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Citation(s) in
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For:
Escourbiac F
, Constans S, Vignal N, Cantone V, Richou M, Durocher A, Riccardi B, Bobin I, Jouvelot J, Merola M.
Experimental activity on the definition of acceptance criteria for the ITER divertor plasma facing components.
Fusion Engineering and Design
2009. [DOI:
10.1016/j.fusengdes.2009.01.072
]
[
Citation(s) in
RCA
: 27
]
[
Impact Index Per Article: 1.8
]
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[Indexed: 10/21/2022]
Number
Cited by Other Article(s)
1
Reception tests of the WEST PFUs using ultrasonic testing and infrared thermography.
NUCLEAR MATERIALS AND ENERGY
2022. [DOI:
10.1016/j.nme.2022.101210
]
[
Citation(s) in
RCA
: 0
]
[
Impact Index Per Article: 0
]
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[Indexed: 11/30/2022]
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2
High heat flux testing for W/Cu monoblock PFUs with varying defects.
FUSION ENGINEERING AND DESIGN
2022. [DOI:
10.1016/j.fusengdes.2022.113137
]
[
Citation(s) in
RCA
: 1
]
[
Impact Index Per Article: 0.5
]
[
Reference Citation Analysis
]
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[Indexed: 11/21/2022]
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3
Assessment of critical heat flux margins on tungsten monoblocks of the ITER divertor vertical targets.
FUSION ENGINEERING AND DESIGN
2019. [DOI:
10.1016/j.fusengdes.2019.03.094
]
[
Citation(s) in
RCA
: 18
]
[
Impact Index Per Article: 3.6
]
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[Indexed: 11/30/2022]
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4
Fabrication route of the ANSALDO-ENEA ITER inner vertical target divertor full scale prototype.
FUSION ENGINEERING AND DESIGN
2019. [DOI:
10.1016/j.fusengdes.2018.12.074
]
[
Citation(s) in
RCA
: 0
]
[
Impact Index Per Article: 0
]
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[Indexed: 11/30/2022]
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5
Fabrication and acceptance of ITER vertical target divertor full scale plasma facing units fabricated by HRP.
FUSION ENGINEERING AND DESIGN
2017. [DOI:
10.1016/j.fusengdes.2017.03.012
]
[
Citation(s) in
RCA
: 4
]
[
Impact Index Per Article: 0.6
]
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[Indexed: 11/27/2022]
Abstract
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6
Nondestructive Testing of EAST W/Cu Divertor Components.
FUSION SCIENCE AND TECHNOLOGY
2017. [DOI:
10.13182/fst13-772
]
[
Citation(s) in
RCA
: 11
]
[
Impact Index Per Article: 1.6
]
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[Indexed: 11/12/2022]
Abstract
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7
Effects of 30 keV Helium Irradiation on (110) Single Crystal Tungsten.
FUSION SCIENCE AND TECHNOLOGY
2017. [DOI:
10.13182/fst13-a18079
]
[
Citation(s) in
RCA
: 6
]
[
Impact Index Per Article: 0.9
]
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[Indexed: 11/12/2022]
Abstract
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8
Developments Toward Fully Metallic Actively Cooled Plasma-Facing Components for the Tungsten Divertor in ITER.
FUSION SCIENCE AND TECHNOLOGY
2017. [DOI:
10.13182/fst13-a24092
]
[
Citation(s) in
RCA
: 2
]
[
Impact Index Per Article: 0.3
]
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[Indexed: 11/12/2022]
Abstract
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9
HRP facility for fabrication of ITER vertical target divertor full scale plasma facing units.
FUSION ENGINEERING AND DESIGN
2015. [DOI:
10.1016/j.fusengdes.2014.12.010
]
[
Citation(s) in
RCA
: 5
]
[
Impact Index Per Article: 0.6
]
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[Indexed: 11/26/2022]
Abstract
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10
Qualification and post-mortem characterization of tungsten mock-ups exposed to cyclic high heat flux loading.
FUSION ENGINEERING AND DESIGN
2013. [DOI:
10.1016/j.fusengdes.2013.05.091
]
[
Citation(s) in
RCA
: 71
]
[
Impact Index Per Article: 6.5
]
[
Reference Citation Analysis
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[Indexed: 11/28/2022]
Abstract
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11
Technological review of the HRP manufacturing process R&D activity.
FUSION ENGINEERING AND DESIGN
2013. [DOI:
10.1016/j.fusengdes.2013.05.031
]
[
Citation(s) in
RCA
: 3
]
[
Impact Index Per Article: 0.3
]
[
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[Indexed: 11/18/2022]
Abstract
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12
A Reliable Technology to Manufacture the ITER Inner Vertical Target.
FUSION SCIENCE AND TECHNOLOGY
2012. [DOI:
10.13182/fst12-a13376
]
[
Citation(s) in
RCA
: 3
]
[
Impact Index Per Article: 0.3
]
[
Reference Citation Analysis
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[Indexed: 11/12/2022]
Abstract
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13
High heat flux testing of mock-ups for a full tungsten ITER divertor.
FUSION ENGINEERING AND DESIGN
2011. [DOI:
10.1016/j.fusengdes.2011.02.012
]
[
Citation(s) in
RCA
: 47
]
[
Impact Index Per Article: 3.6
]
[
Reference Citation Analysis
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[Indexed: 11/29/2022]
Abstract
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14
Fatigue lifetime of repaired high heat flux components for ITER divertor.
FUSION ENGINEERING AND DESIGN
2011. [DOI:
10.1016/j.fusengdes.2011.03.020
]
[
Citation(s) in
RCA
: 15
]
[
Impact Index Per Article: 1.2
]
[
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[Indexed: 11/19/2022]
Abstract
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15
Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing.
FUSION ENGINEERING AND DESIGN
2011. [DOI:
10.1016/j.fusengdes.2011.01.114
]
[
Citation(s) in
RCA
: 58
]
[
Impact Index Per Article: 4.5
]
[
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[Indexed: 11/16/2022]
Abstract
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16
Non-destructive examination with infrared thermography system for ITER divertor components.
FUSION ENGINEERING AND DESIGN
2010. [DOI:
10.1016/j.fusengdes.2010.04.010
]
[
Citation(s) in
RCA
: 16
]
[
Impact Index Per Article: 1.1
]
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[Indexed: 11/24/2022]
Abstract
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17
Manufacturing and testing of reference samples for the definition of acceptance criteria for the ITER divertor.
FUSION ENGINEERING AND DESIGN
2010. [DOI:
10.1016/j.fusengdes.2010.07.008
]
[
Citation(s) in
RCA
: 6
]
[
Impact Index Per Article: 0.4
]
[
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[Indexed: 11/16/2022]
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18
Thermal conductivity and thermal expansion coefficient of diamond/5wt%Si–Cu composite by vacuum hot pressing.
FUSION ENGINEERING AND DESIGN
2010. [DOI:
10.1016/j.fusengdes.2010.08.043
]
[
Citation(s) in
RCA
: 22
]
[
Impact Index Per Article: 1.6
]
[
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[Indexed: 11/17/2022]
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