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41

Contribution to a conference proceedings
Journal Article

Diagnostics and control for the steady state and pulsed tokamak DEMO

Orsitto, F. P.
2016

Nuclear fusion, 56 (2016) 2, S. 026009 -

42

Advanced materials for a damage resilient divertor concept for DEMO: Powder-metallurgical tungsten-fibre reinforced tungsten

Coenen, J. W.
2016

Fusion engineering and design, 124 (2016) S. 964-968

OpenAccess OpenAccess

43

Journal Article

Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants

Neu, R.
2016

Fusion engineering and design, 109-111 (2016) S. 1046 - 1052

44

Journal Article

Development of yttrium-containing self-passivating tungsten alloys for future fusion power plants

Wegener, T.
2016

Nuclear materials and energy, 9 (2016) S. 394 - 398

OpenAccess OpenAccess

45

Journal Article

Materials for DEMO and reactor applications—boundary conditions and new concepts

Coenen, J. W.
2016

Physica scripta, T167 (2016) S. 014002

46

Journal Article

Major aspects of the design of a first mirror for the ITER core CXRS diagnostics

Krasikov, Yury
2015

Fusion engineering and design, 96-97 (2015) S. 812 - 816

47

Journal Article

Mirror Station for studies of the protection of diagnostic mirrors from impurity contamination in ITER: Design and first results

Litnovsky, Andrey
2015

Fusion engineering and design, 96-97 (2015) S. 290 - 293

48

Journal Article

Status of the R&D activities to the design of an ITER core CXRS diagnostic system

Mertens, Philippe
2015

Fusion engineering and design, 96-97 (2015) S. 129 - 135

49

Journal Article

Optimization of tungsten castellated structures for the ITER divertor

Litnovsky, A.
2015

Journal of nuclear materials, 463 (2015) S. 174 - 179

50

Journal Article

Studies of protection and recovery techniques of diagnostic mirrors for ITER

Litnovsky, A.
2015

Nuclear fusion, 55 (2015) 9, S. 093015

51

Journal Article

Preliminary test results on tungsten tile with castellation structures in KSTAR

Hong, Suk-Ho
2014

Fusion engineering and design, 89 (2014) 7-8, S. 1704 - 1708

52

Journal Article

Surface erosion and modification of toughened, fine-grained, recrystallized tungsten exposed to TEXTOR edge plasma

Ueda, Y.
2014

Physica scripta, T159 (2014) S. 014038

53

Journal Article

Estimation of the contribution of gaps to tritium retention in the divertor of ITER

Matveev, D.
2014

Physica scripta, T159 (2014) S. 014063 -

54

Journal Article

Overview of plasma–material interaction experiments on EAST employing MAPES

Ding, Fang
2014

Journal of nuclear materials, 455 (2014) 1-3, S. 710 - 716

55

Journal Article

Influence of particle flux density and temperature on surface modifications of tungsten and deuterium retention

Buzi, Luxherta
2014

Journal of nuclear materials, 455 (2014) 1-3, S. 316 - 319

56

Journal Article

Irradiation of KU1 and KS-4V substrate SiO2 overcoated Al mirrors

Martin, Piedad
2013

Fusion engineering and design, 88 (2013) 6-8, S. 1224 - 1227

57

Journal Article

First studies of ITER-diagnostic mirrors in a tokamak with an all-metal interior: results of the first mirror test in ASDEX Upgrade

Litnovsky, A.
2013

Nuclear fusion, 53 (2013) 7, S. 073033

58

Journal Article

Dust investigations in TEXTOR: Impact of dust on plasma–wall interactions and on plasma performance

Litnovsky, A.
2013

Journal of nuclear materials, 438 (2013) S. S126 - S132

59

Journal Article

Deuterium inventory in Tore Supra: Coupled carbon–deuterium balance

Pégourié, B.
2013

Journal of nuclear materials, 438 (2013) S. S120 - S125

60

Journal Article

Migration of tungsten dust in tokamaks: role of dust–wall collisions

Ratynskaia, S.
2013

Nuclear fusion, 53 (2013) 12, S. 123002 -

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