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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

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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

Remote operational trials with the ITER FDR divertor handling equipment
M. Irving, L. Baldi, G. Benamati, L. Galbiati, E. MartinFusion Engineering and Design2003
高精度タイトル一致
Water hydraulic actuators for ITER maintenance devices
Mikko Siuko, M. Pitkäaho, A. Raneda, J. Poutanen, M. VileniusFusion Engineering and Design2003
高精度タイトル一致
ITER hot cell
O. Asuar, V. Baulo, T. Fisher, R. Haange, H. YoshidaFusion Engineering and Design2003
高精度

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

タイトル一致
AM laser system (IVVS) for the ITER in vessel viewing and ranging
A. Coletti, L. Bartolini, M. Ferri De Collibus, G. Fornetti, C. TalaricoFusion Engineering and Design2003
高精度タイトル一致
Development of a long reach articulated manipulator for ITER in vessel inspection under vacuum and temperature
Y. Perrot, J.J. Cordier, J.P. Friconneau, D. Maisonnier, J.D. PalmerFusion Engineering and Design2003
高精度タイトル一致
Towards advanced welding methods for the ITER vacuum vessel sectors
L.P. Jones, P. Aubert, V. Avilov, F. Coste, M. WykesFusion Engineering and Design2003
高精度タイトル一致
A breeding blanket in ITER-FEAT
Claudio Nardi, Luigi Petrizzi, Giovanni PiazzaFusion Engineering and Design2003
高精度タイトル一致
Design of parallel intersector weld/cut robot for machining processes in ITER vacuum vessel
Huapeng Wu, Heikki Handroos, Janne Kovanen, Asko Rouvinen, Lawrence JonesFusion Engineering and Design2003
高精度タイトル一致
On the nuclear response of the water-cooled Pb–17Li test blanket module for ITER-FEAT
P Chiovaro, P.A Di Maio, E Oliveri, G VellaFusion Engineering and Design2003
高精度タイトル一致
Waste management within the framework of ITER in Cadarache
S. Rosanvallon, S. Nordlinder, L. Fayette, G. BrunelFusion Engineering and Design2003
高精度タイトル一致
ITER site selection studies in Spain
M. Medrano, C. Alejaldre, J. Doncel, A. Garcı́a, F. AlbisuFusion Engineering and Design2003
高精度タイトル一致
Canada's offer to host the ITER project
Robert Keith RaeFusion Engineering and Design2003
高精度タイトル一致
Japanese site for ITER; Rokkasho
Japanese ITER Site Forum, Hiroshi KishimotoFusion Engineering and Design2003
高精度タイトル一致
MELCOR model of divertor cooling loop and divertor ex-vessel LOCA analysis for the ITER plant
C.H. Sheng, A. SjöbergFusion Engineering and Design2003
高精度タイトル一致
Ex-vessel break in ITER divertor cooling loop analysis with the ECART code
G. Cambi, S. Paci, F. Parozzi, M.T. PorfiriFusion Engineering and Design2003
高精度タイトル一致
Seismic analysis of ITER tokamak including interaction with soil and building
V.M. Sorin, P. Barabaschi, G. SannazzaroFusion Engineering and Design2003
高精度タイトル一致
Shutdown dose evaluation experiment for ITER
Y. Morimoto, K. Ochiai, S. Sato, J. Hori, T. NishitaniFusion Engineering and Design2003
高精度タイトル一致
Final disposal possibilities of radioactive waste components from ITER
K. Brodén, G. OlssonFusion Engineering and Design2003
高精度タイトル一致
Extension of ITER waste assessment
E. Eriksson, J. RaederFusion Engineering and Design2003
高精度タイトル一致
Numerical evaluation of experimental models to investigate the dynamic behavior of the ITER tokamak assembly
M. Onozuka, N. Takeda, M. Nakahira, K. Shimizu, T. NakamuraFusion Engineering and Design2003
高精度タイトル一致
Physics and control of ELMing H-mode negative-central-shear advanced tokamak ITER scenario based on experimental profiles from DIII-D
L.L. Lao, V.S. Chan, M.S. Chu, T. Evans, D.A. Humphreys, J.A. Leuer, M.A. Mahdavi, T.W. Petrie, P.B. Snyder, H.E. St JohnNuclear Fusion2003被引用: 4
高精度タイトル一致
Influence of reflections on the operation of the 2 MW, CW 170 GHz coaxial cavity gyrotron for ITER
M.I. Airila, O. Dumbrajs, P. Kåll, B. PiosczykNuclear Fusion2003被引用: 11
高精度タイトル一致
An ITER-relevant evacuated waveguide transmission system for the JET-EP ECRH project
M.A. Henderson, S. Alberti, J. Bird, J. Doane, B. Elzendoorn, C. Flemming, T.P. Goodman, F. Hoekzema, J.P. Hogge, G. MacMillanNuclear Fusion2003被引用: 10
高精度タイトル一致
Performance of a remote steering antenna for ECRH/ECCD applications in ITER using a four-wall corrugated square waveguide
W. Kasparek, G. Gantenbein, B. Plaum, R. Wacker, A.V. Chirkov, G.G. Denisov, S.V. Kuzikov, K. Ohkubo, F. Hollmann, D. WagnerNuclear Fusion2003被引用: 32
高精度タイトル一致
Core plasma operation consistent with SOL parameters in ITER
G.W. Pacher, H.D. Pacher, A.S. Kukushkin, G. Janeschitz, G. PereverzevNuclear Fusion2003被引用: 21
高精度タイトル一致
Heating, current drive and energetic particle studies on JET in preparation of ITER operation
J.-M. Noterdaeme, R. Budny, A. Cardinali, C. Castaldo, R. Cesario, F. Crisanti, J. deGrassie, D.A. D'Ippolito, F. Durodié, A. EkedahlNuclear Fusion2003被引用: 11
高精度タイトル一致
Design improvements and R&D achievements for vacuum vessel and in-vessel components towards ITER construction
K. Ioki, P. Barabaschi, V. Barabash, S. Chiocchio, W. Daenner, F. Elio, M. Enoeda, A. Gervash, C. Ibbott, L. JonesNuclear Fusion2003被引用: 25
高精度タイトル一致
The ITER magnets: preparation for full size construction based on the results of the model coil programme
M. Huguet, the ITER International Team and Participant TeamsNuclear Fusion2003被引用: 8
高精度タイトル一致
Irradiation test of diagnostic components for ITER application in the Japan Materials Testing Reactor
T. Shikama, T. Nishitani, T. Kakuta, S. Yamamoto, S. Kasai, M. Narui, E. Hodgson, R. Reichle, B. Brichard, A. KrassilinikovNuclear Fusion2003被引用: 36
高精度タイトル一致
Scaling laws for edge plasma parameters in ITER from two-dimensional edge modelling
A.S. Kukushkin, H.D. Pacher, G.W. Pacher, G. Janeschitz, D. Coster, A. Loarte, D. ReiterNuclear Fusion2003被引用: 115
高精度タイトル一致
Comparison of ITER performance predicted by semi-empirical and theory-based transport models
V. Mukhovatov, Y. Shimomura, A. Polevoi, M. Shimada, M. Sugihara, G. Bateman, J.G. Cordey, O. Kardaun, G. Pereverzev, I. VoitsekhovichNuclear Fusion2003被引用: 44
高精度タイトル一致
Status of ITER
R AymarFusion Engineering and Design2002
高精度タイトル一致
The ITER design
R Aymar, P Barabaschi, Y ShimomuraPlasma Physics and Controlled Fusion2002
高精度タイトル一致
Impurity production and edge plasma pollution during ITER-FEAT ELMs
S E Pestchanyi, H Würz, I S LandmanPlasma Physics and Controlled Fusion2002
高精度タイトル一致
A new optimized design concept of the switching network resistors of the large ITER-FEAT tokamak
B. Bareyt, S. BulgakovFusion Engineering and Design2002
高精度タイトル一致
Copper vapor laser application for surface monitoring of divertor and first wall in ITER
O.I. Buzhinskij, N.N. Vasiliev, A.I. Moshkunov, I.A. Slivitskaya, A.A. SlivitskyFusion Engineering and Design2002
高精度タイトル一致
A high-data-transfer-rate VME system for TCP-IP remote real-time control of the ITER in-vessel vision system
Rita Pereira, Nuno Cruz, Carlo Neri, Carlos Correia, Carlos VarandasFusion Engineering and Design2002
高精度タイトル一致
Erosion of plasma-facing components in ITER
G. Federici, H. Wuerz, G. Janeschitz, R. TiveyFusion Engineering and Design2002
高精度タイトル一致
Design and manufacturing of the ITER limiter
A. Cardella, K. Skladnov, K. Ioki, H. Pacher, W. DaennerFusion Engineering and Design2002
高精度タイトル一致
Thermal–mechanical test on ITER primary first wall mock-ups
G Dell'Orco, P Lorenzetto, A Malavasi, G Polazzi, D ZitoFusion Engineering and Design2002
高精度タイトル一致
Manufacturing and testing of large-scale mock-ups of ITER plasma facing components in Russia
V Belyakov, I Mazul, Yu StrebkovFusion Engineering and Design2002
高精度タイトル一致
Investigation of tungsten alloys as plasma facing materials for the ITER divertor
M. Roedig, W. Kuehnlein, J. Linke, M. Merola, E. ViscaFusion Engineering and Design2002
高精度タイトル一致
Experimental test campaign on an ITER divertor mock-up
G Dell'Orco, A Malavasi, M Merola, G Polazzi, D ZitoFusion Engineering and Design2002
高精度タイトル一致
Design of plasma facing components for the ITER feat divertor
G Mazzone, G Brolatti, E D'Agata, A Iorizzo, G ZanotelliFusion Engineering and Design2002
高精度タイトル一致
ITER Test Blanket Working Group activities: a summary, recommendations and conclusions
V.A Chuyanov, ITER Test Blanket Working GroupFusion Engineering and Design2002
高精度タイトル一致
Design description and performance analyses of the European HCPB test blanket system in ITER feat
L.V Boccaccini, N Bekris, Y Chen, U Fischer, H Tsige-TamiratFusion Engineering and Design2002
高精度タイトル一致
Progress on design and R&D of ITER FW/blanket
K Ioki, M Akiba, A Cardella, W Daenner, M YamadaFusion Engineering and Design2002
高精度タイトル一致
Neutronic and thermal mechanical analyses of ITER-FEAT breeding blanket innovative design
D Aquaro, A Barbini, N Cerullo, R IscaroFusion Engineering and Design2002
高精度タイトル一致
Electromagnetic analysis of electrical connections for ITER blanket module attachment
P Sonato, N Miki, P Testoni, G ZollinoFusion Engineering and Design2002
高精度タイトル一致
Strategy for the blanket testing in ITER
L.V Boccaccini, U Fischer, K Kleefeldt, S Malang, K SchleisiekFusion Engineering and Design2002
高精度タイトル一致
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