Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Flavien Sabourin"'
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, Elsevier, 2021, 173, pp.112834. ⟨10.1016/j.fusengdes.2021.112834⟩
Fusion Engineering and Design, 2021, 173, pp.112834. ⟨10.1016/j.fusengdes.2021.112834⟩
Fusion Engineering and Design, Elsevier, 2021, 173, pp.112834. ⟨10.1016/j.fusengdes.2021.112834⟩
Fusion Engineering and Design, 2021, 173, pp.112834. ⟨10.1016/j.fusengdes.2021.112834⟩
International audience; The ITER machine has been classified as a Basic Nuclear Installation French nuclear regulator (INB n°174), which implies that it will be the first fusion reactor to go through complete French nuclear licencing. The combinatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::54930b666690c08099eee9d60b658d4e
https://hal.archives-ouvertes.fr/hal-03326811/file/Paper_V4.0_Thermomechanical_behavior_model.pdf
https://hal.archives-ouvertes.fr/hal-03326811/file/Paper_V4.0_Thermomechanical_behavior_model.pdf
Autor:
Nam Il Her, Terenig Arzoumanian, Chang Hyun Noh, Kwanwoo Nam, Flavien Sabourin, Chang Ho Choi, Dongkwon Kang, Naresh Gupta, Manoj Panchal, Germán Pérez-Pichel, J.-M. Martinez, Shyam P. Singh
Publikováno v:
Fusion Engineering and Design. 146:2302-2306
This paper aims to provide a comprehensiveness description of the ITER Thermal Shield thermal integrity management keeping focused on the methods required for supporting the Thermal Shield manufacturing and assembly phases. Three main aspects are cov
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b671f6e7e9b6e5ac626ae04593a7370
https://doi.org/10.1016/j.fusengdes.2019.03.177
https://doi.org/10.1016/j.fusengdes.2019.03.177
Autor:
N. Gupta, Namil Her, G. Perez Pichel, Flavien Sabourin, J.B. Layly, Chang-Hwan Choi, D. Patel, Terenig Arzoumanian, S.P. Singh, J. Chenard, J.-M. Martinez
Publikováno v:
Fusion Engineering and Design. 138:239-246
The role of the ITER Tokamak thermal shield system is to minimize heat loads transferred from the hot tokamak components to the cooled superconducting components. The system consists of two single wall structures fabricated from 304L-(N) stainless st
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fac3ae38cb0a050a615b0536be4d3b1c
https://doi.org/10.1016/j.fusengdes.2018.11.035
https://doi.org/10.1016/j.fusengdes.2018.11.035
Progress status of the ITER Vacuum Vessel sectors manufacturing design thermal hydraulic performance
Autor:
I. Zamora, O. Mata, M. Ichard, Flavien Sabourin, A. Aleman, B. Hermosa, A. Martell, E. Martinez-Saban, J.-M. Martinez, A. Martin, M. Martin, C. Colomer, Alfredo Portone, Joan Caixas, J. Fradera, P. Briani, F. Cau
Publikováno v:
Fusion Engineering and Design. 124:578-581
The present work exposes the 3D steady state thermal hydraulic (TH) analysis of the Irregular Sector number 3 (IrS#3) of the ITER Vacuum Vessel (VV), including the Irregular Field Joints (IrFJ) by means of a commercial CFD (Computational Fluid Dynami
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c0fc40b5d53b18f89f6998bfb6f5bd29
https://doi.org/10.1016/j.fusengdes.2017.03.095
https://doi.org/10.1016/j.fusengdes.2017.03.095
Autor:
A. Terasawa, Y. Utin, E. Popova, C. Sborchia, E. Fernandez, Chang-Hwan Choi, E. Privalova, S. Sfarni, M. Cambazar, Y.G. Kim, Vincent Albin, G. Sannazaro, T. Gaucher, P. Teissier, J.-M. Martinez, José María Zarzalejos, C. Jun, A. Lee, S. Borrelly, Songke Wang, B. Xiang, Shuangsong Du, A. Alekseev, A. Martin, Joan Caixas, H. Kim, Flavien Sabourin
Publikováno v:
Fusion Engineering and Design. :688-692
Some years ago, analyses were performed by ITER Organization Central Team (IO-CT) to verify the structural integrity of the ITER vacuum vessel baseline design fixed in 2010 and classified as a Protection Important Component (PIC). The manufacturing p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3357f9f42544cfee4a2e0733b62c5556
https://doi.org/10.1016/j.fusengdes.2016.02.017
https://doi.org/10.1016/j.fusengdes.2016.02.017
Autor:
Raul Pampin, Flavien Sabourin, E. Polunovskiy, Rafael Juarez, N. Casal, Fernando Mota, Anne Arnould, Fabio Moro, Alejandro Suarez, A. Martin
Publikováno v:
Fusion Engineering and Design. :1408-1411
Mitigation of the neutron environment inside the cryostat, and of the subsequent decay gamma dose field from activated materials, is necessary in order to reduce heating of coils and occupational exposure, thereby facilitating smooth operation and ma
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0a958b91dcd4dc6a672df2c145db1be3
https://doi.org/10.1016/j.fusengdes.2015.12.010
https://doi.org/10.1016/j.fusengdes.2015.12.010
Autor:
Christopher Watts, Jorge E. Gonzalez, S. Gicquel, Gonzalo Martínez, A. Martin, P. Shigin, E. Veshchev, Flavien Sabourin, Roger Reichle, R. Mitteau
Publikováno v:
Fusion Engineering and Design
ITER will have about 50 diagnostic systems for machine protection, plasma control and optimization, and understanding the physics of burning plasma. The implementation in the ITER machine is challenging, particularly for the in-vessel diagnostics, re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5ab4b43579a039735bf3f5af79f20af3
https://doi.org/10.1016/j.fusengdes.2015.06.046
https://doi.org/10.1016/j.fusengdes.2015.06.046
Autor:
Flavien Sabourin, B. Levesy, Matteo Marconi, P.A. Di Maio, Mario Merola, Byoung-Yoon Kim, Rosaria Villari, L. Giancarli, F. Lucca
Publikováno v:
Fusion Engineering and Design. 89:1969-1974
The test blanket module port plug (TBM PP) consists of a TBM frame and two TBM-sets. However, at any time of the ITER operation, a TBM set can be replaced by a dummy TBM. The frame provides a standardized interface with the vacuum vessel (VV)/port st
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fec94035c348f226bb01a86dfebf1a91
https://doi.org/10.1016/j.fusengdes.2014.01.017
https://doi.org/10.1016/j.fusengdes.2014.01.017
Publikováno v:
Fusion Engineering and Design. 89:1324-1329
This paper presents the rationale to the optimization of water distribution in ITER blanket modules, meeting both Blanket System requirements and interface compliance requirements. The key challenging constraints include to: be compatible with the ov
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c652a5a88541350485d2c9dfb76a391e
https://doi.org/10.1016/j.fusengdes.2014.03.002
https://doi.org/10.1016/j.fusengdes.2014.03.002