S. H. Ward R. Akers A. Jacobsen P. Ollus S. D. Pinches E. Tholerus R. G. L. Vann M. A. Van Zeeland
A novel high-performance computing algorithm, developed in response to the next generation of computational challenges associated with burning plasma regimes in ITER-scale tokamak devices, has been tested and is described herein. LOCUST-GPU 2 The Lorentz-Orbit Code for Use in Stellarators and Tokamaks (LOCUST) is designed for computationally scal…
Preprint PublishedS. Jimenez D. Bookless R. Nath W.J. Leong
In order to reach commercially-relevant availability future fusion power plants must have highly efficient maintenance systems. On the other hand, as radiation levels increase so too will the number of maintenance tasks that must be performed without human access. To meet these conflicting constraints remote maintenance systems must significantly…
Preprint PublishedAndrew Davis Aleksander Dubas Rubin Otin
The field of fusion energy is about to enter the ITER era, for the first time we will have access to a device capable of producing 500 MW of fusion power, with plasmas lasting more than 300 seconds and with core tem- perature…
Preprint PublishedA.Valentine N.Fonnesu B.Bienkowska E.Laszynska D.Flammini R.Villari G.Mariano T.Eade T.Berry L.Packer
As a demonstration fusion power plant, EU DEMO has to prove the maturity of fusion technology and its viability for electricity production. The central requirements for DEMO rest on its capability to generate significant net electric power to the grid (300MW to 500 MW) safely and consistently. Plant availability and lifetime will approach that of a…
Preprint PublishedL. Xiang F. Militello D. Moulton F. Subba L. Aho-Mantila D. Coster M. Wensing T. Lunt M. Wischmeier H. Reimerdes
The SOLPS-ITER simulations of European DEMO reactor, with 450 MW of power to be exhausted, show an increased operational space compared to the conventional single-null configuration. Using a reduced model with fluid neutrals and bundled impurities, we assessed the existence and the boundaries of operational space for DEMO with the conventional sing…
Preprint PublishedTriestino Minniti Frank Schoofs Llion Marc Evans Winfried Kockelmann J.H. You Heather Lewtas
The divertor target plates are the most exposed in-vessel components to high heat flux loads in a fusion reactor due to a combination of plasma bombardment, radiation and nuclear heating. Reliable exhaust systems of such a huge thermal power required a robust and durable divertor target with a sufficiently large heat removal capability and lifetime…
Preprint PublishedH. J. Sun E. Wolfrum T. Eich A. Kallenbach P. Schneider B. Kurzan U. Stroth the ASDEX Upgrade Team
A survey of the correlation between temperature and density gradient lengths ( and ) has been performed for the near SOL regions in the ASDEX Upgrade tokamak. In common with previous studies, the near SOL temperature and density gradient length ratio, , is found to be close to unity across a wide range of plasmas. However, it is found that it is po…
Preprint PublishedShuo Wang Yueqiang Liu Guoliang Xia X. M. Song G. Z. Hao L. Li B. Li N. Zhang G. Q. Dong X. Bai G. Y. Zheng
The resistive wall mode (RWM) control on the HL-2M tokamak is simulated with the MARS-F code [Liu Y Q et al 2000 Phys. Plasmas 7 3681], aiming at quantifying control current and voltage requirements when more realistic issues are taken into account, i.e. the control power saturation and the sensor signal noise. The fluid model predicts a narrow st…
Preprint PublishedL. W. Packer P. Batistoni B. Colling K. Drozdowicz M. Fabbri Z. Ghani M. R Gilbert S. Jednorog E. Laszynska D. Leichtlef J.W.Mietelski C.R. Nobs M. Pillon I.E. Stamatelatos T. Vasilopoulou R. Villari A. Wójcik-Gargula JET Contributors
The planned high-profile experiments during 2020 at the Joint European Torus (JET), notably including a deuterium-tritium (DT) experimental phase, are expected to produce large neutron yields, in the region of 1021 neutrons. The scientific objectives are linked with a technology programme, WPJET3, to deliver the maximum scientific and…
PreprintD. Kumar J. Hargreaves A. Bharj A. Scorror L. M. Harding H. Dominguez-Andrade R. Holmes R. Burrows H. Dawson A. D. Warren P.E.J. Flewitt T.L. Martin
Plasma-wall interactions in a commercial-scale fusion power station may exert high transient thermal loads on plasma-facing surfaces, repeatedly subjecting underlying structural materials to high temperatures for short durations. Specimens of the reduced activation ferritic-martensitic steel Eurofer-97 were continuously aged at constant temperat…
Preprint Published