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ITER

ITER

Cadarash, France

ITER (""The Way"" in Latin) is one of the most ambitious energy projects in the world today.

ITERの研究史を読む公式サイト

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#核融合232#ITER189#トカマク92#ダイバータ57#プラズマ物理48#JET37#タングステン31#核融合炉25#EAST25#DIII-D20

関連論文数 5,884 件

装置分析

ジャーナル別論文数

FED
NF
PPCF
POP
RSI

年別論文数推移

高精度マッチ高精度50件

Influence of radiation on insulation gas at the ITER–NBI system
Yukio Fujiwara, Takashi Inoue, Kenji Miyamoto, Naoki Miyamoto, Kazuhiro WatanabeFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Executive Summary: Introduction
T. MizoguchiFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Executive Summary: Design Overview
R. AymarFusion Engineering and Design2001
高精度タイトル一致

信頼度別論文数

高精度

3,700

低精度

794

中精度

1,390

最新論文

Fusion Engineering and Design2026

Allowable misalignment tolerances for the ITER actively cooled tungsten first wall under edge heat loads

M.L. Richiusa, S. Nicolici, R. Hunt, S. Carpentier-Chouchana

Plasma Physics and Controlled Fusion2026

Dynamics of ion temperature gradient modes in burning plasma conditions in the presence of energetic particles

R Ivanov, A Biancalani, A Bottino, D Gossard, T Hayward-Schneider, A Mishchenko, R Wu

Plasma Physics and Controlled Fusion2026

Angular emission of scintillators for nuclear fusion diagnostics

Mauricio Rodríguez-Ramos, Javier González-Martín, Micaela Videla-Trevin, Alex Reyner-Viñolas, Pablo Alvarez-Frau, Martin Kocan, Javier García-López

ITER R&D: Executive Summary: R&D Overview
T. MizoguchiFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Executive Summary: Concluding Remarks
T. MizoguchiFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Magnets: Introduction
T. Mizoguchi, N. MitchellFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Magnets: Conductor and Joint Development
H Tsuji, S Egorov, J Minervini, N Mitchell, E SalpietroFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Magnets: Central Solenoid Model Coil
H Tsuji, S Egorov, J Minervini, M Martovetsky, R.J ThomeFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Magnets: Toroidal Field Model Coil
N Mitchell, E SalpietroFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Vacuum Vessel and In-vessel Components: Introduction
T. MizoguchiFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Vacuum Vessel and In-vessel Components: Vacuum Vessel
K. Koizumi, L. Jones, V. Krylov, D.E. Nelson, M. OnozukaFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Vacuum Vessel and In-Vessel Components: Shield Blanket Module
W. Dänner, A. Cardella, K. Ioki, R. Mattas, Y. StrebkovFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Vacuum Vessel and In-Vessel Components: Divertor Cassette
R. Tivey, M. Akiba, D. Driemeyer, I. Mazul, M. UlricksonFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Vacuum Vessel and In-vessel Components: Materials Development and Test
G Kalinin, V Barabash, S Fabritsiev, H Kawamura, S ZinkleFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Remote Handling Systems: Introduction
T. MizoguchiFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Remote Handling Systems: Blanket Remote Handling Systems
K. Shibanuma, T. HondaFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Remote Handling Systems: Divertor Remote Handling Systems
D. Maisonnier, E. Martin, J.D. PalmerFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Auxiliary Systems: Introduction
T. MizoguchiFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Auxiliary Systems: Ion Cyclotron Heating and Current Drive System
G. Bosia, R. Kock, D.W. SwainFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Auxiliary Systems: Electron Cyclotron Heating and Current Drive System
T Imai, N Kobayashi, R Temkin, M Thumm, V AlikaevFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Auxiliary Systems: Neutral Beam Heating and Current Drive System
T Inoue, R Hemsworth, V Kulygin, Y OkumuraFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Auxiliary Systems: Fuelling and Vacuum Pumping System
P. Ladd, M.J. Gouge, D. Murdoch, G.L. SaksaganskiyFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Auxiliary Systems: Tritium Systems
H. Yoshida, D. Murdoch, M. Nishi, V. Tebus, S. WillmsFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Auxiliary Systems: Coil Power Supply Components
P.L. Mondino, T. Bonicelli, V. Kuchinskiy, A. RoshalFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Auxiliary Systems: Plasma Diagnostics
A.E Costley, D.J Campbell, S Kasai, K.E Young, V ZaveriaevFusion Engineering and Design2001
高精度タイトル一致
ITER R&D: Auxiliary Systems: Safety Related R&D
C. Gordon, W. Gulden, B. Kolbasov, D. Petti, K. TakaseFusion Engineering and Design2001
高精度タイトル一致
Manufacturing and maintenance technologies developed for a thick-wall structure of the ITER vacuum vessel
M. Onozuka, J.P. Alfile, Ph. Aubert, J.-F. Dagenais, G. SchreckFusion Engineering and Design2001
高精度タイトル一致
Tritium contamination and decontamination study on materials for ITER remote handling equipment
Yasuhisa Oya, Kazuhiro Kobayashi, Wataru Shu, Takeshi Higashijima, Kouichi KoizumiFusion Engineering and Design2001
高精度タイトル一致
DEMO blanket testing in ITER. Influence on reaching DEMO
G ShatalovFusion Engineering and Design2001
高精度タイトル一致
First test results for the ITER central solenoid model coil
T. Kato, H. Tsuji, T. Ando, Y. Takahashi, R. MaixFusion Engineering and Design2001
高精度タイトル一致
European achievements for ITER high heat flux components
M Merola, G Vieider, M Bet, I Bobin Vastra, C.H WuFusion Engineering and Design2001
高精度タイトル一致
Progress of the European R&D on plasma–wall interactions, neutron effects and tritium removal in ITER plasma facing materials
C.H. Wu, C. Alessandrini, J.P. Bonal, J.W. Davis, H. WürzFusion Engineering and Design2001
高精度タイトル一致
Improvements in the design and manufacture of the ITER FEAT first wall towards cost minimization
A. Cardella, F. Elio, K. Ioki, T. Osaki, Y. OharaFusion Engineering and Design2001
高精度タイトル一致
Tests on the integration of the ITER divertor dummy armour prototype on a simplified model of cassette body
G Dell'Orco, A Canneta, G Cattadori, G.P Gaspari, D ZitoFusion Engineering and Design2001
高精度タイトル一致
ITER glow discharge cleaning system
A.B Antipenkov, P Ladd, R MarrsFusion Engineering and Design2001
高精度タイトル一致
Design of a welded box divertor cassette for ITER FEAT
L Petrizzi, G Brolatti, A Dal Santo, F Lucca, G VieiderFusion Engineering and Design2001
高精度タイトル一致
Overview of the engineering design of ITER divertor
C Ibbott, S Chiocchio, E D'Agata, G Federici, R TiveyFusion Engineering and Design2001
高精度タイトル一致
Manufacture and first wall joining for an ITER primary wall module prototype: R&D phase with small scale mock-ups
I Bobin-Vastra, M Febvre, P Lorenzetto, Y Bouveret, D ConchonFusion Engineering and Design2001
高精度タイトル一致
Manufacture and first wall joining for an ITER primary wall module prototype: results of a medium scale mock-up manufacturing
M. Febvre, I. Bobin-Vastra, P. Lorenzetto, Y. Bouveret, D. ConchonFusion Engineering and Design2001
高精度タイトル一致
Supply of a prototype component for the ITER divertor baffle
I Bobin-Vastra, M Febvre, B Schedler, L Plöchl, M MerolaFusion Engineering and Design2001
高精度タイトル一致
Erosion of ITER-FEAT vertical targets during off-normal events
H Würz, S Pestchanyi, V Safronov, F KapplerFusion Engineering and Design2001
高精度タイトル一致
Study of alternative SS/Cu-alloy joining methods for ITER
A Gervash, I Mazul, N YablokovFusion Engineering and Design2001
高精度タイトル一致
Development of negative ion sources for the ITER neutral beam injector
M. Hanada, M. Kashiwagi, T. Morishita, M. Taniguchi, K. WatanabeFusion Engineering and Design2001
高精度タイトル一致
An alternative residual ion dump for the ITER neutral beam system
P Franzen, J Sielanko, R Riedl, E SpethFusion Engineering and Design2001
高精度タイトル一致
Design of neutral beam system for ITER-FEAT
T Inoue, E Di Pietro, M Hanada, R.S Hemsworth, K WatanabeFusion Engineering and Design2001
高精度タイトル一致
Development and design of an ECRF launching system for ITER
K Takahashi, T Imai, K Sakamoto, N Kobayashi, A KasugaiFusion Engineering and Design2001
高精度タイトル一致
Self-field effects in large superconducting cables for ITER
Alexander AnghelFusion Engineering and Design2001
高精度タイトル一致
Circuit analysis and control of the power supply system for the testing of ITER TF model coil
V Marchese, S.M Darweschsad, G Nöther, A Ulbricht, F WüchnerFusion Engineering and Design2001
高精度タイトル一致
The ITER-FEAT power supply system and interface with the site HV power grid
A. Roshal, B. Bareyt, I. Benfatto, N. Britousov, T. ShojiFusion Engineering and Design2001
高精度タイトル一致
Development of ITER-CS model coil terminal assembling by using indium wires
Y Takahashi, T Kato, Y Nunoya, T Ando, H TsujiFusion Engineering and Design2001
高精度タイトル一致
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