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

装置分析

ジャーナル別論文数

FED

PPCF

POP

RSI

年別論文数推移

高精度マッチ高精度50件

How should we test the ITER TF coils?

P. Libeyre, D. Ciazynski, J.L. Duchateau, T. Schild, G. ZahnFusion Engineering and Design2005

高精度タイトル一致

Fatigue assessment of the ITER TF coil case based on JJ1 fatigue tests

K. Hamada, H. Nakajima, K. Takano, Y. Kudo, C. JongFusion Engineering and Design2005

高精度タイトル一致

High temperature superconductors for the ITER magnet system and beyond

W.H. Fietz, S. Fink, R. Heller, P. Komarek, A. VostnerFusion Engineering and Design2005

高精度

信頼度別論文数

高精度

3,700

低精度

794

中精度

1,390

Transient electrical behaviour of the ITER TF coils during fast discharge and two fault cases

S. Fink, T. Bonicelli, W.H. Fietz, A. Miri, A. UlbrichtFusion Engineering and Design2005

高精度タイトル一致

The ITER thermal shields for the magnet system: Design evolution and analysis

V. Bykov, Yu. Krasikov, S. Grigoriev, V. Komarov, V. TanchukFusion Engineering and Design2005

高精度タイトル一致

The European development of a full scale switching unit for the ITER switching and discharging networks

T. Bonicelli, A. De Lorenzi, D. Hrabal, R. Piovan, S.R. ShawFusion Engineering and Design2005

高精度タイトル一致

Design optimisation of the ITER TF coil case and structures

Marco Ferrari, Pietro Barabaschi, Cornelis T.J. Jong, Yuri Krivchenkov, Neil MitchellFusion Engineering and Design2005

高精度タイトル一致

Updating the design of the feeder components for the ITER magnet system

K. Yoshida, Y. Takahashi, T. Isono, N. MitchellFusion Engineering and Design2005

高精度タイトル一致

Fibreglass unidirectional composite to be used for ITER pre-compression rings

Claudio Nardi, Livio Bettinali, Aldo PizzutoFusion Engineering and Design2005

高精度タイトル一致

A low cost joint for the ITER PF coils, design and test results

B. Stepanov, P. Bruzzone, M. VogelFusion Engineering and Design2005

高精度タイトル一致

Development of the plasma facing components for the dome-liner component of the ITER divertor

U. Luconi, M. Di Marco, A. Federici, M. Grattarola, G. PasqualeFusion Engineering and Design2005

高精度タイトル一致

Manufacturing and testing in reactor relevant conditions of brazed plasma facing components of the ITER divertor

M. Bisio, V. Branca, M. Di Marco, A. Federici, F. VaroneFusion Engineering and Design2005

高精度タイトル一致

Manufacture of blanket shield modules for ITER

P. Lorenzetto, B. Boireau, C. Boudot, P. Bucci, S. TähtinenFusion Engineering and Design2005

高精度タイトル一致

Development of a copper alloy to beryllium HIP bonding technology for the ITER first wall

P. Sherlock, A.T. Peacock, A.D. Mc CallumFusion Engineering and Design2005

高精度タイトル一致

A mature industrial solution for ITER divertor plasma facing components: Hypervapotron cooling concept adapted to Tore Supra flat tile technology

F. Escourbiac, I. Bobin-Vastra, V. Kuznetsov, M. Missirlian, J. SchlosserFusion Engineering and Design2005

高精度タイトル一致

High temperature stresses in brazed Glidcop/W model structures of interest for ITER divertor technology

C. Braham, R. Coppola, C. Nardi, M. ValliFusion Engineering and Design2005

高精度タイトル一致

Development of an original active thermography method adapted to ITER plasma facing components control

A. Durocher, N. Vignal, F. Escourbiac, J.L. Farjon, F. CismondiFusion Engineering and Design2005

高精度タイトル一致

Erosion of macrobrush tungsten armor after multiple intense transient events in ITER

B.N. Bazylev, G. Janeschitz, I.S. Landman, S.E. PestchanyiFusion Engineering and Design2005

高精度タイトル一致

Structural and fracture mechanics analysis of ITER toroidal field coil

K. Watanabe, S. Iki, K. Takiue, M. SaitoFusion Engineering and Design2005

高精度タイトル一致

Results and analysis of high heat flux tests on a full-scale vertical target prototype of ITER divertor

M. Missirlian, F. Escourbiac, M. Merola, I. Bobin-Vastra, A. DurocherFusion Engineering and Design2005

高精度タイトル一致

Overview of the engineering design of the ITER divertor improvements towards manufacture

R. Tivey, E. D’Agata, V. Chuyanov, H. HeidlFusion Engineering and Design2005

高精度タイトル一致

Steady state and transient thermal–hydraulic analyses on ITER divertor module

G. Dell’Orco, A. Ancona, A. Di Maio, M. Merola, I. ZammutoFusion Engineering and Design2005

高精度タイトル一致

Assessment of a cooperative maintenance scheme for ITER divertor cooling pipes

J.P. Friconneau, O. David, J.P. Martins, J.D. Palmer, A. TesiniFusion Engineering and Design2005

高精度タイトル一致

ITER articulated inspection arm (AIA): R&d progress on vacuum and temperature technology for remote handling

Y. Perrot, J.J. Cordier, J.P. Friconneau, L. Gargiulo, A. TesiniFusion Engineering and Design2005

高精度タイトル一致

ITER Articulated Inspection Arm (AIA): Geometric calibration issues of a long-reach flexible robot

D. Arhur, Y. Perrot, C. Bidard, J.P. Friconneau, L. SemeraroFusion Engineering and Design2005

高精度タイトル一致

Analyses of the ITER vacuum vessel with the use of a new modelling technique

V. Rozov, E. D’Agata, K. Ioki, M. Morimoto, G. SannazzaroFusion Engineering and Design2005

高精度タイトル一致

Generic control system design for the Cassette Multifunctional Mover and other ITER remote handling equipment

M. Irving, J. Palmer, M. SiukoFusion Engineering and Design2005

高精度タイトル一致

Design progress of the ITER vacuum vessel and ports

Yu. Utin, V. Chuyanov, F. Elio, K. Ioki, G. SannazzaroFusion Engineering and Design2005

高精度タイトル一致

Recent developments towards ITER 2001 divertor maintenance

J. Palmer, M. Siuko, P. Agostini, R. Gottfried, M. Van UffelenFusion Engineering and Design2005

高精度タイトル一致

Special blanket design in the NB region of ITER

F. Elio, K. Ioki, Y. Utin, M. MorimotoFusion Engineering and Design2005

高精度タイトル一致

ITER vacuum vessel sector manufacturing development in Europe

Lawrence Jones, Aldo Bianchi, Alain Cros, Enrico di Pietro, Yuri UtinFusion Engineering and Design2005

高精度タイトル一致

Experimental result of the laser in vessel viewing and ranging system (IVVS) for ITER

C. Neri, L. Bartolini, B. Brichard, A. Coletti, L. SemeraroFusion Engineering and Design2005

高精度タイトル一致

Development and control towards a parallel water hydraulic weld/cut robot for machining processes in ITER vacuum vessel

Huapeng Wu, Heikki Handroos, Pekka Pessi, Juha Kilkki, Lawrence JonesFusion Engineering and Design2005

高精度タイトル一致

Protection of the primary circuits and effect on the design of the inner deuterium/tritium fuel cycle of ITER

M. Glugla, C. Caldwell-Nichols, I.R. Cristescu, L. Doerr, P. SchaeferFusion Engineering and Design2005

高精度タイトル一致

Experimental validation of a method for performance monitoring of the front-end permeators in the TEP system of ITER

B. Bornschein, M. Glugla, K. Günther, T.L. Le, K.H. SimonFusion Engineering and Design2005

高精度タイトル一致

Requirements and selection criteria for the mechanical pumps for the ITER tritium plant

C.J. Caldwell-Nichols, M. Glugla, S. Welte, D.K. MurdochFusion Engineering and Design2005

高精度タイトル一致

Strategy for determination of ITER in-vessel tritium inventory

David Murdoch, Ioana-Ruxandra Cristescu, Rainer LässerFusion Engineering and Design2005

高精度タイトル一致

JET contribution to ITER fuel cycle issues

C. Grisolia, N. Bekris, J. Likonen, P. Coad, S. RosanvallonFusion Engineering and Design2005

高精度タイトル一致

Pellet delivery and survivability through curved guide tubes for fusion fueling and its implications for ITER

S.K. Combs, L.R. Baylor, J.B.O. Caughman, D.T. Fehling, M. WatsonFusion Engineering and Design2005

高精度タイトル一致

EU contributions to the ITER materials properties data assessment

A.T. Peacock, V. Barabash, F. Gillemot, P. Karditsas, M. WaltersFusion Engineering and Design2005

高精度タイトル一致

On the nuclear response of the helium-cooled lithium lead test blanket module in ITER

P. Chiovaro, P.A. Di Maio, G. VellaFusion Engineering and Design2005

高精度タイトル一致

The European breeding blankets development and the test strategy in ITER

Y. Poitevin, L.V. Boccaccini, A. Cardella, L. Giancarli, G. BenamatiFusion Engineering and Design2005

高精度タイトル一致

New modular concept for the helium cooled pebble bed test blanket module for ITER

R. Meyder, L.V. Boccaccini, B. Dolensky, S. Hermsmeyer, Z. XuFusion Engineering and Design2005

高精度タイトル一致

Fusion-driven hybrid system with ITER model

I. Murata, Y. Yamamoto, S. Shido, K. Kondo, K. OchiaiFusion Engineering and Design2005

高精度タイトル一致

HCLL TBM for ITER-design studies

G. Rampal, A. Li Puma, Y. Poitevin, E. Rigal, C. BoudotFusion Engineering and Design2005

高精度タイトル一致

The helium-cooled lithium lead blanket test proposal in ITER and requirements on test blanket modules instrumentation

A. Li Puma, Y. Poitevin, L. Giancarli, G. Rampal, W. FaraboliniFusion Engineering and Design2005

高精度タイトル一致

Progress in licensing ITER in Cadarache

Lina Rodríguez-Rodrigo, Jean-Philippe Girard, Joëlle Uzan-Elbez, Gabriel Marbach, Sandrine RosanvallonFusion Engineering and Design2005

高精度タイトル一致

Fire risk analysis in ITER tritium building

Franck Lignini, Joëlle Uzan-Elbez, Jean-Philippe Girard, Maria Teresa Porfiri, Lina Rodríguez-RodrigoFusion Engineering and Design2005

高精度タイトル一致

ITER

トピックキーワード

装置分析

ジャーナル別論文数

年別論文数推移

高精度マッチ高精度50件

信頼度別論文数

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