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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.

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#核融合184#ITER163#トカマク79#ダイバータ51#プラズマ物理48#JET28#タングステン26#核融合炉25#EAST20#DIII-D19

関連論文数 5,833 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

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

信頼度別論文数

高精度

3,677

低精度

786

中精度

1,370

最新論文

Physics of Plasmas2026

Chaos as the cause of randomness in tearing mode onset times in DIII-D ITER baseline scenario plasmasOpen Access

Kitt Thomas, Laszlo Bardoczi, Kieran Gibson, Ashton C. Brown

Fusion Engineering and Design2026

On the ITER vertical neutron camera stability

A. Zharov, G. Konovalov, G. Nemtsev, P. Reviakin

Fusion Engineering and Design2026

Nuclear Analysis Supporting the Design Optimization of the ITER Radial Gamma-Ray Spectrometer (RGRS)

Rojin Mehrara, Giovanni Mariano, Urszula Wiącek, Alessandro Ciurlino, ... Bruno Coriton

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
The JET high DC power test facility and the life testing of a high current ITER switch
S.R Shaw, T Bonicelli, M Huart, C LescureFusion Engineering and Design2001
高精度タイトル一致
Development program of a 60 kA high temperature superconductor current lead for the ITER toroidal field coils
R Heller, G Friesinger, A.M Fuchs, P Komarek, M VogelFusion Engineering and Design2001
高精度タイトル一致
NbTi superconducting busbars for the ITER TFMC
P Libeyre, P Decool, J.L Duchateau, H Cloez, F BeaudetFusion Engineering and Design2001
高精度タイトル一致
Irradiation and mechanical testing of ITER relevant magnet insulation
H Fillunger, H Gerstenberg, K Humer, R.K Maix, N WiegnerFusion Engineering and Design2001
高精度タイトル一致
ITER-FEAT central solenoid structural analysis and fatigue life assessment
M Verrecchia, D Bessette, N Mitchell, Y KrivchenkovFusion Engineering and Design2001
高精度タイトル一致
Test program preparations of the ITER toroidal field model coil (TFMC)
J.L Duchateau, H Fillunger, S Fink, R Heller, R ZaninoFusion Engineering and Design2001
高精度タイトル一致
Key features of the ITER-FEAT magnet system
K Okuno, D Bessette, M Ferrari, M Huguet, E ZapretilinaFusion Engineering and Design2001
高精度タイトル一致
Completion of the ITER toroidal field model coil
R.K Maix, H Fillunger, F Hurd, E Salpietro, N ValleFusion Engineering and Design2001
高精度タイトル一致
The ITER-FEAT toroidal field structures
C.T.J. Jong, N. Mitchell, C. SborchiaFusion Engineering and Design2001
高精度タイトル一致
ITER TF model coil assembly, commissioning and instrumentation
F.H Hurd, H Fillunger, G Zahn, A Ulbricht, F BeaudetFusion Engineering and Design2001
高精度タイトル一致
The thermal shields for the ITER magnet system: thermal, structural and assembly aspects
V Bykov, A Nishikawa, G Dalle Carbonare, A Alekseev, M NakahiraFusion Engineering and Design2001
高精度タイトル一致
Design of the ITER–FEAT cryoplant to achieve stable operation over a wide range of experimental parameters and operation scenarios
G Claudet, V Kalinine, N Mitchell, P Roussel, N ShatilFusion Engineering and Design2001
高精度タイトル一致
Pressure drop and helium inlet in ITER CS1 conductor
Pierluigi BruzzoneFusion Engineering and Design2001
高精度タイトル一致
Numerical simulation of welds of thick steel sheets for some experimental models towards ITER TF coil case
B Carmignani, G Toselli, S Interlandi, F Lucca, A MarinFusion Engineering and Design2001
高精度タイトル一致
Structural analysis and verification of the ITER TF model coil test conditions
S Raff, P Schanz, H Fillunger, B GlaßlFusion Engineering and Design2001
高精度タイトル一致
Manufacture of full scale models of the ITER Toroidal Field coil cases
G Bevilacqua, L Borin, G Durix, F Fusari, C SborchiaFusion Engineering and Design2001
高精度タイトル一致
Irradiation effects on the fatigue behaviour of an ITER candidate magnet insulation material in tension and interlaminar shear
P Rosenkranz, K Humer, H.W Weber, E.R HodgsonFusion Engineering and Design2001
高精度タイトル一致
New operational aspects of the ITER-FEAT primary vacuum pumping system
Chr Day, H Haas, A Mack, D.K MurdochFusion Engineering and Design2001
高精度タイトル一致
A mock-up of a tritium pellet injector for ITER
I Viniar, G Saksaganskii, S Skoblikov, I Krasilnikov, S PimanikhinFusion Engineering and Design2001
高精度タイトル一致
The tritium fuel cycle of ITER-FEAT
M Glugla, A Busigin, L Dörr, R Haange, H YoshidaFusion Engineering and Design2001
高精度タイトル一致
First operation experiences with ITER-FEAT model pump
A Mack, Chr Day, H Haas, D.K Murdoch, P SchummerFusion Engineering and Design2001
高精度タイトル一致
Experimental validation of main components of the Tokamak exhaust process for ITER-FEAT
R Lässer, M Glugla, K Günther, T.L Le, K.H SimonFusion Engineering and Design2001
高精度タイトル一致
ITER vacuum pumping and leak detection systems
P Ladd, A Antipenkov, G Janeschitz, R MarrsFusion Engineering and Design2001
高精度タイトル一致
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