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Alain Durocher
Observed names:
A Durocher,
A. Durocher,
Durocher, A.
Institution:
ITER
Observed institutions:
ITER,
Commissariat à l'Énergie Atomique et aux Énergies Alternatives,
CEA Cadarache,
Institut de Recherche sur la Fusion par confinement Magnétique
OpenAlex ID:
A5046701554
Use of tungsten material for the ITER divertor
2016
·
T. Hirai
, S. Panayotis
, et al.
·
Nuclear Materials and Energy
·
358
PDF
Status of technology R&D for the ITER tungsten divertor monoblock
2014
·
T. Hirai
, F. Escourbiac
, et al.
·
Journal of Nuclear Materials
·
152
Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation
2021
·
J. Bucalossi
, J. Achard
, et al.
·
Nuclear Fusion
·
148
PDF
ITER divertor materials and manufacturing challenges
2017
·
T. Hirai
, V. Barabash
, et al.
·
Fusion Engineering and Design
·
109
ITER full tungsten divertor qualification program and progress
2014
·
T Hirai
, F Escourbiac
, et al.
·
Physica Scripta
·
103
PDF
The use of copper alloy CuCrZr as a structural material for actively cooled plasma facing and in vessel components
2005
·
M. Lipa
, A. Durocher
, et al.
·
Fusion Engineering and Design
·
87
Design optimization of the ITER tungsten divertor vertical targets
2017
·
T. Hirai
, S. Carpentier-Chouchana
, et al.
·
Fusion Engineering and Design
·
79
High heat flux testing of EU tungsten monoblock mock-ups for the ITER divertor
2014
·
P. Gavila
, B. Riccardi
, et al.
·
Fusion Engineering and Design
·
68
Self-castellation of tungsten monoblock under high heat flux loading and impact of material properties
2016
·
S. Panayotis
, T. Hirai
, et al.
·
Nuclear Materials and Energy
·
62
PDF
Status of the ITER full-tungsten divertor shaping and heat load distribution analysis
2014
·
S Carpentier-Chouchana
, T Hirai
, et al.
·
Physica Scripta
·
57
Fracture modes of ITER tungsten divertor monoblock under stationary thermal loads
2017
·
S. Panayotis
, T. Hirai
, et al.
·
Fusion Engineering and Design
·
47
Experimental activity on the definition of acceptance criteria for the ITER divertor plasma facing components
2009
·
F. Escourbiac
, S. Constans
, et al.
·
Fusion Engineering and Design
·
43
Assessment of critical heat flux margins on tungsten monoblocks of the ITER divertor vertical targets
2019
·
F. Escourbiac
, A. Durocher
, et al.
·
Fusion Engineering and Design
·
42
Recent developments toward the use of tungsten as armour material in plasma facing components
2007
·
R. Mitteau
, J.M. Missiaen
, et al.
·
Fusion Engineering and Design
·
39
PDF
New advanced launcher for lower hybrid current drive on Tore Supra
2000
·
Ph Bibet
, G Agarici
, et al.
·
Fusion Engineering and Design
·
36
First analysis of the misaligned leading edges of ITER-like plasma facing units using a very high resolution infrared camera in WEST
2020
·
A. Grosjean
, Y. Corre
, et al.
·
Nuclear Fusion
·
34
PDF
Experience feedback from high heat flux component manufacturing for Tore Supra
2001
·
J. Schlosser
, A. Durocher
, et al.
·
Fusion Engineering and Design
·
34
Development of an original active thermography method adapted to ITER plasma facing components control
2005
·
A. Durocher
, N. Vignal
, et al.
·
Fusion Engineering and Design
·
31
Investigation of steady-state tokamak issues by long pulse experiments on Tore Supra
2009
·
G. Giruzzi
, R. Abgrall
, et al.
·
Nuclear Fusion
·
29
Design, fabrication and testing of an improved high heat flux element, experience feedback on steady state plasma facing components in Tore Supra
1998
·
J Schlosser
, P Chappuis
, et al.
·
Fusion Engineering and Design
·
28
Advanced qualification methodology for actively cooled plasma facing components
2007
·
A. Durocher
, F. Escourbiac
, et al.
·
Nuclear Fusion
·
27
PDF
CuCrZr alloy hot cracking during electron beam welding
2007
·
A. Durocher
, D. Ayrault
, et al.
·
Journal of Nuclear Materials
·
25
ITER-like PAM launcher for Tore Supra's LHCD system
2005
·
J.H. Belo
, Ph. Bibet
, et al.
·
Fusion Engineering and Design
·
25
TORE SUPRA experience of copper chromium zirconium electron beam welding
2002
·
A. Durocher
, M. Lipa
, et al.
·
Journal of Nuclear Materials
·
24
First plasma experiments in Tore Supra with a new generation of high heat flux limiters for RF antennas
2000
·
G Agarici
, B Beaumont
, et al.
·
Fusion Engineering and Design
·
23
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Works count:
76
Citation count:
2,160
H-index:
24
I10-index:
48
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