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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

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ジャーナル別論文数

FED
NF
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RSI

年別論文数推移

高精度マッチ高精度50件

Electromechanical analysis of the JET ICRH ITER-like antenna
P. Testoni, F. Durodie, V. Riccardo, P. Sonato, R. WaltonFusion Engineering and Design2003
高精度タイトル一致
In-line magnetic residual ion dump for the ITER neutral beam system
P. Franzen, J. Sielanko, H.P.L. De Esch, E. Speth, R. RiedlFusion Engineering and Design2003
高精度タイトル一致
Accelerator R&D for JT-60U and ITER NB systems
T. Inoue, M. Hanada, T. Iga, T. Imai, T. YamamotoFusion Engineering and Design2003
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
Design and overview of fabrication tests for the 1 MV bushing for ITER NB system
E. Di Pietro, T. Amemiya, M. Hanada, T. Iga, K. WatanabeFusion Engineering and Design2003
高精度タイトル一致
The internal vacuum transmission lines of the ITER-like ICRH antenna project for JET
P Wouters, I Monakhov, F Durodié, F Baity, R WaltonFusion Engineering and Design2003
高精度タイトル一致
The control system of the ITER vertical stabilization converter
E Gaio, R Piovan, V Toigo, I BenfattoFusion Engineering and Design2003
高精度タイトル一致
Study of the radiation induced electromotive force effect on mineral insulated cables for magnetic diagnostics in ITER
R. Van Nieuwenhove, L. VermeerenFusion Engineering and Design2003
高精度タイトル一致
Results of irradiation tests of KU-1 and KS-4V silica glasses as ITER candidate window materials
K.Yu. Vukolov, B.A. LevinFusion Engineering and Design2003
高精度タイトル一致
Radiation resistant alternative substrates for ITER bolometers
M. González, E.R. HodgsonFusion Engineering and Design2003
高精度タイトル一致
Summary, assessment and implications of the ITER model coil test results
N MitchellFusion Engineering and Design2003
高精度タイトル一致
Mechanical behaviour of the ITER toroidal field model coil (TFMC) in the single coil test
S. Raff, P. Schanz, F. Wüchner, H. Fillunger, P. LibeyreFusion Engineering and Design2003
高精度タイトル一致
Analysis of the measurement of the current sharing temperature in the ITER TF Model Coil
C. Marinucci, L. Bottura, P. BruzzoneFusion Engineering and Design2003
高精度タイトル一致
ITER toroidal field model coil test: analysis of heat transfer from plates to conductors
Jean-Luc Duchateau, D. Ciazynski, P. Hertout, S. Nicollet, R. HellerFusion Engineering and Design2003
高精度タイトル一致
Analysis of an unmitigated quench in a poloidal field coil of ITER
R. Meyder, V. PaslerFusion Engineering and Design2003
高精度タイトル一致
The ITER thermal shields for the magnet system: specific design, assembly and structural issues
Yu. Krasikov, V. Bykov, G.Dalle Carbonare, A. Boykov, V. TanchukFusion Engineering and Design2003
高精度タイトル一致
Mechanical response of the ITER toroidal field magnet system during fault conditions
M. Verrecchia, C. JongFusion Engineering and Design2003
高精度タイトル一致
DC behaviour of NbTi cable-in-conduit conductors for ITER-FEAT
Rainer Wesche, B. Stepanov, M. Vogel, T. Gloor, P. BruzzoneFusion Engineering and Design2003
高精度タイトル一致
Optimisation of the reaction heat treatment cycle of internal tin and bronze Nb3Sn strands for ITER
K Hense, H Fillunger, I Kajgana, H Kirchmayr, M MüllerFusion Engineering and Design2003
高精度タイトル一致
Design and manufacture of a prototype NbTi full-size joint sample for the ITER poloidal field coils
P. Decool, D. Ciazynski, P. Libeyre, A. della Corte, D. BressonFusion Engineering and Design2003
高精度タイトル一致
Mechanical attachment of the conductor ends in the ITER poloidal field coils
D. Bessette, P. DecoolFusion Engineering and Design2003
高精度タイトル一致
Influence of reactor irradiation on the mechanical behavior of ITER TF coil candidate insulation systems
K. Bittner-Rohrhofer, K. Humer, H. Fillunger, R.K. Maix, H.W. WeberFusion Engineering and Design2003
高精度タイトル一致
Radiation hardness of newly developed ITER relevant insulation systems
K. Bittner-Rohrhofer, K. Humer, Z.D. Wang, H.W. Weber, N.A. MunshiFusion Engineering and Design2003
高精度タイトル一致
Cold trap and cryogenic molecular sieve adsorber: components for tritium extraction from the purge gas of the HCPB-breeder blanket for ITER
N. Bekris, C. Caldwell-Nichols, E. HutterFusion Engineering and Design2003
高精度タイトル一致
The inner deuterium/tritium fuel cycle of ITER
M. Glugla, R. Lässer, L. Dörr, D.K. Murdoch, H. YoshidaFusion Engineering and Design2003
高精度タイトル一致
EU contribution to ITER CTA fuel cycle design and R&D
D. Murdoch, N. Bekris, J.-C. Boissin, C. Day, A. MackFusion Engineering and Design2003
高精度タイトル一致
Tritium tests with a technical PERMCAT for final clean-up of ITER exhaust gases
B. Bornschein, M. Glugla, K. Günther, R. Lässer, S. WelteFusion Engineering and Design2003
高精度タイトル一致
Performance tests of the ITER model pump
H. Haas, Chr. Day, A. Mack, D.K. MurdochFusion Engineering and Design2003
高精度タイトル一致
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
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