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1

Journal Article

Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade

Krieger, K.
2020

Physica scripta, T171 (2020) S. 014037 -

Published on 2020-03-04. Available in OpenAccess from 2021-03-04. Restricted Restricted

2

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

3

Journal Article

Overview of first Wendelstein 7-X high-performance operation

Klinger, T.
2019

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

OpenAccess OpenAccess

4

Journal Article

Μicro-Structured Tungsten: an AdvancedPplasma-Facing Material

Terra, A.
2019

Nuclear materials and energy, 19 (2019) S. 7 - 12

OpenAccess OpenAccess

5

Journal Article

High Pulse Numbe Thermal Shock Testing of Tungsten Alloys Produced by Powder Injection Molding

Loewenhoff, Th.
2019

Nuclear materials and energy, 20 (2019) S. 100680

OpenAccess OpenAccess

6

Journal Article

Major results from the first plasma campaign of the Wendelstein 7-X stellarator

Wolf, R. C.
2017

Nuclear fusion, 57 (2017) 10, S. 102020 -

OpenAccess OpenAccess

7

Journal Article

High Pulse Number transient heat loads on beryllium

Spilker, B.
2017

Nuclear materials and energy, 12 (2017) S. 1184 - 1188

OpenAccess OpenAccess

8

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 -

9

Journal Article

Evolution of Plastic Deformation in Heavily Deformed and Recrystallized Tungsten of ITER Specification Studied by TEM

Dubinko, A.
2017

International journal of refractory metals & hard materials, 66 (2017) S. 105 - 115

10

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

11

Journal Article

Overview of progress in European medium sized tokamaks towards an integrated plasma-edge/wall solution

Eich, T.
2017

Nuclear fusion, 57 (2017) 10, S. 102014

OpenAccess OpenAccess

12

Journal Article

The WEST project: validation program for WEST tungsten coated plasma facing components

Richou, M.
2016

Physica scripta, T167 (2016) S. 014029 -

13

Journal Article

Thermal Shock Behaviour of H and H/He-Exposed Tungsten at High Temperature

Lemahieu, N.
2016

Physica scripta, T167 (2016) S. 014008

14

Book
Dissertation / PhD Thesis

Influence of Impurities on the Fuel Retention in Fusion Reactors

Reinhart, Michael
2015

OpenAccess OpenAccess

15

Journal Article

Synergistic Effects of ELMs and Steady State H and H/He Irradiation on Tungsten

Lemahieu, Nathan
2015

Fusion engineering and design, 98-99 (2015) S. 2020 - 2024

16

Conference Presentation

Interpretation of partially detached divertor operation with and without impurity seeding in JET with EDGE2D-EIRENE

Järvinen, A.
2015

OpenAccess OpenAccess

17

Journal Article

Scaling of divertor power footprint width in RF-heated type-III ELMy H-mode on the EAST superconducting tokamak

Wang, L.
2014

Nuclear fusion, 54 (2014) 11, S. 114002 -

18

Journal Article

Overview of physics results from the conclusive operation of the National Spherical Torus Experiment

Sabbagh, S. A.
2013

Nuclear fusion, 53 (2013) 10, S. 104007 -

19

Journal Article

Retractable tube design issues in ITER CXRS UPP #3

Baross, T.
2013

Fusion engineering and design, 88 (2013) 6-8, S. 1352 - 1356

20

Journal Article

Science and technology research and development in support to ITER and the Broader Approach at CEA

Bécoulet, A.
2013

Nuclear fusion, 53 (2013) 10, S. 104023 -

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