T.L. Martin A.D. Warren D. Kumar A. Siberry R. Springell R. Holmes R. Clark L. Platts R. Burrows C. Harrington M. Gorley E. Surrey S. Rowthu P. Grundler S. Ritter
The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reac…
PreprintU. Kruezi S. Jachmich H.R. Koslowski M. Lehnen S. Brezinsek G. Matthews JET EFDA Contributors
Disruptions, the fast accidental losses of plasma current and stored energy in tokamaks, represent asignificant risk to the mechanical structure as well as the plasma facing components of reactor-scale fusion facilities like ITER. At JET, the tokamak experiment closest to ITER in terms of operating parameters and size, massive gas injection has bee…
Preprint PublishedE. Lerche M. Goniche P. Jacquet D. Van Eester V. Bobkov L. Colas A. Czarnecka S. Brezinsek M.Brix K. Crombe M. Graham M. Groth I. Monakhov T. Mathurin G. Matthews L. Meneses C. Noble V. Petrzilka F. Rimini A. Shaw JET-EFDA Contributors
Recent JET-ILW [1,2] experiments reiterated the importance of tuning the plasma fuelling in order to optimize ion cyclotron resonance frequency (ICRF) heating in high power H-mode discharges. By fuelling the plasma from gas injection modules (GIMs) located in the midplane and on the top of the machine instead of adopting the more standardly used di…
Preprint PublishedE. Lerche M. Goniche P. Jacquet D. Van Eester V. Bobkov L. Colas I. Monakhov F. Rimini A. Czarnecka K. Crombé R. Dumont J. Hobirk Y. Kazakov M.-L. Mayoral L. Meneses J. Mlynar C. Noble I. Nunes J. Ongena V. Petrzilka M. Reich M. Santala
Ion cyclotron resonance frequency (ICRF) heating has been an essential component in the development of high power H-mode scenarios in JET-ILW. The steps that were taken for the successful use of ICRF heating in terms of enhancing the power capabilities and optimizing the heating performance in view of core impurity mitigation in these experiments w…
Preprint PublishedDuc Nguyen-Manh S.L. Dudarev
Properties of point defects resulting from the incorporation of inert-gas atoms in bcc tungsten are investigated systematically using first-principles density functional theory (DFT) calculations. The most stable configuration for the interstitial neon, argon, krypton and xenon atoms is the tetrahedral site, similarly to what was found earlier for …
PublishedD. Van Eester E. Lerche P. Jacquet V. Bobkov A. Czarnecka J. W. Coenen L. Colas K. Crombé M. Graham S. Jachmich E. Joffrin C. C. Klepper V. Kiptily M. Lehnen C. Maggi F. Marcotte G. Matthews M.-L. Mayoral K. McCormick I. Monakhov M. F. F. Nave, R. Neu, C. Noble, J. Ongena, T. Pütterich, F. Rimini, E. R. Solano, G. van Rooij, and JET-EFDA contributors
The most recent JET campaign has focused on characterizing operation with the "ITER-like" wall. One of the questions that needed to be answered is whether the auxiliary heating methods do not lead to unacceptably high levels of impurity influx, preventing fusion-relevant operation. In view of its high single pass absorption, hydrogen minority funda…
PublishedI Monakhov M Graham T Blackman S Dowson F Durodie P Jacquet J Lehmann M-L Mayoral M P S Nightingale C Noble H Sheikh M Vrancken A Walden A Whitehurst E Wooldridge JET-EFDA Contributors
A load-tolerant External Conjugate-T (ECT) impedance matching system for two A2 Ion Cyclotron Resonance Heating (ICRH) antennas has been successfully put into operation at JET. The system allows continuous injection of the RF power into plasma in the presence of strong antenna loading perturbations caused by Edge Localized Modes (ELMs). Reliable EC…
PublishedA.J. Thornton K.J. Gibson J.R. Harrison M. Lehnen R. Martin A. Kirk The Mast Team
Disruptions are of significant concern to future devices, due to the large amount of energy released during the rapid quenching of the plasma. Disruption mitigation has been performed on MAST, to study the effect on heat loads and disruption time scales in a spherical tokamak. Massive gas injection is performed using a disruption mitigation valve c…
Published