A. Litnovsky I. Duran J.W. Coenen Yu. Gasparyan M.R. Gilbert E. Hollmann Ch. Linsmeier S. Nogami C.H. Skinner S. Zinkle
The chapter is devoted to materials used in controlled fusion facilities. Material solutions for magnetic confinement fusion devices and inertial confinement fusion facilities are described. Fusion materials have to preserve their performance often under extremely harsh conditions characterized by intensive particle fluxes, high levels of neutron i…
PurchaseA. Litnovsky F. Klein X. Tan J. Schmitz J. W. Coenen C. Linsmeier J. Gonzalez-Julian M. Bram I. Povstugar T. Morgan Y. M. Gasparyan A. Suchkov D. Bachurina D. Nguyen-Manh M. Gilbert D. Sobieraj J. S. Wróbel P. Bittner A. Reuban
Self-passivating Metal Alloys with Reduced Thermo-oxidation (SMART) are under development for the primary application as plasma-facing materials of the first wall in a fusion DEMOnstration power plant (DEMO). SMART materials must combine the suppressed oxidation in case of an accident and an acceptable plasma performance during the regular operatio…
Preprint PublishedAndrey Litnovsky Janina Schmitza Felix Klein Karen De Lannoyea Sophie Weckauf Arkadi Kreter Marcin Rasinski Jan W. Coenen Christian Linsmeier Jesus Gonzalez-Julian Martin Bram Ivan Povstugar Thomas Morgan Duc Nguyen-Manh Mark Gilbert Damjan Sobieraj Jan S. Wróbel
During an accident with loss-of-coolant and air ingress in DEMO, the temperature of tungsten first wall cladding may exceed 1000oC and remain for months leading to tungsten oxidation. The radioactive tungsten oxide can be mobilized to the environment at rates of 10 – 150 kg per hour. Smart tungsten-based alloys are under develop…
Preprint PublishedD. Iglesias W. Arter I. Balboa P. Bunting C. Challis J.W. Coenen Y. Corre S. Esquembri S. Jachmich K. Krieger G.F. Matthews R.A. Pittsh V. Riccardo M.L. Richiusa M. Porton F. Rimini S. Silburn V.K. Thompson R. Otin D. Valcarcel L. Vitton-Mea Z. Vizvary J. Williams JET contributors
The JET outboard divertor targets are the in-vessel components which receive the largest heat flux density. Surface delamination, radial cracks, and tie rod failures have been observed in the outboard tungsten-coated CFC tiles, while bulk tungsten special lamellas were intentionally melted in dedicated experiments. These different types of damag…
PreprintJ. C. Flanagan M. Sertoli M. Bacharis G. F. Matthews P. C. de Vries A. Widdowson I. H. Coffey G. Arnoux B. Sieglin S. Brezinsek J. W. Coenen S. Marsen T. Craciunescu A. Murari D. Harting A. Cackett E. Hodille JET-EFDA Contributors
Recent studies dedicated to the characterisation of in-vessel dust in JET with the new ITER-like wall (ILW) show that dust levels are orders of magnitude lower compared with the latter stages of the carbon-wall (CW) period and are decreasing with operational time. Less than 1 g of dust was recovered in a recent inspection, compared with more than 2…
Preprint PublishedM-L. Mayoral V. Bobkov A. Czarnecka I. Day A. Ekedahl P. Jacquet M. Goniche R. King K. Kirov E. Lerche J. Mailloux D. Van Eester O. Asunta C. Challis D. Ciric J.W. Coenen L. Colas C. Giroud M. Graham I. Jenkins E. Joffrin T. Jones D.
The major aspects linked to the use of the JET auxiliary heating systems: NBI, ICRF and LHCD, in the new JET ITER-like wall (JET-ILW) are presented. We show that although there were issues related to the operation of each system, efficient and safe plasma heating was obtained with room for higher power. For the NBI up to 25.7MW was safely injected;…
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…
PublishedC. Giroud G.P. Maddison S. Jachmich F. Rimini M. Beurskens I. Balboa S. Brezinsek R. Coelho J.W.Coenen Et Al
This paper reports the impact on confinement and power load of the high-shape 2.5MA ELMy H-mode scenario at JET of a change from an all carbon plasma facing components to an all metal wall. In preparation to this change, systematic studies of power load reduction and impact on confinement as a result of fuelling in combination with nitrogen seeding…
PublishedC. Thomser V. Bailescu S. Brezinsek J. W. Coenen H. Greuner T. Hirai J. Linke C. P. Lungu H. Maier G. Matthews Ph. Mertens R. Neu V. Philipps V. Riccardo M. Rubel C. Ruset A. Schmidt I. Uytdenhouwen JET EFDA Contributors
The chosen materials for plasma facing components for the deuterium/tritium phase of ITER are beryllium and tungsten. These materials have already been widely investigated in various devices like ion beam or electron beam tests. However, the operation of this material combination in a large tokamak including plasma wall interaction, material degrad…
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