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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.

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

関連論文数 5,884 件

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ジャーナル別論文数

FED
NF
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年別論文数推移

高精度マッチ高精度50件

Manufacture study of ITER radial X-ray camera
Kaiyun Chen, Liqun Hu, Hong Yu, Hongrui Cao, Zhina ZhangFusion Engineering and Design2025
高精度タイトル一致
Characterization of a new 4He scintillator detector prototype for the ITER Radial Neutron Camera
S. Cesaroni, D. Marocco, V. Anagnostopoulou, F. Belli, B. EspositoFusion Engineering and Design2025
高精度タイトル一致
Design, development and manufacture of the ITER Torus and cryostat cryopumps
Robert Pearce, J. Buckerfield, A. Iannetti, F. Chitu, J. ZeutschelFusion Engineering and Design2025
高精度

信頼度別論文数

高精度

3,700

低精度

794

中精度

1,390

最新論文

Fusion Engineering and Design2026

Allowable misalignment tolerances for the ITER actively cooled tungsten first wall under edge heat loads

M.L. Richiusa, S. Nicolici, R. Hunt, S. Carpentier-Chouchana

Plasma Physics and Controlled Fusion2026

Dynamics of ion temperature gradient modes in burning plasma conditions in the presence of energetic particles

R Ivanov, A Biancalani, A Bottino, D Gossard, T Hayward-Schneider, A Mishchenko, R Wu

Plasma Physics and Controlled Fusion2026

Angular emission of scintillators for nuclear fusion diagnostics

Mauricio Rodríguez-Ramos, Javier González-Martín, Micaela Videla-Trevin, Alex Reyner-Viñolas, Pablo Alvarez-Frau, Martin Kocan, Javier García-López

タイトル一致
Implications of the measured BRDF for the ITER divertor impurity monitor
Hiroki Natsume, Kunpei Nojiri, Shin Kajita, Hirohiko Tanaka, Yoshihiko NunoyaFusion Engineering and Design2025
高精度タイトル一致
Prediction and evaluation of measurement performances of imaging diagnostics for ITER wall protection
Marie-Helene Aumeunier, Alexis Juven, Priyanka Jena, Vincent Martin, Martin KocanFusion Engineering and Design2025
高精度タイトル一致
Development of an in-vessel special calibration light source for ITER divertor infrared thermography
Tomohiko Ushiki, Tatsuo Sugie, Hiroyuki Tachibana, Kosuke Shimizu, Yoshihiko NunoyaFusion Engineering and Design2025
高精度タイトル一致
Maintenance plan of the ITER Radial Neutron Camera: Verification and validation by virtual reality simulation
Enrico Occhiuto, Domenico Marzullo, Danilo Nicola Dongiovanni, Ugo Bonavolontà, Basilio EspositoFusion Engineering and Design2025
高精度タイトル一致
Study on the new manufacture of ITER vacuum vessel thermal shield
Kwanwoo Nam, Dongkwon Kang, Moohyun You, Myeongjun Kim, Kijung JungFusion Engineering and Design2025
高精度タイトル一致
Intermediate thermomechanical analysis and optimization of the ITER Upper port mounted bolometer camera
Z. Wang, N. Jaksic, H. Meister, A. Pataki, M.A. VillarejoFusion Engineering and Design2025
高精度タイトル一致
Application of virtual fitting in the manufacturing of the ITER European vacuum vessel sectors
Alessandro Lo Bue, Edoardo Pompa, Miguel Gonzalez Fernandez, Francesca Giovanna Lanzotti, Boris BellesiaFusion Engineering and Design2025
高精度タイトル一致
ITER progresses into new baseline
Pietro Barabaschi, Arnaud Fossen, Alberto Loarte, Alain Becoulet, Laban CoblentzFusion Engineering and Design2025
高精度タイトル一致
Effect of the plasma size on pedestal and global confinement and prediction for ITER with IMEP
T. Luda, C. Angioni, F. Stefanelli, C. Bourdelle, D. Fajardo, M. Dunne, E. Fable, G. TardiniNuclear Fusion2025
高精度タイトル一致AI要約あり
Predictive density profile control with discrete pellets, applied to integrated simulations of ITER
C.A. Orrico, M. van Berkel, T.O.S.J. Bosman, L. Ceelen, W.P.M.H. Heemels, F. Koechl, D. KrishnamoorthyNuclear Fusion2025
高精度タイトル一致AI要約あり
Corrigendum: SOLPS-ITER analysis of a proposed STEP double null geometry: impact of the degree of disconnection on power-sharing (2023 Nucl. Fusion 63 076032)
R.T. Osawa, D. Moulton, S.L. Newton, S. Henderson, B. Lipschultz, A. HudobaNuclear Fusion2025
高精度タイトル一致AI要約あり
Modeling the effects of wall particle recycling on divertor detachment and upstream SOL density flattening in HL-2A by SOLPS-ITER
Rui Wang, Hailong Du, Na Wu, Chaofeng Sang, Lei Xue, Jiaxian Li, Guoyao Zheng, Miao Xue, Xiao Song, Zhenhou WangPlasma Physics and Controlled Fusion2025
高精度タイトル一致AI要約あり
Performance study and comparison of vacuum RF circuits developed for first mirror plasma cleaning systems in ITER optical diagnostics
Andrey Ushakov, Cederik Meekes, Ulf Stephan, Olaff Steinke, Shobhit YadavFusion Engineering and Design2025
高精度タイトル一致
Scoping studies on ITER tungsten first wall and borated water in Vacuum Vessel
Alberto Bittesnich, Davide Laghi, Marco Fabbri, Alfredo PortoneFusion Engineering and Design2025
高精度タイトル一致
Design and line-of-sight optimization for vacuum vessel-mounted and divertor-mounted bolometer cameras in ITER
Joseba Baños, Maitane Amarika, Gorka Beaskoetxea, Iñigo Jon de Echebarrieta, Ulrich WalachFusion Engineering and Design2025
高精度タイトル一致
Electromagnetic loads calculation of the in-vessel optical box of the ITER erosion deposition monitor diagnostic system
Attila Bohm, Jeno Kadi, Tamas Turcsik, Miklos Palankai, Govind JagannathanFusion Engineering and Design2025
高精度タイトル一致
Thermal structural analyses during cool down of the ITER toroidal field coil in the magnet cold test bench
Valerio Tomarchio, Francesca Cau, José Lorenzo, María Mercedes Parody Guzmán, Ana VeleiroFusion Engineering and Design2025
高精度タイトル一致
Electromagnetic analysis on ITER first wall samples diagnostic with sub-modelling technique
I. Pagani, F. Lucca, G. Mariani, S. Iglesias, F. PenzelFusion Engineering and Design2025
高精度タイトル一致
ITER DMS fast shutter prototype testing
D.I. Réfy, A. Zsákai, E. Walcz, L.R. Csiszár, U. KrueziFusion Engineering and Design2025
高精度タイトル一致
Vibration testing of mechanical resilience of bolometer sensors and sensor holders under ITER-relevant conditions
H. Meister, L.C. Ingesson, N. Marques, A. Pataki, U. WalachFusion Engineering and Design2025
高精度タイトル一致
Design and qualification of a ceramic insulating break for ITER In-Vessel Coils
Davide Macioce, Alexander Vostner, Cristina Jimenez Aguinaga, Xabier Gomez Mitxelena, Ignacio Aviles SantillanaFusion Engineering and Design2025
高精度タイトル一致
Design of the cryogenic distribution system for the ITER disruption mitigation based on shattered pellet injection
S. Giors, F. Adong, O. Barana, A. Barturen Montes, A. RizzatoFusion Engineering and Design2025
高精度タイトル一致
Actuator management for the first ITER plasma operation campaign
O. Kudláček, W. Treutterer, I. Gomez Ortiz, P.T. Lang, L. ZabeoFusion Engineering and Design2025
高精度タイトル一致
Operation and remote collaboration tools in view of the ITER neutral beam test facility experimental campaigns
Nuno Cruz, Alastair Shepherd, Gabriele Manduchi, Cesare Taliercio, Adriano LuchettaFusion Engineering and Design2025
高精度タイトル一致
Angular distribution dependence of W migration on the ITER divertor from ERO2.0 simulations
F. Chang, D. Nishijima, M.I. Patino, M.J. Baldwin, J. Romazanov, W. Möller, G.R. TynanNuclear Fusion2025
高精度タイトル一致AI要約あり
Simulation of stochastic transport and deposition of seed runaway electrons during disruption mitigation
Yuxiang Sun, Bo Li, Feng Wang, Di Hu, Yue Yuan, Long Cheng, Yuhao Li, the JOREK TeamNuclear Fusion2025
高精度AI判定AI要約あり
Design of a closed V-shape slot X-divertor to improve divertor detachment and pumping in HL-3 with SOLPS-ITER
Hailong Du, Houyang Guo, Xavier Bonnin, Lei Xue, Jiaxian Li, Na Wu, Jinming Gao, Guoyao Zheng, Dezhen WangPlasma Physics and Controlled Fusion2025
高精度タイトル一致AI要約あり
Manufacturing Assessment of the Simplified Full-Scale Prototype of Diagnostics Shield Module (DSM) for Application of ITER Upper Port 18
Heejin Shim, Jaemin Kim, MunSeong Cheon, Sunil PakFusion Engineering and Design2025
高精度タイトル一致
Pellet fragmentation studies for the ITER disruption mitigation system
Gábor Kocsis, Gergely Bartók, Attila Buzás, Gábor Cseh, Michael LehnenFusion Engineering and Design2025
高精度タイトル一致
Plasma property investigations during negative ion beam extraction in a half-sized ITER NBI ion source at ELISE test facility
D. Yordanov, D. Wünderlich, R. Riedl, C. Wimmer, U. FantzFusion Engineering and Design2025
高精度タイトル一致
Formation of W+ions in collisions of low-energy H+, D+, T+ions with tungsten atoms in the ITER near-wall plasmaOpen Access
Inga Yu. Tolstikhina, V. P. ShevelkoPhysics of Plasmas2025
高精度タイトル一致
Integrated operation scenarios: Chapter 6 of the special issue: on the path to tokamak burning plasma operation
Yong-Su Na, Eugenio Schuster, Robert V Budny, Andrea M Garofalo, Sang-hee Hahn, Hyun-Tae Kim, Florian Koechl, Alexei R Polevoi, Jayson Barr, Matteo BaruzzoNuclear Fusion2025
高精度AI判定AI要約あり
Surface damages of ITER-like W/Cu monoblocks in the lower divertor of EAST
Yang Wang, Dahuan Zhu, Chuanshi Feng, Zongxiao Guo, Pengfei Zi, Changjun Li, Chuannan Xuan, Chunyu He, Wenxue Fu, Binfu GaoNuclear Fusion2025
高精度タイトル一致AI要約あり
Toroidal modeling of Alfvén eigenmodes excited by runaway electrons in DIII-D and ITER
Yueqiang Liu, Chang Liu, Andrey LvovskiyNuclear Fusion2025
高精度タイトル一致AI要約あり
Corrigendum: Runaway electron dynamics in ITER disruptions with shattered pellet injections (2024 Nucl. Fusion 64 086033)
O. Vallhagen, L. Hanebring, F.J. Artola, E. Nardon, T. Fülöp, M. Hoppe, L. Votta, S.L. Newton, I. PusztaiNuclear Fusion2025
高精度タイトル一致AI要約あり
Time variation of error field correction in ITER
X Bai, A Loarte, Y Gribov, J-K Park, Y Q Liu, S H Kim, M Pharr, N C Logan, S C Mcintosh, S D PinchesPlasma Physics and Controlled Fusion2025
高精度タイトル一致AI要約あり
Long pulse H-mode operation in JET-ITER like wall
E Lerche, D King, X Litaudon, S Brezinsek, E Joffrin, R Lobel, F Auriemma, M Beldishevski, N Balshaw, M BaruzzoPlasma Physics and Controlled Fusion2025
高精度タイトル一致AI要約あり
Design of universal bellows for ITER XRCS survey diagnostics
Avik Bhattacharya, Saroj Jha, Sanjeev Varshney, Sapna Mishra, Anil K. BhardwajFusion Engineering and Design2025
高精度タイトル一致
Thickness reduction of hydraulic connectors in ITER blanket shield block based on feasibility verification through mock-up testing
Ji-Young Jeong, Jun-Sung Chang, Sa-Woong Kim, Ji-Hoon Kim, Duck-Hoi KimFusion Engineering and Design2025
高精度タイトル一致
The design progress of neutral beam duct liner remote handling tool in ITER blanket remote handling system
Tomoyuki ITO, Yuto NOGUCHI, Nobukazu TAKEDAFusion Engineering and Design2025
高精度タイトル一致
ITER core plasma thomson scattering diagnostic collection optics design
M. Amarika, G. Beaskoetxea, A. Estevez, M. Roldán, J. PuigFusion Engineering and Design2025
高精度タイトル一致
Automated design rationalization of robot component geometry for ITER blanket remote handling system
Takuya Iwamoto, Yuto Noguchi, Nobukazu TakedaFusion Engineering and Design2025
高精度タイトル一致
The management and cascading of geometrical requirements from designer to manufacturer in the ITER life cycle
Gabriele D’Amico, Francisco Javier Fuentes, Andres Jimenez, Francesca Giovanna Lanzotti, Gianluca PicciFusion Engineering and Design2025
高精度タイトル一致
Impact of triangularity on edge transport and divertor detachment: a SOLPS-ITER study of TCV L-mode plasmas
F. Mombelli, A. Mastrogirolamo, E. Tonello, O. Février, G. Durr-Legoupil-Nicoud, M. Carpita, F. Subba, M. Passoni, the TCV Team, the EUROfusion Tokamak Exploitation TeamNuclear Fusion2025
高精度タイトル一致AI要約あり
Benchmarking the global particle balance of DIV1D with SOLPS-ITER simulations on the tokamak à configuration variable
G L Derks, S Kobussen, E Westerhof, S WiesenPlasma Physics and Controlled Fusion2025
高精度タイトル一致AI要約あり
Phase control of a wall-locked tearing mode in ITER-like cylindrical tokamak
Paolo Zanca, Giuseppe MarchioriPlasma Physics and Controlled Fusion2025
高精度タイトル一致AI要約あり
Simulation of shattered pellet injections with plasmoid drifts in ASDEX Upgrade and ITER
O Vallhagen, L Antonsson, P Halldestam, G Papp, P Heinrich, A Patel, M Hoppe, L Votta, the ASDEX Upgrade Team, the EUROfusion Tokamak Exploitation TeamPlasma Physics and Controlled Fusion2025
高精度タイトル一致AI要約あり
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