O.Crofts A.Loving M.Torrance S.Budden B.Drumm T.Tremethick D.Chauvin M.Siuko W.Brace V.Milushev M.Mittwollen T.Lehmann F.Rauscher G.Fischer P.Pagani Y.Wang C.Baars A.Vale
During the EU DEMO Pre-Concept Design Phase, the remote maintenance team developed maintenance strategies and systems to meet the evolving plant maintenance requirements. These were constrained by the proposed tokamak architecture and the challenging environments but considered a range of port layouts and handling system designs. The design‑d…
Preprint PurchaseM.R. Gilbert T. Eade C. Bachmann U. Fischer N.P. Taylor
Waste-production predictions for the future demonstration fusion power plant (DEMO) are necessary to produce an accurate picture of the likely environmental and economic costs of radioactive waste disposal at end-of-life (EOL). Even during the conceptual stage of DEMO design it is important to perform waste assessment so as to avoid potential surpr…
Preprint PublishedM Valovic P T Lang A Kirk W Suttrop M Bernert M Cavedon M Dunne R Fischer L Garzotti L Guimarais F Janky N Leuthold PJ Mc Carthy A Mlynek B Plockl G Tardini E Viezzer E Wolfrum the ASDEX Upgrade team the EUROfusion MST1 team
Pellets are used in ASDEX Upgrade [1] to control plasma density under conditions of ELM control or divertor detachment. In experiments presented here direct fuelling by gas is negligible. Relative pellet size and pellet deposition are aimed to approach those in ITER but differences still remain. ELMs are controlled by n=2 RMPs in feed forward mode …
PreprintM. Willensdorfer T.B. Cote M. Griener D.A. Ryan E. Strumberger W. Suttrop N. Wang M. Cavedon S.S. Denk M. Dunne R. Fischer J. Galdon-Quiroga C.J. Ham C.C. Hegna M. Hoelzl A. Kirk M. Maraschek F. Mink N. Leuthold F. Orain E. P. Seliunin H. Zohm the ASDEX Upgrade Team and the MST1 Team
The impact of the three-dimensional (3D) tokamak geometry from external magnetic perturbations (MPs) on the local edge stability has been examined in high confinement mode (H-mode) plasmas with edge localised modes (ELMs) in ASDEX Upgrade. The 3D geometry has been probed using rigidly rotating MP fields. The measured distortions of the plasma bound…
Preprint PublishedM.R. Gilbert T. Eade C. Bachmann U. Fischer N.P. Taylor
Inventory calculations have a key role to play in designing future fusion power plants because, for a given irradiation field and material, they can predict the time evolution in chemical composition, activation, decay heat, gamma-dose, gas production, and even damage (dpa) dose. For conceptual designs of the European DEMO fusion reactor such calcu…
Preprint PublishedM. Valovič P.T. Lang A. Kirk W. Suttrop M. Cavedon G. Cseh M. Dunne L.R. Fischer L. Garzotti L. Guimarais G. Kocsis A. Mlynek B. Plőckl R. Scannell T. Szepesi G. Tardini A. Thornton E. Viezzer E. Wolfrum The ASDEX Upgrade team The EUROfusion MST1 team
The complete refuelling of the plasma density loss (pump-out) caused by mitigation of Edge Localised Modes (ELMs) is demonstrated on the ASDEX Upgrade tokamak. The plasma is refuelled by injection of frozen deuterium pellets and ELMs are mitigated by external resonant magnetic perturbations (RMPs). In this experiment relevant dimensionless paramete…
Preprint PublishedY. Liu D. Ryan A. Kirk L. Li W. Suttrop M. Dunne R. Fischer J.C. Fuchs B. Kurzan P. Piovesan M. Willensdorfer The ASDEX Upgrade team The EUROfusion MST1 team
The plasma response to the vacuum resonant magnetic perturbation (RMP) fields, produced by the ELM control coils in ASDEX Upgrade experiments, is computationally modelled using the MARS-F/K codes [Liu Y.Q. et al 2000 Phys. Plasmas 7 3681; Liu Y.Q. et al 2008 Phys. Plasmas 15 112503]. A systematic investigation is carried out, considering various pl…
Preprint PublishedA. Kirk W. Suttrop I.T. Chapman Yueqiang Liu R. Scannell A.J. Thornton L. Barrera Orte P. Cahyna T. Eich R. Fischer C. Fuchs C. Ham J.R. Harrison MW. Jakubowski B. Kurzan S. Pamela M. Peterka D. Ryan S. Saarelma B. Sieglin M. Valovic M Willensdorfer MAST and ASDEX Upgrade Teams
Sustained Edge Localised Mode (ELM) mitigation has been achieved on MAST and AUG using RMPs with various toroidal mode numbers over a wide range of low to medium collisionality discharges. The ELM energy loss and peak heat loads at the divertor targets have been reduced. The ELM mitigation phase is typically associated with a drop in plasma density…
Preprint PublishedA. Loving O. Crofts N. Sykes D. Iglesias M. Coleman J. Thomas J. Harman U. Fischer J. Sanz M. Siuko M. Mittwollen Et.Al.
EDFA, as part of the Power Plant Physics and Technology programme, has been working on the pre-conceptual design of a Demonstration Power Plant (DEMO). As part of this programme, a review of the remote maintenance strategy considered maintenance solutions compatible with expected environmental conditions, whilst showing potential for meeting the pl…
PublishedU. Fischer P. Batistoni R. Forrest C. Konno R.L. Perel K. Seidel S.P. Simakov
An overview is presented of the nuclear data required for nuclear design analyses of fusion technology focusing on ITER, the International Thermonuclear Experimental Reactor, and IFMIF, the International Fusion Materials Irradiation Facility. The status of the available data evaluations and libraries is reviewed with regard to the required material…
Published- 1
- 2