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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

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NF
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POP
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年別論文数推移

中精度マッチ中精度50件

Prototype tokamak fusion reactor based on SiC/SiC composite material focusing on easy maintenance
S Nishio, S Ueda, R Kurihara, T Kuroda, T YoshidaFusion Engineering and Design2000
中精度概要文一致
Study of a spherical torus based volumetric neutron source for nuclear technology testing and development
E.T Cheng, R.J Cerbone, I.N Sviatoslavsky, L.D Galambos, Y.-K.M PengFusion Engineering and Design2000
中精度概要文一致
Assessment of the gas dynamic trap mirror facility as intense neutron source for fusion material test irradiations
U. Fischer, A. Möslang, A.A. IvanovFusion Engineering and Design2000

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

中精度
概要文一致
The feasibility of a tokamak reactor with a very high aspect ratio plasma
Y Murakami, K Shinya, S NishioFusion Engineering and Design2000
中精度概要文一致
Energy analysis and carbon dioxide emission of Tokamak fusion power reactors
Koji Tokimatsu, Hiroki Hondo, Yuichi Ogawa, Kunihiko Okano, Makoto KatsuraiFusion Engineering and Design2000
中精度概要文一致
European structural materials development for fusion applications
B van der Schaaf, K Ehrlich, P Fenici, A.A Tavassoli, M VictoriaFusion Engineering and Design2000
中精度概要文一致
Status of fusion technology development in JAERI stressing steady-state operation for future reactors
Shinzaburo MatsudaFusion Engineering and Design2000
中精度概要文一致
Japanese developments of fusion reactor plasma facing components
T. Hino, M. AkibaFusion Engineering and Design2000
中精度概要文一致
Pumping performance of pebble drop divertor
K Matsuhiro, M Isobe, Y Ueda, M NishikawaFusion Engineering and Design2000
中精度概要文一致
Thermal fatigue damage of the divertor plate
Satoshi Suzuki, Koichiro Ezato, Kazuyoshi Sato, Kazuyuki Nakamura, Masato AkibaFusion Engineering and Design2000
中精度概要文一致
HIP technologies for fusion reactor blankets fabrication
G Le Marois, L Federzoni, P Bucci, P RevirandFusion Engineering and Design2000
中精度概要文一致
Progress of fusion fuel processing system development at the Japan Atomic Energy Research Institute
Masataka Nishi, Toshihiko Yamanishi, Yoshinori Kawamura, Yasunori Iwai, Satoshi KonishiFusion Engineering and Design2000
中精度概要文一致
Irradiation effects on magnetic probes made of mineral insulated cable
T Nishitani, T Shikama, M Fukao, H Matsuo, S KasaiFusion Engineering and Design2000
中精度概要文一致
Fission-reactor-radiation-tests of MI-cables and magnetic coils for fusion burning plasma diagnostics
T. Shikama, S. Yamamoto, R. Snider, M. Fukao, T. SagawaFusion Engineering and Design2000
中精度概要文一致
Neoclassical impurity transport in the core of an ignited tokamak plasma
R. Dux, A.G. PeetersNuclear Fusion2000被引用: 39
中精度概要文一致
Thermal hydraulic characteristics during ingress of coolant and loss of vacuum events in fusion reactors
K. Takase, T. Kunugi, Y. Seki, H. AkimotoNuclear Fusion2000被引用: 10
中精度概要文一致
Development of key fusion technologies at JET
JET Team (prepared by M.A. Pick)Nuclear Fusion2000被引用: 3
中精度概要文一致
Compact reversed shear tokamak reactor with a superheated steam cycle
K. Okano, Y. Asaoka, T. Yoshida, M. Furuya, K. Tomabechi, Y. Ogawa, N. Sekimura, R. Hiwatari, T. Yamamoto, T. IshikawaNuclear Fusion2000被引用: 54
中精度概要文一致
Evaluation of CO2 emissions in the life cycle of tokamak fusion power reactors
K. Tokimatsu, H. Hondo, Y. Ogawa, K. Okano, K. Yamaji, M. KatsuraiNuclear Fusion2000被引用: 6
中精度概要文一致
MHD activity at the beta limit in RI mode discharges on TEXTOR-94
H.R. Koslowski, G. Fuchs, R. Jaspers, A. Krämer-Flecken, A.M. Messiaen, J. Ongena, J. Rapp, F.C. Schüller, M.Z. Tokar'Nuclear Fusion2000被引用: 22
中精度概要文一致
The requirements of a next step large steady state tokamak
G. Janeschitz, P. Barabaschi, G. Federici, K. Ioki, P. Ladd, V. Mukhovatov, M. Sugihara, R. Tivey, ITER-JCT and Home TeamNuclear Fusion2000被引用: 17
中精度概要文一致
Report on the 5th European Fusion PhysicsWorkshop, Sesimbra, Portugal, 10-12 December1997
D J Campbell, H J de Blank, O Gruber, T C Hender, J Jacquinot, F W Perkins, M L Watkins, M ZabiégoPlasma Physics and Controlled Fusion1999
中精度概要文一致
Diagnostics for Experimental Thermonuclear Fusion Reactors 2
Kenneth M YoungPlasma Physics and Controlled Fusion1999
中精度概要文一致
Deuterium-tritium operation in magnetic confinement experiments: results and underlying physics
J Jacquinot, the JET teamPlasma Physics and Controlled Fusion1999
中精度概要文一致
The physics of spherical confinement systems
D C RobinsonPlasma Physics and Controlled Fusion1999
中精度概要文一致
Effect of divertor geometry on boundary and core plasma performance in ASDEX Upgrade and JET
H-S Bosch, J C Fuchs, J Gafert, G Haas, A Herrmann, A Kallenbach, M Kaufmann, J Neuhauser, F Ryter, R SchneiderPlasma Physics and Controlled Fusion1999
中精度概要文一致
Design study of a tritium transport package for future fusion reactors
S. O’hira, T. Suzuki, S. Hode, M. NishiFusion Engineering and Design1999
中精度概要文一致
Spherical tokamak volume neutron source
T.C. Hender, G.M. Voss, N.P. TaylorFusion Engineering and Design1999
中精度概要文一致
Systems cost and performance analysis for a spherical torus-based volume neutron source
J.D. Galambos, D.J. Strickler, Y.-K.M. PengFusion Engineering and Design1999
中精度概要文一致
Safety and environment aspects of a fusion power reactor
G Marbach, I CookFusion Engineering and Design1999
中精度概要文一致
Rf ion sources for fusion applications: design, development and performance
E Speth, M Ciric, J.H Feist, P Frank, R WilhelmFusion Engineering and Design1999
中精度概要文一致
Studies in JET divertors of varied geometry. I: Non-seeded plasma operation
L.D. Horton, G.C. Vlases, P. Andrew, V.P. Bhatnagar, A.V. Chankin, S. Clement, G.D. Conway, S.J. Davies, J.C.M. de Haas, J.K. EhrenbergNuclear Fusion1999被引用: 77
中精度概要文一致
Studies in JET divertors of varied geometry. II: Impurity seeded plasmas
G.F. Matthews, B. Balet, J.G. Cordey, S.J. Davies, G.M. Fishpool, H.Y. Guo, L.D. Horton, M.G. von Hellermann, L.C. Ingesson, J. LingertatNuclear Fusion1999被引用: 69
中精度概要文一致
Confinement degradation of ELMy H modes at high density and/or radiated power fraction
JET Team (prepared by G.F. Matthews)Nuclear Fusion1999被引用: 12
中精度概要文一致
Recent results from divertor and scrape-off layer studies at JET
JET Team (prepared by R.D. Monk)Nuclear Fusion1999被引用: 40
中精度概要文一致
Long sustainment of JT-60U plasmas with high integrated performance
Y. Kamada, A. Isayama, T. Oikawa, Y. Sakamoto, N. Hosogane, H. Takenaga, Y. Kusama, T. Fujita, S. Takeji, T. OzekiNuclear Fusion1999被引用: 72
中精度概要文一致
Progress towards sustainment of advanced tokamak modes in DIII-D
B.W. Rice, K.H. Burrell, J.R. Ferron, C.M. Greenfield, G.L. Jackson, L.L. Lao, R.J. La Haye, T.C. Luce, B.W. Stallard, E.J. StraitNuclear Fusion1999被引用: 37
中精度概要文一致
Towards steady state tokamak operation with double transport barriers
JET Team (prepared by F.X. Söldner)Nuclear Fusion1999被引用: 14
中精度概要文一致
Highly radiative plasmas for local transport studies and power and particle handling in reactor regimes
K.W. Hill, M.G. Bell, R.E. Bell, R. Budny, C.E. Bush, D.R. Ernst, G.W. Hammett, D.R. Mikkelsen, H.K. Park, A.T. RamseyNuclear Fusion1999被引用: 10
中精度概要文一致
Neoclassical islands, β-limits, error fields and ELMs in reactor scale tokamaks
F.W. Perkins, A. Bondeson, R.J. Buttery, J.D. Callen, J.W. Connor, A.M. Garofalo, D.A. Gates, R.W. Harvey, C.C. Hegna, T.C. HenderNuclear Fusion1999被引用: 25
中精度概要文一致
Global Alfvén eigenmode stability in thermonuclear tokamak plasmas
A. Jaun, A. Fasoli, J. Vaclavik, L. VillardNuclear Fusion1999被引用: 10
中精度概要文一致
Chapter 2: Plasma confinement and transport
ITER Physics Expert Group on Confinement and Transport, ITER Physics Expert Group on Confinement Modelling and Database, ITER Physics Basis EditorsNuclear Fusion1999被引用: 886
中精度概要文一致
Chapter 6: Plasma auxiliary heating and current drive
ITER Physics Expert Group on Energetic Particles, Heating and Current Drive, ITER Physics Basis EditorsNuclear Fusion1999被引用: 168
中精度概要文一致
Chapter 7: Measurement of plasma parameters
ITER Physics Expert Group on Diagnostics, ITER Physics Basis EditorsNuclear Fusion1999被引用: 50
中精度概要文一致
Chapter 8: Plasma operation and control
ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ITER Physics Expert Group on Energetic Particles, Heating and Current Drive, ITER Physics Expert Group on Diagnostics, ITER Physics Basis EditorsNuclear Fusion1999被引用: 81
中精度概要文一致
Bulk ion heating with ICRH in JET DT plasmas
D.F.H. Start, J. Jacquinot, V. Bergeaud, V.P. Bhatnagar, S.W. Conroy, G.A. Cottrell, S. Clement, G. Ericsson, L.-G. Eriksson, A. FasoliNuclear Fusion1999被引用: 74
中精度概要文一致
Edge localized modes and edge pedestal in NBI and ICRF heated H, D and T plasmas in JET
V.P. Bhatnagar, J. Lingertat, R. Barnsley, P. Breger, J.P. Christiansen, S. Clement, J.G. Cordey, S.J. Davies, J.K. Ehrenberg, L.-G. ErikssonNuclear Fusion1999被引用: 24
中精度概要文一致
Plasma boundary reconstruction from reflectometer arrays
C.E. Kessel, N.L. BretzNuclear Fusion1999被引用: 3
中精度概要文一致
Time dependent transport simulations of JET H mode plasmas
J.E. KinseyNuclear Fusion1999被引用: 14
中精度概要文一致
Plasma control issues for an advanced steady state tokamak reactor
D. Moreau, I. VoitsekhovitchNuclear Fusion1999被引用: 36
中精度概要文一致
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