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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

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NF
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POP
RSI

年別論文数推移

高精度マッチ高精度50件

Rail deployment and storage procedure and test for ITER blanket remote maintenance
S Kakudate, K ShibanumaFusion Engineering and Design2003
高精度タイトル一致
Divertor issues on ITER and extrapolation to reactors
Andrei S Kukushkin, Horst D Pacher, Gianfranco Federici, Günter Janeschitz, Guenther W PacherFusion Engineering and Design2003
高精度タイトル一致
The effects of grain size and helium accumulation on radiation hardening and loss of ductility of pure copper for ITER application
S.A Fabritsiev, A.S PokrovskyFusion 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
Evolution of the ITER project during the CTA
R. Aymar, W.R. Spears, ITER International TeamFusion Engineering and Design2003
高精度タイトル一致
Test results of the ITER toroidal field model coil experiment in the TOSKA facility of the Forschungszentrum Karlsruhe
A Ulbricht, the ITER L2 Project TeamFusion Engineering and Design2003
高精度タイトル一致
Development of active control systems on ASDEX upgrade in view of ITER discharge scenarios
V. Mertens, J. Hobirk, A. Kallenbach, P. Lang, H. ZohmFusion Engineering and Design2003
高精度タイトル一致
European contribution to the development of the ITER divertor
Mario Merola, W. Dänner, J. Palmer, G. Vielder, C.H. WuFusion Engineering and Design2003
高精度タイトル一致
3-D simulation of macroscopic erosion of CFC under ITER off-normal heat loads
S. Pestchanyi, H. WuerzFusion Engineering and Design2003
高精度タイトル一致
Experimental optimisation of a hypervapotron® concept for ITER plasma facing components
Frédéric Escourbiac, J. Schlosser, M. Merola, I. Bobin VastraFusion Engineering and Design2003
高精度タイトル一致
Progress on fatigue characterization of ITER primary first wall mock-ups
G. Dell'Orco, P. Lorenzetto, I. Alessandrini, G. Bernardi, G. VenturiFusion Engineering and Design2003
高精度タイトル一致
Behaviour of the PFC tiles on the ITER divertor under critical loading conditions
Elio D'Agata, S Grigoriev, G Federici, C Ibbott, R TiveyFusion Engineering and Design2003
高精度タイトル一致
Manufacturing of prototype components for the ITER divertor baffle
I. Bobin Vastra, B. Schedler, M. Merola, F. Jacquinot, Y. LeblancFusion Engineering and Design2003
高精度タイトル一致
Manufacture of two primary first wall panel prototypes with Beryllium armor for ITER
C Boudot, I Bobin-Vastra, P Lorenzetto, D Conchon, M FebvreFusion Engineering and Design2003
高精度タイトル一致
Ultrasonic studies on ITER divertor and first wall prototype modules
J. Pitkänen, P. Kauppinen, H. Jeskanen, S. Tähtinen, S. SandlinFusion Engineering and Design2003
高精度タイトル一致
Summary review of aspects of the engineering of ITER divertor PFC-to-cassette attachments
A.D McCallum, J PalmerFusion Engineering and Design2003
高精度タイトル一致
Erosion products of ITER divertor materials under plasma disruption simulation
M.I. Guseva, V.M. Gureev, B.N. Kolbasov, S.N. Korshunov, V.I. VasilievFusion Engineering and Design2003
高精度タイトル一致
Magnum-psi, a new linear plasma generator for plasma-surface interaction studies in ITER relevant conditions
B. de Groot, Z. Ahmad, R.P. Dahiya, R. Engeln, V. VeremiyenkoFusion Engineering and Design2003
高精度タイトル一致
Application of a diffusion bonding methodology to develop a Be/Cu HIP bond suitable for the ITER blanket
P. Sherlock, A. Erskine, P. Lorenzetto, A.T. PeacockFusion Engineering and Design2003
高精度タイトル一致
The thermophysical and mechanical properties of the copper heat sink material intended for use in ITER
S.D. Preston, I. Bretherton, C.B.A. FortyFusion Engineering and Design2003
高精度タイトル一致
Towards a 2 MW, CW, 170 GHz coaxial cavity gyrotron for ITER
B. Piosczyk, A. Arnold, H. Budig, G. Dammertz, X. YangFusion Engineering and Design2003
高精度タイトル一致
The main microwave components of the LHCD system for ITER
F. Mirizzi, Ph. Bibet, S. KuzikovFusion Engineering and Design2003
高精度タイトル一致
Overview of the ITER-FEAT LH system
Ph. Bibet, F. Mirizzi, P. Bosia, L. Doceul, F. WasasterjnaFusion Engineering and Design2003
高精度タイトル一致
Design study of a test stand for ITER gyrotron
D. Fasel, S. Alberti, T. Bonicelli, R. Cleasen, T. VerhoevenFusion Engineering and Design2003
高精度タイトル一致
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
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