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1

Journal Article

Tungsten based divertor development for Wendelstein 7-X

Fellinger, Joris
2023

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

“...Richou, M....”
OpenAccess

2

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 -

“...Richou, M....”
OpenAccess

3

Journal Article

Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns

Diez, M.
2023

Nuclear materials and energy, 34 (2023) S. 101399 -

“...Richou, M....”
OpenAccess OpenAccess

4

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

Loewenhoff, Th.
2022

“...Richou, M....”

5

Journal Article

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 -

“...Richou, M....”
OpenAccess

6

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 -

“...Richou, M....”
OpenAccess OpenAccess

7

Journal Article

Technology readiness assessment of materials for DEMO in-vessel applications

Richardson, M.
2021

Journal of nuclear materials, 550 (2021) S. 152906 -

“...Richou, M....”

8

Journal Article

Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST

Corre, Y.
2021

Physica scripta, 96 (2021) 12, S. 124057 -

“...Richou, M....”
OpenAccess

9

Journal Article

Performance assessment of thick W/Cu graded interlayer for DEMO divertor target

Richou, M.
2020

Fusion engineering and design, 157 (2020) S. 111610 -

“...Richou, M....”
Published on 2020-04-28. Available in OpenAccess from 2022-04-28. Published on 2020-04-28. Available in OpenAccess from 2022-04-28.

10

Journal Article

Realization of High Heat Flux Tungsten Monoblock Type Target With Graded Interlayer for Application to DEMO Divertor

Richou, M.
2017

Physica scripta, T170 (2017) S. 014022 -

“...Richou, M....”

11

Starting the WEST platform : testing ITER relevant Plasma Facing Components in a tokamak environment

Tsitrone, E.
2017

“...Richou, M....”

12

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 -

“...Richou, M....”
OpenAccess OpenAccess

13

Journal Article

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

Richou, M.
2016

Physica scripta, T167 (2016) S. 014029 -

“...Richou, M....”

14

Journal Article

Spark Plasma Sintering of Pure and Doped Tungsten as Plasma Facing Material

Autissier, E.
2014

Physica scripta, T159 (2014) S. 014034

“...Richou, M....”

15

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 -

“...Richou, M....”

16

Journal Article

Physico-chemical characteristics of carbon deposits collected in TEXTOR and Tore Supra tokamaks

Richou, M.
2007

Carbon, 45 (2007) S. 2723

“...Richou, M....”

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