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

Overview of fusion nuclear technology in Russia
Y Strebkov, V BelyakovFusion Engineering and Design2002
中精度概要文一致
Status of fabrication development for plasma facing components in the EU
W Daenner, M Merola, P Lorenzetto, A Peacock, E ViscaFusion Engineering and Design2002
中精度概要文一致
Fabrication of a first wall panel by diffusion bonding
L.F Moreschi, A Pizzuto, I AlessandriniFusion Engineering and Design2002
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
Non-destructive testing of divertor components
M Merola, P Chappuis, F Escourbiac, M Grattarola, A ZabernigFusion Engineering and Design2002
中精度概要文一致
Gas-cooled high performance divertor for a power plant
S Hermsmeyer, S MalangFusion Engineering and Design2002
中精度概要文一致
Attachment system for helium-cooled blanket of RF DEMO fusion reactor
A. Leshukov, Y. Blinov, V. Kovalenko, G. Shatalov, A. StrizhovFusion Engineering and Design2002
中精度概要文一致
Investigation methods and handling of hazardous materials for fusion blanket applications
A.A Goraieb, H HarschFusion Engineering and Design2002
中精度概要文一致
Tritium inventory and recovery in next-step fusion devices
R.A Causey, J.N Brooks, G FedericiFusion Engineering and Design2002
中精度概要文一致
Entrainment behavior of activated dusts in the fusion reactor under LOVA
Hiroyuki Nakaharai, Takahiro Chuman, Shinji Ebara, Takehiko Yokomine, Tadashi KorenagaFusion Engineering and Design2002
中精度概要文一致
Interaction of plasma-facing materials with air and steam
F Druyts, J Fays, C.H WuFusion Engineering and Design2002
中精度概要文一致
Three-dimensional analysis of water–vapor void fraction in a fusion experimental reactor under water ingress
Kazuyuki Takase, Yasuo Ose, Hajime AkimotoFusion Engineering and Design2002
中精度概要文一致
The advanced 3D method for activation analysis of fusion reactor materials
S Sheludjakov, A SerikovFusion Engineering and Design2002
中精度概要文一致
Design and R&D issues for the JT-60 modification to a full superconducting tokamak
M Matsukawa, The JT-60SC design teamFusion Engineering and Design2002
中精度概要文一致
Benefits to European industry from involvement in fusion
E Bogusch, H Bolt, A Chevalier, C Forty, N WatermanFusion Engineering and Design2002
中精度概要文一致
Initial plasma results from the Electric Tokamak*
R.J. Taylor, J.-L. Gauvreau, M. Gilmore, P.-A. Gourdain, D.J. LaFonteese, L.W. SchmitzNuclear Fusion2002被引用: 18
中精度概要文一致
Local physics basis of confinement degradation in JET ELMy H mode plasmas and implications for tokamak reactors
R.V. Budny, B. Alper, D.N. Borba, J.G. Cordey, D.R. Ernst, C. Giraud, C.W. Gowers, K. Gunther, T.S. Hahm, G.W. HammettNuclear Fusion2002被引用: 6
中精度概要文一致
Thermal energy confinement properties of ELMy H mode plasmas in JT-60U
H. Urano, Y. Kamada, H. Shirai, T. Takizuka, S. Ide, T. Fujita, T. FukudaNuclear Fusion2002被引用: 35
中精度概要文一致
Plasma current ramp-up assisted by outer vertical field coils in a high aspect ratio tokamak
Osamu Mitarai, Ryuji Yoshino, Kenkichi UshigusaNuclear Fusion2002被引用: 11
中精度概要文一致
Fusion alpha parameters in tokamaks with high DT fusion rates
R.V. BudnyNuclear Fusion2002被引用: 45
中精度概要文一致
Linear evolution of plasma equilibrium in tokamaks
I. Senda, T. Shoji, T. TsunematsuNuclear Fusion2002被引用: 3
中精度概要文一致
Active control of resistive wall modesin the large-aspect-ratio tokamak
A. Bondeson, Yueqiang Liu, D. Gregoratto, Y. Gribov, V.D. PustovitovNuclear Fusion2002被引用: 51
中精度概要文一致
28th EPS Conference on Controlled Fusion and Plasma Physics
Plasma Physics and Controlled Fusion2001
中精度概要文一致
Overview of recent spherical tokamak results
Alan SykesPlasma Physics and Controlled Fusion2001
中精度概要文一致
Large-volume microwave plasma for energetic H- ionsneutralization
A A Skovoroda, V A ZhiltsovPlasma Physics and Controlled Fusion2001
中精度概要文一致
Report on the 8th European Fusion PhysicsWorkshop, Leysin, Switzerland, 13-15 December 2000
D J Campbell, X Garbet, G D M Hogeweij, P Mantica, A Peeters, G Saibene, Y Shimomura, M L WatkinsPlasma Physics and Controlled Fusion2001
中精度概要文一致
EC beam tracing in fusion plasmas
E. Poli, G.V. Pereverzev, A.G. Peeters, M. BornaticiFusion Engineering and Design2001
中精度概要文一致
EC emission and absorption in tokamaks: relativistic effects in ray tracing, combined EC-heating and transport codes
L.K Kuznetsova, A.Yu Dnestrovskij, M.N GolikovFusion Engineering and Design2001
中精度概要文一致
Simulations of the operational control of a cryogenic plant for a superconducting burning-plasma tokamak
N MitchellFusion Engineering and Design2001
中精度概要文一致
Occupational safety in the fusion design process
K Moshonas, V.J LangmanFusion Engineering and Design2001
中精度概要文一致
Analysis of human intrusion scenarios for the deep disposal of fusion wastes
Xavier Sillen, Jan Marivoet, Massimo ZucchettiFusion Engineering and Design2001
中精度概要文一致
A continuous winding scheme for superconducting tokamak coils with cable-in-conduit conductor
Sang-ho Kim, Kie-hyung Chung, Deok Kyo LeeFusion Engineering and Design2001
中精度概要文一致
The European technology fusion programme
R. AndreaniFusion Engineering and Design2001
中精度概要文一致
How far is a fusion power reactor from an experimental reactor
R Toschi, P Barabaschi, D Campbell, F Elio, D WardFusion Engineering and Design2001
中精度概要文一致
Thermal hydraulics of water cooled divertors
C.B BaxiFusion Engineering and Design2001
中精度概要文一致
Mechanical and electrical tests on the attachment keys for the divertor vertical target
L.F Moreschi, A Pizzuto, M Agostini, S Storai, M MerolaFusion Engineering and Design2001
中精度概要文一致
High heat flux behaviour of damaged plasma facing components
F Escourbiac, P Chappuis, J Schlosser, M Merola, M FebvreFusion Engineering and Design2001
中精度概要文一致
Fabrication of mock-up with Be armour tiles diffusion bonded to the CuCrZr heat sink
L.F Moreschi, A Pizzuto, I Alessandrini, M Agostini, M MerolaFusion Engineering and Design2001
中精度概要文一致
Tokamak dust, characterisation and removal studies
M Wykes, G Counsell, D McGlinchey, C.H WuFusion Engineering and Design2001
中精度概要文一致
On an Electric Pulsed Hydride Injector for gas puffing into tokamaks
Yu.A Kareev, U Tamm, I.S Glushkov, Yu.G Gendel, V.P NovikovFusion Engineering and Design2001
中精度概要文一致
Research into tritium impact on the models of cryosorption panels under conditions simulating operation of a vacuum pump of fusion rectors
A.I Vedeneev, M.V Glagolev, N.T Kazakovskiy, V.N Lobanov, G.L SaksaganskiyFusion Engineering and Design2001
中精度概要文一致
Cold trapping of traces of tritiated water from the helium loops of a fusion breeder blanket
N Bekris, E Hutter, H Albrecht, R.-D Penzhorn, D MurdochFusion Engineering and Design2001
中精度概要文一致
Performance and remote maintenance of attachment schemes for Plasma Facing Components
J Palmer, S Chiocchio, C Damiani, M Irving, A TurnerFusion Engineering and Design2001
中精度概要文一致
Tool prototypes for replacing plasma facing components
M Siuko, S Chiocchio, C Damiani, M Irving, M VileniusFusion Engineering and Design2001
中精度概要文一致
Extended JT-60U plasma regimes for high integrated performance
Y. Kamada, JT-60 TeamNuclear Fusion2001被引用: 89
中精度概要文一致
Experimental verification of effectiveness of integrated pressure suppression systems in fusion reactors during in-vessel loss of coolant events
K. Takase, H. AkimotoNuclear Fusion2001被引用: 9
中精度概要文一致
Plasma-material interactions in current tokamaks and their implications for next step fusion reactors
G. Federici, C.H. Skinner, J.N. Brooks, J.P. Coad, C. Grisolia, A.A. Haasz, A. Hassanein, V. Philipps, C.S. Pitcher, J. RothNuclear Fusion2001
中精度概要文一致
Large superconductors and joints for fusion magnets: From conceptual design to testing at full scale
D. Ciazynski, J.L. Duchateau, P. Decool, P. Libeyre, B. TurckNuclear Fusion2001被引用: 17
中精度概要文一致
Active feedback stabilization of high beta modes in advanced tokamaks
A. Bondeson, Yueqiang Liu, C.M. Fransson, B. Lennartson, C. Breitholtz, T.S. TaylorNuclear Fusion2001被引用: 43
中精度概要文一致
EPS 27th Conference on Controlled Fusion and Plasma Physics
Plasma Physics and Controlled Fusion2000
中精度概要文一致
The variation of confinement with elongation and triangularity in ELMyH-modes on JET
P J Lomas, on behalf of the JET Joint Undertaking and the JET TeamPlasma Physics and Controlled Fusion2000
中精度概要文一致
前へ96 / 117次へ