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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
PPCF
POP
RSI

年別論文数推移

高精度マッチ高精度50件

ITER-FEAT divertor maintenance and integration
E Martin, R Tivey, G Janeschitz, A Antipenkov, C WalkerFusion Engineering and Design2001
高精度タイトル一致
ITER in-vessel components transfer using remotely controlled casks
A Tesini, T Honda, J Palmer, D Maisonnier, K ShibanumaFusion Engineering and Design2001
高精度タイトル一致
Overview of Bore Tools Systems for divertor remote maintenance of ITER
J.-P Friconneau, J.-P Alfille, G Cerdan, C Damiani, M WojtowiczFusion 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
New achievements of the Divertor Test Platform programme for the ITER divertor remote maintenance R&D
C Damiani, L Baldi, L Galbiati, M Irving, N TakedaFusion Engineering and Design2001
高精度タイトル一致
A software environment to execute automatic operational sequences on the ITER-FEAT DTP facility
G Fermani, M ZarfinoFusion Engineering and Design2001
高精度タイトル一致
Modified ITER In-Vessel Viewing System
H Ahola, V Heikkinen, K Keränen, J SuomelaFusion Engineering and Design2001
高精度タイトル一致
Vertical displacement event/disruption electromagnetic analysis for the ITER-FEAT vacuum vessel and in-vessel components
N Miki, M Verrecchia, P Barabaschi, A Belov, Y UtinFusion Engineering and Design2001
高精度タイトル一致
Manufacture of an ITER primary wall module shield prototype by powder hipping
P Lorenzetto, W Daenner, A Lind, H Eriksson, A CardellaFusion Engineering and Design2001
高精度タイトル一致
Assembly of ITER blanket module to vacuum vessel experimental investigations
L.P Jones, Ph Alfilé, C Antonucci, A Cardella, T SchmeskalFusion Engineering and Design2001
高精度タイトル一致
Design and fabrication methods of FW/blanket and vessel for ITER-FEAT
K Ioki, V Barabash, A Cardella, F Elio, H YoshimuraFusion Engineering and Design2001
高精度タイトル一致
Design of blanket cooling manifold system for ITER-FEAT
F Elio, K Ioki, M Yamada, H YoshimuraFusion Engineering and Design2001
高精度タイトル一致
Overview of ITER-FEAT - The future international burning plasma experiment
R. Aymar, V.A. Chuyanov, M. Huguet, Y. Shimomura, ITER Joint Central Team, ITER Home TeamsNuclear Fusion2001被引用: 143
高精度タイトル一致
Overview of JET results in support of the ITER physics basis
JET Team (prepared by C. Gormezano)Nuclear Fusion2001被引用: 16
高精度タイトル一致
Key engineering features of the ITER-FEAT magnet system and implications for the R&D programme
M. Huguet, ITER Joint Central Team, ITER Home TeamsNuclear Fusion2001被引用: 40
高精度タイトル一致
A dimensional extrapolation technique for ITER
P. BarabaschiNuclear Fusion2001被引用: 5
高精度タイトル一致
ITER-FEAT vacuum vessel and blanket design features and implications for the R&D programme
K. Ioki, W. Dänner, K. Koizumi, V.A. Krylov, A. Cardella, F. Elio, M. Onozuka, ITER Joint Central Team, ITER Home TeamsNuclear Fusion2001被引用: 9
高精度タイトル一致
ITER-FEAT operation
Y. Shimomura, R. Aymar, V.A. Chuyanov, M. Huguet, H. Matsumoto, T. Mizoguchi, Y. Murakami, A.R. Polevoi, M. Shimada, ITER Joint Central TeamNuclear Fusion2001被引用: 67
高精度タイトル一致
Neutronics experiments for ITER at JAERI/FNS
C. Konno, F. Maekawa, Y. Kasugai, Y. Uno, J. Kaneko, T. Nishitani, M. Wada, Y. Ikeda, H. TakeuchiNuclear Fusion2001被引用: 7
高精度タイトル一致
The next step in the development of a negative ion beam plasma neutralizer for ITER NBI
V.M. Kulygin, E.D. Dlougach, E.P. Gorbunov, E.Yu. Klimenko, A.A. Mehed'kin, I.V. Moskalenko, A.A. Panasenkov, Yu.M. Pustovoit, A.A. Skovoroda, V.A. SmirnovNuclear Fusion2001被引用: 17
高精度タイトル一致
Progress and achievements of R&D activities for the ITER vacuum vessel
M. Nakahira, H. Takahashi, K. Koizumi, M. Onozuka, K. IokiNuclear Fusion2001被引用: 4
高精度タイトル一致
Progress of the ITER central solenoid model coil programme
H. Tsuji, K. Okuno, R. Thome, E. Salpietro, S. Egorov, N. Martovetsky, M. Ricci, R. Zanino, G. Zahn, A. MartinezNuclear Fusion2001被引用: 57
高精度タイトル一致
ITER-FEAT - the future international burning plasma experiment - presentstatus
R AymarPlasma Physics and Controlled Fusion2000
高精度タイトル一致
RTO/RC ITER plasma performance: inductive and steady-stateoperation
V Mukhovatov, D Boucher, N Fujisawa, G Janeschitz, V Leonov, H Matsumoto, A Polevoy, M Shimada, G VayakisPlasma Physics and Controlled Fusion2000
高精度タイトル一致
The ITER reduced cost design
R. AymarFusion Engineering and Design2000
高精度タイトル一致
Overview of the divertor design and its integration into RTO/RC-ITER
G Janeschitz, R Tivey, A Antipenkov, V Barabash, E MartinFusion Engineering and Design2000
高精度タイトル一致
European development of prototypes for ITER high heat flux components
G Vieider, M Merola, F Anselmi, J.P Bonal, C.H WuFusion Engineering and Design2000
高精度タイトル一致
Novel designs of the ITER gas box liner aimed at reducing tritium codeposition
C Cazzola, J Boscary, R MateraFusion Engineering and Design2000
高精度タイトル一致
The high heat flux components for ITER neutral beam system
E Di Pietro, T Inoue, A Panasenkov, A Krylov, V BykovFusion Engineering and Design2000
高精度タイトル一致
Detail design and manufacture of a prototype beryllium covered divertor baffle for ITER
A Erskine, K Cheyne, M Merola, J Turner, S KingFusion Engineering and Design2000
高精度タイトル一致
Fabrication of the wing and vertical target dummy armour prototypes of the ITER divertor
M Grattarola, M Bet, B Biagiotti, G Gandini, F ZacchiaFusion Engineering and Design2000
高精度タイトル一致
Design issues and cost implications of RTO/RC-ITER divertor
C Ibbott, A Antipenkov, S Chiocchio, G Federici, R TiveyFusion Engineering and Design2000
高精度タイトル一致
Main achievements of the EU HT test programme of ITER primary wall small scale mock ups
P Lorenzetto, A Cardella, P Chappuis, W Daenner, S TähtinenFusion Engineering and Design2000
高精度タイトル一致
Design of a radiative semi-transparent liner for the ITER divertor cassette
A Makhankov, I Arkhipov, G Federici, A Gorodetsky, A ZakharovFusion Engineering and Design2000
高精度タイトル一致
Manufacturing of a full scale baffle prototype for ITER with a CFC and W plasma spray armour
M Merola, I Bobin-Vastra, A Cardella, M Febvre, G VieiderFusion Engineering and Design2000
高精度タイトル一致
Failure analysis of beryllium tile assemblies following high heat flux testing for the ITER program
B.C Odegard, C.H Cadden, N.Y.C Yang, R.D Watson, D.L YouchisonFusion Engineering and Design2000
高精度タイトル一致
Fabrication of monoblock high heat flux components for ITER divertor upper vertical target using hot isostatic pressing diffusion welding
E Rigal, P Bucci, G Le MaroisFusion Engineering and Design2000
高精度タイトル一致
Major achievements of the European shield blanket R&D during the ITER EDA, and their relevance for future next step machines
W Dänner, A Cardella, L Jones, P Lorenzetto, F TavassoliFusion Engineering and Design2000
高精度タイトル一致
FW/Blanket and vacuum vessel for RTO/RC ITER
K Ioki, V Barabash, A Cardella, F Elio, M YamadaFusion Engineering and Design2000
高精度タイトル一致
Improved modules for the blanket of RTO/RC ITER
F Elio, K Ioki, A CardellaFusion Engineering and Design2000
高精度タイトル一致
Neutronic shielding analysis of the water-cooled lithium lead test blanket module in the ITER machine
M RapisardaFusion Engineering and Design2000
高精度タイトル一致
Effect of ITER blanket manufacturing process on the properties of the 316L(N)-IG steel
B.S Rodchenkov, Y.S Strebkov, G.M Kalinin, O.A GolosovFusion Engineering and Design2000
高精度タイトル一致
Tritium inventory and permeation in the ITER breeding blanket
V. Violante, S. Tosti, C. Sibilia, F. Felli, C. AlvaniFusion Engineering and Design2000
高精度タイトル一致
Neutronic, thermal–hydraulic and stress analysis of RF lithium cooled test blanket module for ITER
I.V Vitkovsky, M.M Golovanov, V.A Divavin, I.R Kirillov, O.L SchipakinFusion Engineering and Design2000
高精度タイトル一致
Tritium recovery from an ITER ceramic test blanket module — process options and critical R&D issues
H. Albrecht, E. HutterFusion Engineering and Design2000
高精度タイトル一致
A design study of water detritation and hydrogen isotope separation systems for ITER
Y. Iwai, H. Yoshida, T. Yamanishi, S. Senrui, M. NishiFusion Engineering and Design2000
高精度タイトル一致
Fuel cycle design evolution from FDR-ITER to RTO/RC-ITER
D.K Murdoch, M Glugla, O KvetonFusion Engineering and Design2000
高精度タイトル一致
Catalytic membrane reactors for tritium recovery from tritiated water in the ITER fuel cycle
S Tosti, V Violante, A Basile, G Chiappetta, F SartoFusion Engineering and Design2000
高精度タイトル一致
The influence of water on the performance of ITER cryosorption vacuum pumps
Chr Day, B Kammerer, A MackFusion Engineering and Design2000
高精度タイトル一致
Design of the RTO/RC ITER primary pumping system
P Ladd, C Ibbott, G Janeschitz, E MartinFusion Engineering and Design2000
高精度タイトル一致
Design and analysis of the vacuum vessel for RTO/RC-ITER
M Onozuka, K Ioki, G Johnson, T Kodama, Y UtinFusion Engineering and Design2000
高精度タイトル一致
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