JuLib | Articles & more - {Wirtz, Marius}

1

Journal Article

Mock-ups fabrication by HRP technology with advanced W-alloy monoblocks for DEMO divertor target

Crea, Francesco
2024

Fusion engineering and design, 201 (2024) S. 114232 -

“...Wirtz, Marius...”
OpenAccess

2

Journal Article

Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage

Terentyev, D.
2024

Fusion engineering and design, 200 (2024) S. 114200 -

“...Wirtz, Marius...”

3

Journal Article

Initial experiments to regenerate the surface of plasma-facing components by wire-based laser metal deposition

Tweer, Jannik
2024

Nuclear materials and energy, 38 (2024) S. 101577 -

“...Wirtz, Marius...”
OpenAccess

4

Journal Article

Neutron irradiation effects on the low cycle thermal fatigue performance of first wall mock-ups

Dorow-Gerspach, Daniel
2024

Nuclear materials and energy, 38 (2024) S. 101570 -

“...Wirtz, Marius...”
OpenAccess

5

Journal Article

First thermal fatigue studies of tungsten armor for DEMO and ITER at the OLMAT High Heat Flux facility

Alegre, D.
2024

Nuclear materials and energy, 38 (2024) S. 101615 -

“...Wirtz, Marius...”
OpenAccess OpenAccess

6

Journal Article

Thermal fatigue response of W-EUROFER brazed joints by the application of High Heat Flux loads

Izaguirre, I.
2023

Journal of materials processing technology, 319 (2023) S. 118056 -

“...Wirtz, Marius...”
OpenAccess

7

Journal Article

Tungsten based divertor development for Wendelstein 7-X

Fellinger, Joris
2023

Nuclear materials and energy, 37 (2023) S. 101506 -

“...Wirtz, Marius...”
OpenAccess

8

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 -

“...Wirtz, Marius...”
OpenAccess OpenAccess

9

Journal Article

Bubble Formation in ITER-Grade Tungsten after Exposure to Stationary D/He Plasma and ELM-like Thermal Shocks

Gago, Mauricio
2023

Journal of nuclear engineering, 4 (2023) 1, S. 204 - 212

“...Wirtz, Marius...”
OpenAccess

10

Journal Article

Processing and properties of sintered W/steel-composites for the first wall of future fusion reactor

Ganesh, Vishnu
2023

Journal of nuclear engineering, 4 (2023) 1, S. 177-192

“...Wirtz, Marius...”
OpenAccess

11

Journal Article

Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements

Corre, Yann
2023

Nuclear materials and energy, 34 (2023) S. 101366 -

“...Wirtz, Marius...”
OpenAccess OpenAccess

12

Journal Article

Dependence of tungsten crack behaviors on heat source parameters under transient heat flow

Qu, Miao
2023

Materials science & engineering / A, 874 (2023) S. 145079 -

“...Wirtz, Marius...”

13

Journal Article

Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms

Corre, Y.
2023

Nuclear materials and energy, 37 (2023) S. 101546 -

“...Wirtz, Marius...”
OpenAccess

14

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 -

“...Wirtz, Marius...”
Get full text Published on 2022-03-22. Available in OpenAccess from 2023-03-22.

15

Journal Article

Demonstrating tungsten fiber-reinforced porous-matrix tungsten composites for future fusion application

Mao, Yiran
2022

Nuclear fusion, 62 (2022) 10, S. 106029 -

“...Wirtz, Marius...”
OpenAccess

16

Journal Article

Progress in the Realization of µ-Brush W for Plasma-Facing Components

Dorow-Gerspach, Daniel
2022

Journal of nuclear engineering, 3 (2022) 4, S. 333 - 341

“...Wirtz, Marius...”
OpenAccess

17

Poster

Bubble formation in ITER-grade tungsten after exposure to stationary D/He plasma and ELM like thermal shocks

Gago, Mauricio
2022

“...Wirtz, Marius...”

18

Poster

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

Wirtz, Marius
2022

“...Wirtz, Marius...”

19

Poster

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

Wirtz, Marius
2022

“...Wirtz, Marius...”

20

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 -

“...Wirtz, Marius...”

Narrow Search Results