labit U. Sheikh K. Verhaegh S. Henderson A. Karpushov O. Fevrier H. de Oliviera H. Reimerdes A. Merle X. Feng the TCV team and the EUROfusion MST1 team
Recent experiments on TCV have made significant progress toward partial detachment of the outer divertor in neutral beam heated H-mode plasmas. The heating power required to enter H-mode was measured in a range of divertor configurations, finding that, in the vicinity of the PL-H/ne curve, the threshold power is largely independent of the poloidal …
Preprint PublishedKrassimir Kirov Yu. Baranov I.S. Carvalho C.D. Challis J. Eriksson D. Frigione L. Garzotti J. Graves P. Jacquet D.L. Keeling E. Lerche P.J. Lomas C. Lowry M. Mantsinen F. Rimini and JET Contributors
Fast ion synergistic effects were studied by predictive modelling of JET best performing pulses for various levels of Neutral Beam (NB) and Radio Frequency (RF) power. Calculated DD neutron yields were analysed with the intention of separating the impact of sheer synergistic effects due to changes in fast ion (FI) distribution function (DF) from su…
Preprint PublishedMichael Kovari Arne Kallenbach Mattia Siccinio
We have implemented a one-dimensional scrape-off layer (SOL) model in the PROCESS fusion reactor systems code. It allows reactor scenarios to be obtained while limiting both the plasma temperature of the SOL at the entrance to the sheath at the divertor target, and the power density on the target. To take account of cross-field transport in an …
Preprint PublishedMatti Coleman Y. Hoerstensmeyer F. Cismondi
One of the overarching goals of a DEMO-class device is to demonstrate tritium self-sufficiency in a fusion power plant for the first time. A future power reactor will necessarily require a start-up inventory of tritium, mT start, before commencing fully fledged D-T operations for electricity production. In Europe, it is also presently cons…
Preprint PublishedJonathan Shimwell Remi Delaporte-Mathurin Jean-Charles Jaboulay Julien Aubert Chris Richardson Chris Bowman Andrew Davis Jamie Bernardi Sikander Yasin Xiaoying Tang
Breeding blankets are designed to ensure tritium self-sufficiency in deuterium- tritium fusion power plants. In addition to this, breeder blankets play a vital role in shielding key components of the reactor, and provide the main source of heat which will ultimately be used to generate electricity. The design of blankets is critical to the success …
Preprint PublishedMatti Coleman S. McIntosh
The European DEMO fusion power reactor (EU-DEMO) is still in the pre-conceptual design phase. The design strategy for the EU-DEMO hinges on investigating multiple reactor designs and technologies in parallel, progressively down-selecting these in the mid-2020’s, in preparation for the conceptual design phase. The present implementation of the str…
Preprint PublishedMichael Komm Stuart Henderson Sarah Elmore COMPASS team EUROfusion MST1 team
Partial detachment is the desired regime for the baseline burning plasma scenario in ITER and next-step devices, as it allows to disspate the majority of the energy carried by charged particles through the scrape-off-layer (SOL) and thus avoids localised heat flux deposition in the divertor region. The COMPASS tokamak is equipped with an open diver…
Preprint PublishedB D Dudson J Allen T Body B Chapman C Lau L Townley D Moulton J Harrison B Lipschultz
A new 1D divertor plasma code, SD1D, has been used to examine the role of recombination, radiation, and momentum exchange in detachment. Neither momentum or power losses by themselves are found to be sufficient to produce target ion flux rollover in detachment; radiative power losses are required to a) limit and reduce the ionization source and …
Preprint PublishedVasili Kiptily F. Belli J. Eriksson C. Hellesen V.Goloborod’ko K.Schöpf
An effect due to fusion born triton production has been observed in JET high-performance deuterium plasma discharges with NBI and H-minority ICRF heating, using DD and DT neutron spectrometry as well as fusion product loss measurements. The observations show that increase of the triton burn up rate leads to decrease of second harmonic ωcH
Preprint Published