JuLib | Articles & more - {"Firdaouss, M."}

1

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 -

“...Firdaouss, M....”
OpenAccess

2

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 -

“...Firdaouss, M....”
OpenAccess OpenAccess

3

Journal Article

Overview of the emissivity measurements performed in WEST: in situ and post-mortem observations

Gaspar, J.
2022

Nuclear fusion, 62 (2022) 9, S. 096023 -

“...Firdaouss, M....”
Get full text Published on 2022-08-25. Available in OpenAccess from 2023-08-25.

4

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 -

“...Firdaouss, M....”
OpenAccess OpenAccess

5

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 -

“...Firdaouss, M....”
OpenAccess

6

Journal Article

Impact of plasma-wall interaction and exhaust on the EU-DEMO design

Maviglia, F.
2021

Nuclear materials and energy, 26 (2021) S. 100897 -

“...Firdaouss, M....”
OpenAccess

7

Journal Article

Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST

Gaspar, J.
2021

Nuclear fusion, 61 (2021) 9, S. 096027 -

“...Firdaouss, M....”
OpenAccess Restricted

8

Journal Article

Infra-red thermography estimate of deposited heat load dynamics on the lower tungsten divertor of WEST

Fedorczak, N.
2020

Physica scripta, T171 (2020) S. 014046 -

“...Firdaouss, M....”
OpenAccess OpenAccess

9

Journal Article

Global scaling of the heat transport in fusion plasmas

Moradi, Sara
2020

Physical review research, 2 (2020) 1, S. 013027

“...Firdaouss, M....”
OpenAccess

10

Poster

Heat flux analysis of Type I ELM impact on a sloped, protruding surface in the JET bulk tungsten divertor

Gaspar, J.
2018

“...Firdaouss, M....”

11

Conference Presentation

Evaluation of beryllium sputtering yields for first wall components in the JET tokamak using the Monte-Carlo code ERO2.0

Romazanov, J.
2017

“...Firdaouss, M....”

12

Journal Article

Thermal analysis of protruding surfaces in the JET divertor

Corre, Y.
2017

Nuclear fusion, 57 (2017) 6, S. 066009 -

“...Firdaouss, M....”

13

Journal Article

Overview of the JET results in support to ITER

Litaudon, X.
2017

Nuclear fusion, 57 (2017) 10, S. 102001

“...Firdaouss, M....”
OpenAccess

14

Journal Article

First ERO2.0 modeling of Be erosion and non-local transport in JET ITER-like wall

Romazanov, J.
2017

Physica scripta, T170 (2017) S. 014018 -

“...Firdaouss, M....”
OpenAccess OpenAccess

15

Journal Article

The DEMO wall load challenge

Wenninger, R.
2017

Nuclear fusion, 57 (2017) 4, S. 046002 -

“...Firdaouss, M....”

16

Poster

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

Tsitrone, E.
2017

“...Firdaouss, M....”

17

Conference Presentation

First application of ERO2.0 to the Be erosion studies at JET ILW

Romazanov, J.
2017

“...Firdaouss, M....”

18

Conference Presentation

ERO2.0 modelling of Be erosion at JET limiters

Romazanov, J.
2016

“... Firdaouss, M....”

19

Journal Article

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

Richou, M.
2016

Physica scripta, T167 (2016) S. 014029 -

“...Firdaouss, M....”

20

Poster

Development of the DEMO Wall Load Specification

Wenninger, R.
2016

“...Firdaouss, M....”

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