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

ITER overview

Y. Shimomura, R. Aymar, V. Chuyanov, M. Huguet, R. Parker, ITER Joint Central TeamNuclear Fusion1999被引用: 60

高精度タイトル一致

High-power test of the all-metal supports for a center conductor of an ITER ICRF antenna

S Moriyama, H Kimura, T Fujii, M Saigusa, K OhtaFusion Engineering and Design1999

高精度タイトル一致

Linear quadratic Gaussian controller design for plasma current, position and shape control system in ITER

V Belyakov, A Kavin, V Kharitonov, B Misenov, A ZhabkoFusion Engineering and Design1999

高精度

信頼度別論文数

高精度

3,700

低精度

794

中精度

1,390

Experimental validation of calculations of decay heat induced by 14 MeV neutron activation of ITER materials

N.P Taylor, Y Ikeda, H.-W Bartels, G Cambi, M.Z YoussefFusion Engineering and Design1999

高精度タイトル一致

Activation product transport using TRACT: ORE estimation of an ITER cooling loop

Panos J. KarditsasFusion Engineering and Design1999

高精度タイトル一致

The JA home team design of the ITER ECRF power supply system

M. Tsuneoka, T. Imai, E. Bowles, I. Benfatto, M. IshibashiFusion Engineering and Design1999

高精度タイトル一致

Critical heat flux analysis and R&D for the design of the ITER divertor

A.R. Raffray, J. Schlosser, M. Akiba, M. Araki, D. YouchisonFusion Engineering and Design1999

高精度タイトル一致

Monte Carlo analysis of helium production in the ITER shielding blanket module

Satoshi Sato, Hiromasa Iida, Romano Plenteda, Robert T SantoroFusion Engineering and Design1999

高精度タイトル一致

Leak detection system in ITER

S Hiroki, P Ladd, K Shaubel, G Janeschitz, R.A MarrsFusion Engineering and Design1999

高精度タイトル一致

ITER achievements by July 1998 and future prospects

R. AymarFusion Engineering and Design1999

高精度タイトル一致

ITER magnet design and R&D

N MitchellFusion Engineering and Design1999

高精度タイトル一致

The ITER toroidal field model coil (TFMC)

E Salpietro, R Maix, G Bevilacqua, G Di Bartolo, G.E TardivelliFusion Engineering and Design1999

高精度タイトル一致

Engineering design of the ITER blanket and relevant research and development results

F Elio, K Ioki, P Barabaschi, L Bruno, H TakatsuFusion Engineering and Design1999

高精度タイトル一致

ITER reference breeding blanket design

M Ferrari, A Bianchi, G Celentano, W Dänner, F ZacchiaFusion Engineering and Design1999

高精度タイトル一致

Objectives feasibility assessment of the water-cooled lithium–lead mock-up testing in ITER

L Giancarli, G Benamati, B Bielak, M.A Fütterer, J SzczepanskiFusion Engineering and Design1999

高精度タイトル一致

ITER divertor, design issues and research and development

R. Tivey, T. Ando, A. Antipenkov, V. Barabash, G. VieiderFusion Engineering and Design1999

高精度タイトル一致

European development of the ITER divertor target

G Vieider, M Merola, J.P Bonal, P Chappuis, C.H WuFusion Engineering and Design1999

高精度タイトル一致

The ultimate safety margins of ITER: a demonstration of the safety potential of fusion

David A Petti, Hans-Werner BartelsFusion Engineering and Design1999

高精度タイトル一致

Neutronics experiment on a mock-up of the ITER shielding blanket at the Frascati Neutron Generator

P. Batistoni, M. Angelone, U. Fischer, H. Freiesleben, S. UnholzerFusion Engineering and Design1999

高精度タイトル一致

Analyses of loss of vacuum accident (LOVA) in ITER

T. Honda, H.-W. Bartels, B. Merrill, T. Inabe, T. OkazakiFusion Engineering and Design1999

高精度タイトル一致

Evaluation of biological dose rates around the ITER NBI ports by 2-D Sn/activation and 3-D Monte Carlo analyses

Satoshi Sato, Hiromasa Iida, Romano Plenteda, Davide Valenza, Robert T SantoroFusion Engineering and Design1999

高精度タイトル一致

Error field mode studies on JET, COMPASS-D and DIII-D, and implications for ITER

R.J. Buttery, M. De' Benedetti, D.A. Gates, Yu. Gribov, T.C. Hender, R.J. La Haye, P. Leahy, J.A. Leuer, A.W. Morris, A. SantagiustinaNuclear Fusion1999被引用: 167

高精度タイトル一致

Integrated design of the ITER magnets and their auxiliary systems

M. Huguet, ITER Joint Central Team, ITER Home TeamsNuclear Fusion1999被引用: 3

高精度タイトル一致

Remote handling maintenance of ITER

R. Haange, ITER Joint Central Team, ITER Home TeamsNuclear Fusion1999被引用: 7

高精度タイトル一致

Overview of ITER physics deuterium-tritium experiments in JET

J. Jacquinot, V.P. Bhatnagar, J.G. Cordey, L.D. Horton, D.F.H. Start, R. Barnsley, P. Breger, J.P. Christiansen, S. Clement, S.J. DaviesNuclear Fusion1999被引用: 79

高精度タイトル一致

Tritium experience in large tokamaks: Application to ITER

C.H. Skinner, C.A. Gentile, J.C. Hosea, D. Mueller, J.P. Coad, G. Federici, R. HaangeNuclear Fusion1999被引用: 26

高精度タイトル一致

Predictive tests of ITG based models of tokamak heat transport on ITER database discharges

M. Erba, W. Horton, M. OttavianiNuclear Fusion1999被引用: 4

高精度タイトル一致

Transport simulations of H-mode plasmas with ITER database

Ryoji Hiwatari, Yuichi Ogawa, Tsuneo AmanoPlasma Physics and Controlled Fusion1998

高精度タイトル一致

Edge parameter operational space and trajectories for ITER

Yu Igitkhanov, G Janeschitz, G W Pacher, M Sugihara, H D Pacher, D E Post, E Solano, J Lingertat, A Loarte, T OsbornePlasma Physics and Controlled Fusion1998

高精度タイトル一致

H-mode pedestal characteristics, ELMs, and energy confinement in ITER shape discharges on DIII-D

T H Osborne, R J Groebner, L L Lao, A W Leonard, R Maingi, R L Miller, G D Porter, D M Thomas, R E WaltzPlasma Physics and Controlled Fusion1998

高精度タイトル一致

Scaling of the H-mode power threshold for ITER

The ITER H-mode Threshold Database Working Group, presented by E RighiPlasma Physics and Controlled Fusion1998

高精度タイトル一致

Ignition analyses with ITER89P and ITER93HP scalings for burn control and diagnostics in ITER-ID

Osamu Mitarai, Katsunori MuraokaPlasma Physics and Controlled Fusion1998

高精度タイトル一致

The strengths, needs and possible drawbacks of different heating and current drive systems in relation to ITER

R WilhelmPlasma Physics and Controlled Fusion1998