JuLib | Articles & more

1

Journal Article

Benchmarking by high heat flux testing of W-steel joining technologies

Dorow-Gerspach, D.
2023

Nuclear materials and energy, 37 (2023) S. 101508 -

OpenAccess OpenAccess

2

Poster

Current status of experiments with pre-damaged tungsten divertor PFUs in WEST

Loewenhoff, Th.
2022

3

Journal Article

Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys

Terentyev, D.
2022

Nuclear fusion, 62 (2022) 2, S. 026045 -

4

Poster

High heat flux testing results of various W-FGM-steel joints

Ganesh, Vishnu
2022

OpenAccess

5

Journal Article

Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

Bucalossi, J.
2022

Nuclear fusion, 62 (2022) 4, S. 042007 -

OpenAccess OpenAccess

6

Journal Article

First plasma exposure of a pre-damaged ITER-like plasma-facing unit in the WEST tokamak: procedure for the PFU preparation and lessons learned

Richou, Marianne
2022

Nuclear fusion, 62 (2022) 5, S. 056010 -

Get full text Published on 2022-03-22. Available in OpenAccess from 2023-03-22.

7

Journal Article

Intense cyclic heating effects on thermo-fracture and thermal shock of solid tungsten and open-cell tungsten foam

Ghazari, Arian
2022

Journal of nuclear materials, 565 (2022) S. 153730 -

8

Poster

Comparative Study of Powder Injection Molded Tungsten Alloys Exposed to Synergistic Loads

Wirtz, Marius
2022

9

Journal Article

Materials for in-vessel components

Pintsuk, Gerald
2022

Fusion engineering and design, 174 (2022) S. 112994 -

OpenAccess OpenAccess

10

Poster

Interaction of heat loads and seeding impurities with tungsten using different experimental methods

Wirtz, Marius
2022

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