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1

Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X

Sunn Pedersen, Thomas
2022

Nuclear fusion, 62 (2022) 4, S. 042022 -

OpenAccess

2

Journal Article

Micro-structuring of tungsten for mitigation of ELM-like fatigue

Terra, Alexis
2020

Physica scripta, T171 (2020) S. 014045

Get full text Published on 2020-03-06. Available in OpenAccess from 2021-03-06. Published on 2020-03-06. Available in OpenAccess from 2021-03-06. Get full text

3

Journal Article

Interpretative transport modeling of the WEST boundary plasma: main plasma and light impurities

Gallo, A.
2020

Nuclear fusion, 60 (2020) 12, S. 126048 -

OpenAccess

4

Journal Article

Micro-structured tungsten, a high heat flux pulse proof material

Terra, A.
2020

Nuclear materials and energy, 25 (2020) S. 100789 -

OpenAccess OpenAccess

5

Journal Article

Overview of first Wendelstein 7-X high-performance operation

Klinger, T.
2019

Nuclear fusion, 59 (2019) 11, S. 112004 -

OpenAccess OpenAccess

6

Journal Article

Probe manipulators for Wendelstein 7-X and their interaction with the magnetic topology

RACK, M.
2018

Plasma science & technology, 20 (2018) 5, S. 054002 -

Restricted Restricted OpenAccess

7

Journal Article

Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification

Brezinsek, S.
2017

Nuclear fusion, 57 (2017) 11, S. 116041 -

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 tungsten alloys as a material for the first wall of a future fusion power plant

Litnovsky, A.
2017

Nuclear fusion, 57 (2017) 6, S. 066020 -

10

Journal Article

Plasma-wall interaction of advanced materials

Coenen, J. W.
2017

Nuclear materials and energy, 12 (2017) S. 307-312

OpenAccess OpenAccess

11

Journal Article

Preparation of erosion and deposition investigations on plasma facing components in Wendelstein 7-X

Dhard, C. P.
2017

Physica scripta, 2017 (2017) T170, S. 014010 -

Restricted Restricted OpenAccess OpenAccess

12

Journal Article

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

Coenen, J. W.
2016

Physica scripta, T167 (2016) S. 014002

13

Journal Article

Theoretical investigation of crack formation in tungsten after heat loads

Arakcheev, A. S.
2015

Journal of nuclear materials, 463 (2015) S. 246 - 249

14

Journal Article

Conceptual study of ferromagnetic pebbles for heat exhaust in fusion reactors with short power decay length

Gierse, N.
2015

Nuclear materials and energy, 2 (2015) S. 12 - 19

OpenAccess

15

Journal Article

Investigation of the Impact of Transient Heat Loads Applied by Laser Irradiation on ITER-Grade Tungsten

Huber, Alexander
2014

Physica scripta, T159 (2014) S. 014005

OpenAccess

16

Journal Article

Liquid metals as alternative solution for the power exhaust of future fusion devices: status and perspective

Coenen, J. W.
2014

Physica scripta, T159 (2014) S. 014037

17

Journal Article

Investigation of the Impact on Tungsten of Transient Heat Loads Induced by Laser Irradiation, Electron Beams and Plasma Guns

Huber, A.
2013

Fusion science and technology, 63 (2013) 1T, S. 197 - 200

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