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

Progress in the development of the ITER baseline scenario in TCV

B Labit, O Sauter, T Pütterich, F Bagnato, Y Camenen, S Coda, C Contré, R Coosemans, F Eriksson, O FévrierPlasma Physics and Controlled Fusion2024

高精度タイトル一致

Radwaste analysis and package optimization with the F4E-radwaste tool and application to the ITER IVVS

Alvaro Cubi, Raul Pampin, Marco Fabbri, Gregory Dubus, Alfredo de BlasFusion Engineering and Design2024

高精度タイトル一致

Dust contamination of Divertor Remote Handling System in ITER Hot Cell: A novel approach to model complex superficial radiation sources

P. Martínez-Albertos, P. Sauvan, J.P. Catalán, F. Javier, R. JuárezFusion Engineering and Design2024

信頼度別論文数

高精度

3,677

低精度

786

中精度

1,370

高精度タイトル一致

Applicability of the ITER-like EC HVPS design to the DEMO ECS

D. Fasel, J. Dubray, A. Ferro, T. Franke, D. VelascoFusion Engineering and Design2024

高精度タイトル一致

The diagnostic rack design and the functional demonstration of the locking mechanism for ITER diagnostic lower port integrations

Suguru Tanaka, Jaemin Kim, Heejin Shim, Daniel Nagy, Kimihiro IokiFusion Engineering and Design2024

高精度タイトル一致

Erosion resistance test of SiC mirror sample for ITER divertor VUV spectrometer

Boseong Kim, Kil-Byoung Chai, Jae-Sun Park, Changrae Seon, Xavier BonninFusion Engineering and Design2024

高精度タイトル一致

Radiation environment in ITER tokamak equatorial port 11

Roman Afanasenko, Konstantin Vukolov, Evgeny Andreenko, Ilya Orlovskiy, Roman RodionovFusion Engineering and Design2024

高精度タイトル一致

Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage

D. Terentyev, M. Wirtz, T.W. Morgan, T. Nozawa, J. ElenbaasFusion Engineering and Design2024

高精度タイトル一致

RAMI analysis of ITER diagnostic radial neutron camera

Danilo Nicola Dongiovanni, Francesco Belli, Giorgio Brolatti, Cristina Centioli, Tonio PinnaFusion Engineering and Design2024

高精度タイトル一致

Modelling of NBI shine-through in ITER non-nuclear phase to limit heat fluxes on first wall

P. Vincenzi, M. Schneider, A. SnickerFusion Engineering and Design2024

高精度タイトル一致

Overview of tritium management in WCLL test blanket system of ITER

Luigi Candido, Antonio Aiello, Stefano La Rovere, Carlos Moreno, Italo RicapitoFusion Engineering and Design2024

高精度タイトル一致

ITER DMS fast shutter development and laboratory testing

D.I. Réfy, A. Zsákai, E. Walcz, D. Oravecz, F. AuricaneFusion Engineering and Design2024

高精度タイトル一致

Preparation for Korean procurement scope of ITER sealing flanges

G.H. Kim, C.K. Park, Y.J. Jung, M.S. Ha, V. BarabashFusion Engineering and Design2024

高精度タイトル一致

Investigation on the pressure drop characteristics of ITER thermal shield cooling pipes

Kwanwoo NamFusion Engineering and Design2024

高精度タイトル一致

Design and manufacturing of tritium-carrier process pipes and associated guard-pipe for ITER Test Blanket Systems

R. Pascal, P. Avigni, J.F. Berenguer, I. Blain, L. ZhangFusion Engineering and Design2024

高精度タイトル一致

Nuclear analyses for the ITER Diagnostic Equatorial Port 8

A. Colangeli, A. Chaudhary, D. Flammini, N. Fonnesu, R. VillariFusion Engineering and Design2024

高精度タイトル一致

Structural and thermal fluid dynamics analyses of the ITER Pressure Suppression System considering no stable steam condensation regimes

Luca Berti, Alessio Pesetti, Francesco d'Errico, Donato AquaroFusion Engineering and Design2024

高精度タイトル一致

Final opto-mechanical design of ex-vessel components for the Wide Angle Viewing System diagnostic for ITER Equatorial Port 12

M. Medrano, C. Pastor, A. Soleto, R. Carrasco, J.J. PiquerasFusion Engineering and Design2024

高精度タイトル一致

Final design analysis of the optical hinge of the wide angle viewing system for ITER equatorial port 12

S. Cabrera, E. Rincón, M. Medrano, F.Le Guern, E. RodríguezFusion Engineering and Design2024

高精度タイトル一致

Fast Shutter optioneering study for the ITER Disruption Mitigation System

A. Zsákai, D.I. Réfy, E. Walcz, D. Nagy, S. JachmichFusion Engineering and Design2024

高精度タイトル一致

Nuclear analyses in support of ITER ex-port Radial Neutron Camera design

Fabio Moro, Daniele Marocco, Francesco Belli, Dariusz Bocian, Basilio EspositoFusion Engineering and Design2024

高精度タイトル一致

Thermo-mechanical analysis of the components in the launcher transmission line of ITER ex-port plug collective Thomson scattering

Esther Rincón Rincón, Emilio Blanco, Mercedes Medrano, Juan José Imaz, Stefan SchmuckFusion Engineering and Design2024

高精度タイトル一致

Nuclear analyses for the integration of ITER equatorial Port 2

S. Noce, R. Villari, A. Colangeli, D. Flammini, I. WyssFusion Engineering and Design2024

高精度タイトル一致

Design of a Plasma neutraliser for a Fusion reactor or as an upgrade to the ITER heating neutral beam injectors

R S Hemsworth, P VeltriFusion Engineering and Design2024

高精度タイトル一致

Total ionizing dose estimation of ITER upper port remote handling equipment

Shanshuang Shi, Chang-Hwan Choi, Taku Yokoyama, Hongtao PanFusion Engineering and Design2024

高精度タイトル一致

MARTe2 on ARM platforms integration challenges: An asymmetric multiprocessing approach for the ITER magnetics diagnostics

Giuseppe Avon, Arturo Buscarino, Eliana De Marchi, Luigi Fortuna, Fabio ZanonFusion Engineering and Design2024

高精度タイトル一致

Assessment of the relevancy of ENEA Water Loop facility with respect to ITER WCLL TBS Water Cooling System by considering their thermal-hydraulic performances

B. Gonfiotti, C. Ciurluini, F. Giannetti, P. Arena, A. Del NevoFusion Engineering and Design2024

高精度タイトル一致

Mechanical design of a Fast Shutter for the ITER disruption mitigation system

R.L. Csiszár, A. Zsákai, D.I. Réfy, E. Walcz, S. JachmichFusion Engineering and Design2024

高精度タイトル一致

Concept of operation of the Agile Robot Transporter for ITER in-vessel maintenance

Chang-Hwan Choi, Raphael Hery, Jim PalmerFusion Engineering and Design2024

高精度タイトル一致

Key technologies of manufacturing and testing for the ITER blanket shield block

Sa-Woong Kim, Si-Kun Chung, Jun-Sung Chang, Duck-Hoi Kim, Ki-Jung JungFusion Engineering and Design2024

高精度タイトル一致

First principles simulation of early stage plasma initiation process in ITER-scale tokamak

Junxian Chew, Paul Gibbon, Dirk Brömmel, Tom Wauters, Yuri Gribov, Peter de VriesNuclear Fusion2024

高精度タイトル一致

Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall

Y. Torikai, G. Kikuchi, A. Owada, S. Masuzaki, T. Otsuka, N. Ashikawa, M. Yajima, M. Tokitani, Y. Oya, S.E. LeeNuclear Fusion2024

高精度タイトル一致

Exploration of ITER operational space with as-built stiffness of central solenoid modules

S.H. Kim, S.C. McIntosh, Y. Gribov, A. Loarte, A.R. Polevoi, M. Dubrov, A.A. Kavin, V.E. Lukash, R.R. Khayrutdinov, T.A. CasperNuclear Fusion2024

高精度タイトル一致

3D effects on hydrogen transport in ITER-like monoblocks

Rémi Delaporte-Mathurin, Romain Chochoy, Jonathan Mougenot, Yann Charles, Etienne A. Hodille, Christian GrisoliaNuclear Fusion2024

高精度タイトル一致

Impact of gas injection location and divertor surface material on ITER fusion power operation phase divertor performance assessed with SOLPS-ITER

Jae-Sun Park, Xavier Bonnin, Richard Pitts, Jeremy LoreNuclear Fusion2024

高精度タイトル一致

Impact of breech geometry and propellant flow on the release of large pellets for the ITER disruption mitigation system

T.E. Gebhart, L.R. Baylor, M. Dibon, M.N. Ericson, E.J. Felske, S.S. Frank, W.L. Gardner, A.G. Ghiozzi, S. Jachmich, U. KrueziNuclear Fusion2024

高精度タイトル一致

First numerical analysis of runaway electron generation in tungsten-rich plasmas towards ITER

J. Walkowiak, M. Hoppe, I. Ekmark, A. Jardin, J. Bielecki, K. Król, Y. Savoye-Peysson, D. Mazon, D. Dworak, M. ScholzNuclear Fusion2024

高精度タイトル一致

Overview of advances in ASDEX Upgrade plasma control to support critical physics research for ITER and beyond

O. Kudlacek, P. David, I. Gomez, A. Gräter, B. Sieglin, W. Treutterer, M. Weiland, T. Zehetbauer, M. Van Berkel, M. BernertNuclear Fusion2024

高精度タイトル一致AI要約あり

Correlation of source parameters and beam properties in the early operation of the full size ITER negative ion beam source

M. Ugoletti, M. Agostini, C. Poggi, E. Sartori, G. Serianni, B. ZaniolNuclear Fusion2024

高精度タイトル一致AI要約あり

Validation of SOLPS-ITER simulations against the TCV-X21 reference case

Y. Wang, C. Colandrea, D.S. Oliveira, C. Theiler, H. Reimerdes, T. Body, D. Galassi, L. Martinelli, K. Lee, the TCV TeamNuclear Fusion2024

高精度タイトル一致AI要約あり

Lessons learned from European and Japanese production of ITER toroidal field coils

T. Hemmi, B. Bellesia, S. Hasegawa, P. Aprili, A. Bonito Oliva, E. Boter, M. P. Casas, M. Cornelis, K. Gomikawa, R. HarrisonNuclear Fusion2024

高精度タイトル一致AI要約あり

Prediction of pellet mass thresholds for ELM triggering in low-collisionality, ITER-like discharges

A. Wingen, R.S. Wilcox, B.C. Lyons, L.R. Baylor, N.M. FerraroNuclear Fusion2024

高精度タイトル一致AI要約あり

COREDIV simulations of D and D–T high current–high power Baseline pulses in JET-ITER like wall

G. Telesca, A.R. Field, I. Ivanova-Stanik, S. Brezinsek, A. Chomiczewska, D. Frigione, L. Garzotti, E. Kowalska-Strzeciwilk, P. Lomas, J. MaillouxNuclear Fusion2024

高精度タイトル一致AI要約あり

Error field detection and correction studies towards ITER operation

L. Piron, C. Paz-Soldan, L. Pigatto, P. Zanca, O. Sauter, T. Putterich, P. Bettini, M. Bonotto, G. Cunningham, G. De TommasiNuclear Fusion2024

高精度タイトル一致AI要約あり

Tritium management in ITER test blanket systems port cell for maintenance operations

Yingwu Jiang, Jiewei Wu, Fuhao Ji, Yuqing Wang, Muyi Ni, Man JiangNuclear Fusion2024

高精度タイトル一致AI要約あり

Multi-machine benchmark of the self-consistent 1D scrape-off layer model DIV1D from stagnation point to target with SOLPS-ITER

G L Derks, E Westerhof, M van Berkel, J H Jenneskens, J T W Koenders, S Mijin, D Moulton, H Reimerdes, H WuPlasma Physics and Controlled Fusion2024

高精度タイトル一致

Impact of increasing plasma-wall gap on plasma response to RMP fields in ITER

X Bai, A Loarte, Y Q Liu, S D Pinches, F Koechl, L Li, M Dubrov, Y GribovPlasma Physics and Controlled Fusion2024

高精度タイトル一致

An optimization method for ITER radial x-ray camera line-of-sight design basing on Bayesian uncertainty analysis

Sen Xu, Tianbo Wang, Raphael Tieulent, Damien Colette, Didier Mazon, Geert Verdoolaege, Jiquan LiPlasma Physics and Controlled Fusion2024

高精度タイトル一致

Thermal-hydraulic assessment of the ITER IBED PHTS

E. Vallone, G. Agnello, L. Basili, A. Ciampichetti, F.L. VenturiFusion Engineering and Design2024

高精度タイトル一致

High heat flux components with beryllium armour: From the small-scale mock-ups to the full-scale prototype of the ITER first wall panel

P.Yu. Piskarev, А.А. Gervash, D.A. Glazunov, E.V. Okuneva, V.V. LevichevFusion Engineering and Design2024

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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