FusionPapers
図版検索AI要約wiki日本の研究装置ジャーナルChatGPTAbout
© 2026 FUSIONPAPERS
About法務情報
装置一覧に戻る
ITER

ITER

Cadarash, France

ITER (""The Way"" in Latin) is one of the most ambitious energy projects in the world today.

公式サイト

トピックキーワード

#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

装置分析

ジャーナル別論文数

FED
NF
PPCF
POP
RSI

年別論文数推移

中精度マッチ中精度50件

Measurement of neutron energy for ICRF heated D-T plasma experiments
M Osakabe, M Sasao, A.L Roquernore, L.C Johnson, S ItohFusion Engineering and Design1997
中精度概要文一致
Nuclear fusion, an energy source
R ToschiFusion Engineering and Design1997
中精度概要文一致
Management of waste from the International Thermonuclear Experimental Reactor and from future fusion power plants
Karin Brodén, Maria Lindberg, Simon Nisan, Paolo Rocco, Cleve FortyFusion Engineering and Design1997
中精度

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

概要文一致
Possible divertor solutions for a fusion reactor.: Part I. Physical aspects based on present day divertor operation
A Kallenbach, H.-S Bosch, S de Peña Hempel, R Dux, H ZohmFusion Engineering and Design1997
中精度概要文一致
Advances in techniques for diagnosing fusion plasmas
Peter E StottFusion Engineering and Design1997
中精度概要文一致
Fracture mechanics behavior of a NiFe superalloy sheath for superconducting fusion magnets. Part 2. magnet life analysis model
J.H. Kim, I.S. Hwang, R.L. ToblerFusion Engineering and Design1997
中精度概要文一致
Nuclear heating experiments for the validation of fusion reactor shielding performance
P. Batistoni, M. Angelone, M. Pillon, V. RadoFusion Engineering and Design1997
中精度概要文一致
An investigation of the activation of water by D-T fusion neutrons and some implications for fusion reactor technology
Yujiro Ikeda, Yoshitomo Uno, Fujio Maekawa, Donald L. Smith, Anatoly A. FilatenkovFusion Engineering and Design1997
中精度概要文一致
Beryllium as the plasma-facing material in fusion energy systems—experiments, evaluation, and comparison with alternative materials
Robert W Conn, Russell P Doerner, Jongik WonFusion Engineering and Design1997
中精度概要文一致
Impurity induced neutralization of megaelectronvolt energy protons in JET plasmas
A.A. Korotkov, A. Gondhalekar, A.J. StuartNuclear Fusion1997被引用: 71
中精度概要文一致
Plasma exhaust requirement for sustained ignition: relaxation due to profile considerations
D.S. Gray, J.A. Boedo, R.W. ConnNuclear Fusion1997被引用: 5
中精度概要文一致
Nature of high-Z impurity accumulation in tokamaks
M.Z. Tokar, J. Rapp, G. Bertschinger, L. Konen, H.R. Koslowski, A. Kramer-Flacken, V. Philipps, U. Samm, B. UnterbergNuclear Fusion1997被引用: 40
中精度概要文一致
Thermal electron transport in regimes with low and negative magnetic shear in Tore Supra
I. Voitsekhovitch, X. Litaudon, D. Moreau, T. Aniel, A. Becoulet, M. Erba, E. Joffrin, F. Kazarian-Vibert, Y. PeyssonNuclear Fusion1997被引用: 23
中精度概要文一致
High beta tokamak operation in DIII-D limited at low density/collisionality by resistive tearing modes
R.J. La Haye, L.L. Lao, E.J. Strait, T.S. TaylorNuclear Fusion1997被引用: 107
中精度概要文一致
Partially detached radiative divertor with active divertor pumping
T.W. Petrie, R. Maingi, S.L. Allen, D.A. Buchenauer, D.N. Hill, C.J. LasnierNuclear Fusion1997被引用: 28
中精度概要文一致
Liquid jets for fast plasma termination in tokamaks
M.N. Rosenbluth, S.V. Putvinskij, P.B. ParksNuclear Fusion1997被引用: 34
中精度概要文一致
Approximation of eddy currents in three dimensional structures by toroidally symmetric models, and plasma control issues
I. Senda, T. Shoji, T. Tsunematsu, T. Nishino, H. FujiedaNuclear Fusion1997被引用: 7
中精度概要文一致
Criterion for zero net erosion at divertor plates in fusion experiments
D. NaujoksNuclear Fusion1997被引用: 4
中精度概要文一致
Diagnostics for experimental thermonuclear fusion reactors
K M YoungPlasma Physics and Controlled Fusion1996
中精度概要文一致
Modelling ohmic confinement experiments on the START tokamak
C M RoachPlasma Physics and Controlled Fusion1996
中精度概要文一致
Ignition analysis with the H-mode power threshold scaling in a D - T tokamak reactor
Osamu Mitarai, Katsunori MuraokaPlasma Physics and Controlled Fusion1996
中精度概要文一致
ICRF heating of TFTR plasmas fuelled by deuterium - tritium neutral beam injection
G Taylor, B LeBlanc, M Murakami, C K Phillips, J R Wilson, M G Bell, R V Budny, C E Bush, Z Chang, D DarrowPlasma Physics and Controlled Fusion1996
中精度概要文一致
Designing a VH-mode core/L-mode edge discharge
G M Staebler, F L Hinton, J C WileyPlasma Physics and Controlled Fusion1996
中精度概要文一致
Compatibility of H-mode with a radiating boundary and divertor detachment
H-S Bosch, O Gruber, G Haas, A Kallenbach, M Kaufmann, K Lackner, V Mertens, R Neu, J Neuhauser, F RyterPlasma Physics and Controlled Fusion1996
中精度概要文一致
Maintenance of a commercial fusion power station and its implications for safety
D.V. Sherwood, J. Pearcey, H.M. Thompson, J.-Ch. Sublet, N.P. TaylorFusion Engineering and Design1996
中精度概要文一致
Some aspects of volumetric neutron source based on tokamak with ‘warm’ magnet system and inner radiation shield
O.G. Filatov, V.V. Filatov, Ye.G. Kuzmin, A.N. Makhankov, V.E. ZhogolevFusion Engineering and Design1996
中精度概要文一致
Convective heat transfer enhancement when using gas-solid particle two phase coolant for the Tokamak type reactor first wall cooling
A.M. Epinatiev, V.V. Perevezentsev, A.V. RazmerovFusion Engineering and Design1996
中精度概要文一致
Present activities for the preparation of a Japanese draft of structural design guidelines for the experimental fusion reactor
K. Miya, Y. Muto, H. Takatsu, K. Hada, S. KinoshitaFusion Engineering and Design1996
中精度概要文一致
Transient electromagnetic analysis in tokamaks using typhoon code
A.V. Belov, N.I. Doinikov, A.E. Duke, V.V. Kokotkov, S.E. SytchevskyFusion Engineering and Design1996
中精度概要文一致
Observations of enhanced core confinement in negative magnetic shear discharges with an L mode edge on DIII-D
B.W. Rice, E.A. Lazarus, M.E. Austin, K.H. Burrell, T.A. Casper, R.J. Groebner, P. Gohil, C.B. Forest, H. Ikezi, L.L. LaoNuclear Fusion1996被引用: 45
中精度概要文一致
Study of electron ripple injection concept for radial electric field control in a tokamak
W. Choe, M. Ono, C.-S. ChangNuclear Fusion1996被引用: 5
中精度概要文一致
Control of wall particle inventory with divertor pumping on DIII-D
R. Maingi, G.L. Jackson, M.R. Wade, M.A. Mahdavi, P.K. Mioduszewski, G. Haas, M.J. Schaffer, J.T. Hogan, C.C. KlepperNuclear Fusion1996被引用: 43
中精度概要文一致
Empirical scaling law for the effective heat diffusivity in ELMy H mode plasmas
G. BeckerNuclear Fusion1996被引用: 11
中精度概要文一致
Calculation of electron cyclotron current drive consistent with tokamak transport
E. Lazzaro, G. Ramponi, A. FigueiredoNuclear Fusion1996被引用: 5
中精度概要文一致
A Bayesian approach to the global confinement time scaling in W7-AS
V. Dose, W. von der Linden, A. GarrettNuclear Fusion1996被引用: 7
中精度概要文一致
Similarity in divertor studies
I.H. Hutchinson, G.C. VlasesNuclear Fusion1996被引用: 20
中精度概要文一致
Direct ion orbit loss near the plasma edge of a divertor tokamak in the presence of a radial electric field
K. MiyamotoNuclear Fusion1996被引用: 47
中精度概要文一致
Energy confinement scaling from the international stellarator database
U. Stroth, M. Murakami, R.A. Dory, H. Yamada, S. Okamura, F. Sano, T. ObikiNuclear Fusion1996被引用: 258
中精度概要文一致
Divertor plate power load equalization by means of biasing
R R WeynantsPlasma Physics and Controlled Fusion1995
中精度概要文一致
A volumetric neutron source for fusion nuclear technology testing and development
Mohamed A AbdouFusion Engineering and Design1995
中精度概要文一致
Neutron and thermal calculation of blanket for high power operating condition of fusion reactor
Hisashi Sagawa, Satoshi Shimakawa, Toshimasa Kuroda, Hiroshi Kawamura, Minoru SaitoFusion Engineering and Design1995
中精度概要文一致
Ceramic breeding blanket development for experimental fusion reactor in JAERI
T Kurasawa, H Takatsu, S Sato, S Mori, T KurodaFusion Engineering and Design1995
中精度概要文一致
Study of magnetic damping effect on dynamic deflection of fusion reactor first wall
Yoshikatsu Yoshida, Kenzo Miya, Kazuyuki DemachiFusion Engineering and Design1995
中精度概要文一致
Numerical analysis of magnetoelastic buckling of fusion reactor components
K Demachi, Y Yoshida, K MiyaFusion Engineering and Design1995
中精度概要文一致
Fusion reactor design parameters relevant to the passive removal of decay heat
F. AndritsosFusion Engineering and Design1995
中精度概要文一致
Remote handling technology development for fusion experimental reactors
E. Tada, D. Maisonnier, J. HerndonFusion Engineering and Design1995
中精度概要文一致
The role of the Associations in the European fusion programme
K. PinkauFusion Engineering and Design1995
中精度概要文一致
Advanced electron cyclotron heating systems for next-step fusion experiments
Manfred ThummFusion Engineering and Design1995
中精度概要文一致
Energy deposition during disruption simulation experiments in a plasma accelerator
H. Bolt, V. Barabash, A. Gervash, J. Linke, M. RödigFusion Engineering and Design1995
中精度概要文一致
Structural analysis and design against failure of fusion power plant components with special reference to pulsed operation
Panayiotis J. KarditsasFusion Engineering and Design1995
中精度概要文一致
前へ99 / 117次へ