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1

Journal Article

Erratum to: The 2016 Thermal Spray Roadmap

Vardelle, Armelle
2017

Journal of thermal spray technology, 26 (2017) 5, S. 985 - 986

2

Journal Article

Preparing the future post-mortem analysis of beryllium-based JET and ITER samples by multi-wavelengths Raman spectroscopy on implanted Be, and co-deposited Be

Rusu, M. I.
2017

Nuclear fusion, 57 (2017) 7, S. 076035

3

Journal Article

Development of advanced high heat flux and plasma-facing materials

Linsmeier, Ch.
2017

Nuclear fusion, 57 (2017) 9, S. 092007

OpenAccess OpenAccess

4

Journal Article

Development and analyses of self-passivating tungsten alloys for DEMO accidental conditions

Wegener, Tobias
2017

Fusion engineering and design, 124 (2017) S. 183-186

OpenAccess OpenAccess

5

Journal Article

Overview of the JET results in support to ITER

Litaudon, X.
2017

Nuclear fusion, 57 (2017) 10, S. 102001

OpenAccess

6

Journal Article

Tensile deformation behavior of tungsten fibre-reinforced tungsten composite specimens in as-fabricated state

Gietl, H.
2017

Fusion engineering and design, 124 (2017) S. 396 - 400

OpenAccess OpenAccess

7

Journal Article

Damage and deuterium retention of re-solidified tungsten following vertical displacement event-like heat load

Hamaji, Y.
2017

Nuclear materials and energy, 12 (2017) S. 1303 - 1307

OpenAccess OpenAccess

8

Journal Article

Material testing facilities and programs for PFC testing

Linsmeier, Ch.
2017

Nuclear fusion, 57(9) (2017) S. 092012

OpenAccess OpenAccess

9

Journal Article

Smart alloys for a future fusion power plant: First studies under stationary plasma load and in accidental conditions

Litnovsky, A.
2017

Nuclear materials and energy, 12 (2017) S. 1363-1367

OpenAccess OpenAccess

10

Journal Article

Advanced smart tungsten alloys for a future fusion power plant

Litnovsky, A.
2017

Plasma physics and controlled fusion, 59 (2017) 6, S. 064003 -

11

Journal Article

A fluid-kinetic approach for 3D plasma edge transport in He plasma

Rack, M.
2017

Nuclear fusion, 57 (2017) 5, S. 056011 -

12

Journal Article

Surface morphology of tungsten exposed to helium plasma at temperatures below fuzz formation threshold 1073 K

Sakamoto, Ryuichi
2017

Nuclear fusion, 57 (2017) 1, S. 016040 -

13

Contribution to a conference proceedings
Journal Article

First direct comparative test of single crystal rhodium and molybdenum mirrors for ITER diagnostics

Litnovsky, A.
2017

Fusion engineering and design, 123 (2017) S. 674-677

Restricted Restricted Published on 2017-03-31. Available in OpenAccess from 2019-03-31. Published on 2017-03-31. Available in OpenAccess from 2019-03-31.

14

Journal Article

Nitrogen retention mechanisms in tokamaks with beryllium and tungsten plasma-facing surfaces

Oberkofler, M.
2016

Physica scripta, T167 (2016) S. 014077

15

Journal Article

Chemically deposited tungsten fibre-reinforced tungsten – The way to a mock-up for divertor applications

Riesch, J.
2016

Nuclear materials and energy, 9 (2016) S. 75 - 83

OpenAccess OpenAccess

16

Journal Article

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

17

Journal Article

Modelling deuterium release from tungsten after high flux high temperature deuterium plasma exposure

Grigorev, Petr
2016

Journal of nuclear materials, 481 (2016) S. 181 - 189

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