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

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

Locking Mechanism of Diagnostic Rack in ITER Lower Port #02

Suguru TANAKA, Toshiyuki MARUYAMA, Takaki HATAE, Kimihiro IOKIFusion Engineering and Design2023

高精度タイトル一致

Neutronic analyses for the equatorial diagnostic port plug #12 in ITER

D. Flammini, A. Chaudhary, A. Colangeli, N. Fonnesu, R. VillariFusion Engineering and Design2023

高精度タイトル一致

Demonstration of ITER Real-Time Framework with application of PF coil control in KSTAR

Seung-Ju Lee, Giil Kwon, Sang-won Yun, Taegu Lee, Taehyun TakFusion Engineering and Design2023

高精度

信頼度別論文数

高精度

3,677

低精度

786

中精度

1,370

Functional safety assessment process for MITICA safety system in the ITER neutral beam test facility

Luca Grando, Manuela Battistella, Samuele Dal Bello, Adriano Luchetta, Michele PicciniFusion Engineering and Design2023

高精度タイトル一致

China's progress on hot helium leak test of ITER shield blocks

Kun Wang, Zhen Leng, Jiming Chen, Tongzhen Fang, Min WangFusion Engineering and Design2023

高精度タイトル一致

Early design validation on the Vacuum Vessel ports sealing interface installation and removal with Virtual Reality in ITER TBM port cells

Chiara Di Paolo, Stéphane Gazzotti, Sarah Griffiths, Thibault Plantin de Hugues, Cyril KharouaFusion Engineering and Design2023

高精度タイトル一致

Computational study of the dose-rate field of an ITER heat exchanger due to activated corrosion products

M. De Pietri, P. Sauvan, J. Alguacil, Y. Le Tonqueze, R. JuarezFusion Engineering and Design2023

高精度タイトル一致

Manufacturing, testing and installation of the full tungsten actively cooled ITER-like divertor in the WEST tokamak

M. Missirlian, M. Firdaouss, M. Richou, C. Hernandez, B. ZagoFusion Engineering and Design2023

高精度タイトル一致

Tests on the prototype of the Optical Hinge for the Wide Angle Viewing System to ITER gamma radiation conditions

R. Carrasco, F. Lapayese, A. de la Peña, M. Medrano, J.J. PiquerasFusion Engineering and Design2023

高精度タイトル一致

Neutronics analysis of the visible infrared wide angle viewing system in equatorial port #12 of ITER

Yannick Peneliau, Jérémy Grosy, Christophe Guillon, Nicolas Lapcevic, Marco FabbriFusion Engineering and Design2023

高精度タイトル一致

A case study of the real-time framework for the implementation of the ITER plasma control system

W. Lee, T. Tak, A. Zagar, W. Van Herck, G PospelovFusion Engineering and Design2023

高精度タイトル一致

EMC and earthing concept of the ITER EC-system

U. Siravo, F. Albajar, D. Parmar, J. Dubray, D. VelascoFusion Engineering and Design2023

高精度タイトル一致

Construction of hot helium leak test facility for ITER blanket shield block

Jun-sung Chang, Sa-woong Kim, Si-kun Chung, Kwan-woo Nam, Ki-Jung JungFusion Engineering and Design2023

高精度タイトル一致

Compaction technology development for ITER In-vessel coil joints

Dapeng Yin, Houxiang Han, Huajun Liu, Yu Wu, Jing JinFusion Engineering and Design2023

高精度タイトル一致

ITER Central Solenoid Precompression Test Mock-up – Validation phase to prepare the assembly on-site

Cyril Brun, Clément Nguyen, Patrick Decool, Antoine Jonas, Kevin FreudenbergFusion Engineering and Design2023

高精度タイトル一致

Storing EPICS process variables in HDF5 files for ITER

R. Castro, Y. Makushok, L. Abadie, B. Bauvir, J. VegaFusion Engineering and Design2023

高精度タイトル一致

Optical design and stray RF investigation of ITER EC H&CD equatorial launcher using mockup

Satoru Yajima, Ken Kajiwara, Ryosuke Ikeda, Takahiro Shinya, Koji TakahashiFusion Engineering and Design2023

高精度タイトル一致

Development of the optical remote handling connector for ITER Divertor Operational Instrumentation

Janne Lyytinen, Petri Tikka, Jukka Koskinen, Mikko Karppinen, Sergey BenderFusion Engineering and Design2023

高精度タイトル一致

Advanced ultrasonic examination of heavy–gauge high strength studs for the ITER toroidal field gravity supports

I. Aviles Santillana, G. Arnau Izquierdo, S. Bonnin, M. Celuch, J.M. CouletFusion Engineering and Design2023

高精度タイトル一致

Instrumented fast valve for the ITER DMS support laboratory test bench

D.I. Réfy, S. Zoletnik, E. Walcz, D. Nagy, U. KrueziFusion Engineering and Design2023

高精度タイトル一致

Design updates of ITER Blanket Remote Handling System to accommodate in-vessel environment

Noguchi Yuto, Nakata Kentaro, Ito Tomoyuki, Takeda NobukazuFusion Engineering and Design2023

高精度タイトル一致

Development of sub-miniaturised testing methodology for W/Cu joints extracted from the ITER-specification monoblock

K. Poleshchuk, D. Terentyev, C.C. Chang, A. Galatanu, K. VerbekenFusion Engineering and Design2023

高精度タイトル一致

Nuclear scoping analysis of ITER bioshield top lid toward its preliminary design review

P. Martínez-Albertos, P. Sauvan, J. Bergman, M. Loughlin, R. JuárezFusion Engineering and Design2023

高精度タイトル一致

Review and down-selection of NDE technologies suitable for ITER cooling water system remote weld inspections

Kwame Akowua, Lee Aucott, David Waillis, Hery Raphael, Helena LiveseyFusion Engineering and Design2023

高精度タイトル一致

Procedure qualification and integration of the continuous external Rogowski diagnostics to the superconducting magnets of ITER tokamak

Y. Ma, M. Nakamoto, T. Sakurai, Y. Kiyoshi, M. WalshFusion Engineering and Design2023

高精度タイトル一致

Stress-strain curve mapping by nanoindentation – a technique to qualify diffusion-bonded window assemblies for ITER

Renato Pero, Nicholas Randall, Damian Frey, Remo N. Widmer, Andrew BushbyFusion Engineering and Design2023

高精度タイトル一致

Shut-down dose rate analysis for final design of shielding tent in port interspace of ITER UP#18

SeongHee Hong, Jaemin Kim, HeeJin Shim, MunSeong Cheon, Sunil ParkFusion Engineering and Design2023

高精度タイトル一致

Remote maintenance scenario of the caesium ovens and beam source of the ITER heating neutral beam

Chang-Hwan Choi, Carlo Damiani, Mikel Bilbao Gutierrez, Susagna Balague, Lorenzo AntolaFusion Engineering and Design2023

高精度タイトル一致

SOLPS-ITER numerical evaluation about the effect of drifts in a divertor configuration of ASDEX-Upgrade and a limiter configuration of J-TEXT

H. Wu, P. Shi, F. Subba, H. Sun, R. ZaninoFusion Engineering and Design2023

高精度タイトル一致

The final design of the ITER Interlock Discharge Loop Interface Boxes (DLIB) and its compliance with the IEC 61508 standard

I. Prieto Diaz, Y. Liu, R. Pedica, A. Marqueta, P.R. Moraga MontejoFusion Engineering and Design2023

高精度タイトル一致

Electromagnetic computer codes validation for ITER related analyses.

P. Testoni, F. Auricane, O. Biro, F. Cau, J. LorenzoFusion Engineering and Design2023

高精度タイトル一致

SOLPS-ITER simulations of an X-point radiator in the ASDEX Upgrade tokamak

O. Pan, M. Bernert, T. Lunt, M. Cavedon, B. Kurzan, S. Wiesen, M. Wischmeier, U. Stroth, the ASDEX Upgrade TeamNuclear Fusion2023被引用: 12

高精度タイトル一致

Evaluation of the functional acceptability of the ITER vacuum vessel

Hokyu Moon, Soo-Hyeon Park, Hyun-Soo Kim, Beom Seok KimNuclear Fusion2023被引用: 1

高精度タイトル一致

Beryllium melt instabilities and ejection during unmitigated current quenches in ITER

L. Vignitchouk, S. Ratynskaia, R.A. Pitts, M. LehnenNuclear Fusion2023被引用: 3

高精度タイトル一致

Numerical error analysis of SOLPS-ITER simulations of EAST

Dieter Boeyaert, Stefano Carli, Kristel Ghoos, Wouter Dekeyser, Sven Wiesen, Martine BaelmansNuclear Fusion2023被引用: 3

高精度タイトル一致

A reduced model for the ITER divertor based on SOLPS solutions for ITER Q = 10 baseline conditions: A. identifying options for the control parameters

P.C. Stangeby, J.D. Lore, R.A. Pitts, J.M. Canik, X. BonninNuclear Fusion2023被引用: 3

高精度タイトル一致

A reduced model for the ITER divertor based on SOLPS solutions for ITER Q = 10 baseline conditions: B. A reduced model based on reversed-direction two point modeling

P.C. Stangeby, J.D. Lore, R.A. Pitts, J.M. Canik, X. BonninNuclear Fusion2023被引用: 1

高精度タイトル一致

Kinetic modelling of start-up runaway electrons in KSTAR and ITER

Y. Lee, P.C. de Vries, P. Aleynikov, J. Lee, Y.-S. Lee, H.-T. Kim, A.B. Mineev, K.-D. Lee, J.-G. Bak, J.-W. JuhnNuclear Fusion2023被引用: 1

高精度タイトル一致

Divertor power load investigations with deuterium and tritium in type-I ELMy H-mode plasmas in JET with the ITER-like wall

M. Faitsch, I. Balboa, P. Lomas, S.A. Silburn, A. Tookey, D. Kos, A. Huber, E. de la Luna, D. Keeling, A. KappatouNuclear Fusion2023被引用: 1

高精度タイトル一致

Experiments in high-performance JET plasmas in preparation of second harmonic ICRF heating of tritium in ITER

M.J. Mantsinen, P. Jacquet, E. Lerche, D. Gallart, K. Kirov, P. Mantica, D. Taylor, D. Van Eester, M. Baruzzo, I. CarvalhoNuclear Fusion2023被引用: 7

高精度タイトル一致

Determining the access to H–mode in the ITER pre–fusion and fusion power operation phases at low plasma current with full–radius TGLF–SAT2 simulations of L–mode plasmas

C. Angioni, J. Citrin, A. Loarte, A.R. Polevoi, S.H. Kim, E. Fable, G. TardiniNuclear Fusion2023被引用: 1

高精度タイトル一致

ITER relevant multi-emissive sheaths at normal magnetic field inclination

P. Tolias, M. Komm, S. Ratynskaia, A. PodolnikNuclear Fusion2023被引用: 4

高精度タイトル一致

Implementation of SOLPS-ITER code with new Grad–Zhdanov module for D–T mixture

S.O. Makarov, D.P. Coster, E.G. Kaveeva, V.A. Rozhansky, I.Y. Senichenkov, I.Y. Veselova, S.P. Voskoboynikov, A.A. Stepanenko, X. Bonnin, R.A. PittsNuclear Fusion2023被引用: 6

高精度タイトル一致

Global SOLPS-ITER and ERO2.0 coupling in a linear device for the study of plasma–wall interaction in helium plasma

G. Alberti, E. Tonello, P. Carminati, A. Uccello, X. Bonnin, J. Romazanov, S. Brezinsek, M. PassoniNuclear Fusion2023

高精度タイトル一致

Quantifying electron cyclotron power deposition broadening in DIII-D and the potential consequences for the ITER EC system

J.H. Slief, R.J.R. van Kampen, M.W. Brookman, J. van Dijk, E. Westerhof, M. van BerkelNuclear Fusion2023被引用: 3

高精度タイトル一致

Parametric study of midplane gas puffing to maximize ICRF power coupling in ITER

W. Zhang, A. Messiaen, W. Helou, V. Bobkov, P. Lamalle, R.A. Pitts, W. TierensNuclear Fusion2023被引用: 1

高精度タイトル一致

Trends in runaway electron plateau partial recombination by massive H2 or D2 injection in DIII-D and JET and first extrapolations to ITER and SPARC

E.M. Hollmann, L. Baylor, A. Boboc, P. Carvalho, N.W. Eidietis, J.L. Herfindal, S. Jachmich, A. Lvovskiy, C. Paz-Soldan, C. ReuxNuclear Fusion2023被引用: 1

高精度タイトル一致

Self-consistent investigation of density fueling needs on ITER and CFETR utilizing the new Pellet Ablation Module

J. McClenaghan, L.L. Lao, P.B. Parks, W. Wu, J. Zhang, V.S. ChanNuclear Fusion2023被引用: 5

高精度タイトル一致

Recent modeling for the ITER ion cyclotron range of frequency antennas with the TOPICA code

D. Milanesio, W. Helou, V. Polli, F. Durodié, P. Lamalle, V. Maquet, A. Messiaen, W. Tierens, W. ZhangNuclear Fusion2023被引用: 1

高精度タイトル一致

Time-dependent SOLPS-ITER simulations of the tokamak plasma boundary for model predictive control using SINDy

J.D. Lore, S. De Pascuale, P. Laiu, B. Russo, J.-S. Park, J.M. Park, S.L. Brunton, J.N. Kutz, A.A. KaptanogluNuclear Fusion2023被引用: 6

高精度タイトル一致

ITER

トピックキーワード

装置分析

ジャーナル別論文数

年別論文数推移

高精度マッチ高精度50件

信頼度別論文数

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