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Julio A. Guirao
Observed names:
J Guirao,
J. Guirao,
Julio A. Guirao Guijarro,
Julio Guirao
Observed institutions:
ITER,
Princeton University,
Princeton Plasma Physics Laboratory,
NAITEC Centro Tecnológico
OpenAlex ID:
A5111197850
Innovations in Technology and Science R&D for ITER
2019
·
David J. Campbell
, Tsuyoshi Akiyama
, et al.
·
Journal of Fusion Energy
·
46
Development of design Criteria for ITER In-vessel Components
2013
·
G. Sannazzaro
, V. Barabash
, et al.
·
Fusion Engineering and Design
·
45
Final design of the generic equatorial port plug structure for ITER diagnostic systems
2015
·
V.S. Udintsev
, P. Maquet
, et al.
·
Fusion Engineering and Design
·
30
Use of a new methodology for prediction of weld distortion and residual stresses using FE simulation applied to ITER vacuum vessel manufacture
2009
·
J. Guirao
, E. Rodríguez
, et al.
·
Fusion Engineering and Design
·
28
Final design of the generic upper port plug structure for ITER diagnostic systems
2015
·
Sunil Pak
, Russell Feder
, et al.
·
Fusion Engineering and Design
·
23
Final design of the ITER outer vessel steady-state magnetic sensors
2017
·
M. Kocan
, I. Duran
, et al.
·
Fusion Engineering and Design
·
22
Determination through the distortions analysis of the best welding sequence in longitudinal welds VATS electron beam welding FE simulation
2010
·
J. Guirao
, E. Rodríguez
, et al.
·
Fusion Engineering and Design
·
21
Standardized integration of ITER diagnostics Equatorial Port Plugs
2019
·
J. Guirao
, M.J. Walsh
, et al.
·
Fusion Engineering and Design
·
20
Weld distortion prediction of the ITER Vacuum Vessel using Finite Element simulations
2013
·
Joan Caixas
, Julio Guirao
, et al.
·
Fusion Engineering and Design
·
19
A study of the influence of electron beam welding sequences on the ITER vacuum vessel prototype VATS
2011
·
J. Guirao
, E. Rodríguez
, et al.
·
Fusion Engineering and Design
·
15
FEM simulation of a small EB welded mock-up and new sequence proposed to improve the final distortions
2009
·
J. Guirao
, E. Rodríguez
, et al.
·
Fusion Engineering and Design
·
14
Shutdown dose rate mitigation in the ITER upper ports
2018
·
Aljaž Kolšek
, Rafael Juarez
, et al.
·
Fusion Engineering and Design
·
13
Progress in ITER ECE Diagnostic Design and Integration
2019
·
V.S. Udintsev
, S. Danani
, et al.
·
EPJ Web of Conferences
·
12
PDF
The use of the long modular diagnostics shield module to mitigate shutdown dose rates in the ITER diagnostics equatorial ports
2018
·
R. Juárez
, J. Guirao
, et al.
·
Nuclear Fusion
·
12
Analysis of the effect of the Electron-Beam welding sequence for a fixed manufacturing route using finite element simulations applied to ITER vacuum vessel manufacture
2016
·
Cristina Martín-Menéndez
, Eduardo Rodríguez
, et al.
·
Fusion Engineering and Design
·
12
Progress in ITER ECE diagnostic design and integration
2022
·
Y. Liu
, V.S. Udintsev
, et al.
·
Journal of Instrumentation
·
11
PDF
Integration of ITER diagnostic ports at the Budker institute
2022
·
A. Shoshin
, A. Burdakov
, et al.
·
Fusion Engineering and Design
·
11
Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports
2018
·
R. Juárez
, J. Guirao
, et al.
·
Nuclear Fusion
·
11
PDF
Development of load specifications for the design of ITER diagnostic system and port integration
2017
·
Yuhu Zhai
, Julio Guirao
, et al.
·
Fusion Engineering and Design
·
11
PDF
Electromagnetic analysis of ITER equatorial Wide Angle Viewing System (WAVS) in-vessel components
2021
·
S. Garitta
, C. Portafaix
, et al.
·
Fusion Engineering and Design
·
10
PDF
The European Procurement of Cold Test and Case Insertion of the ITER Toroidal Field Coils
2011
·
E. Barbero
, R. Batista
, et al.
·
IEEE Transactions on Applied Superconductivity
·
10
Neutronic analyses for the equatorial diagnostic port plug #12 in ITER
2023
·
D. Flammini
, A. Chaudhary
, et al.
·
Fusion Engineering and Design
·
9
Integration of diagnostics on ITER
2015
·
M. Walsh
, P. Andrew
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
·
9
Electromagnetic analysis of ITER generic equatorial port plug designs during three plasma current disruption cases
2011
·
J. Guirao
, E. Rodríguez
, et al.
·
Fusion Engineering and Design
·
8
Nuclear analyses for the ITER Diagnostic Equatorial Port 8
2024
·
A. Colangeli
, A. Chaudhary
, et al.
·
Fusion Engineering and Design
·
7
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Works count:
53
Citation count:
519
H-index:
12
I10-index:
21
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