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Fusion Engineering and Design

Fusion Engineering and Design

An International Journal for Fusion Energy and Technology devoted to Experiments, Theory, Methods and Design

公式サイト

Impact Factor

1.7

Citescore

3.7

最新論文

  • Corrigendum to “Improving the Newton cooling model to drive the optimization method for heterogeneous storage of ECRH hot data” [Fusion Engineering and Design 215 (2026) 115715]
  • Corrigendum to “Relativistic effects on stopping power of plasmas with heavy ions” [Fusion Engineering and Design 205 (2024), 114524]
  • Corrigendum to “Initial accident scenario analysis in support of a preliminary DEMO tritium plant design” [Fusion Engineering and Design 189 (2023) 113482]
  • Thermal behaviour of ZrCo getter beds during hydrogen absorption at variable flow rates and concentrations
  • Performance of the W7-X ECRH gyrotron diamond output window at 2 MW operation
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全 15,142 件の論文
並び順:新しい順古い順被引用数順

Study of separation factor and product extraction ratio in hydrogen isotope separation with displacement chromatography

Yuting Liu, Wenqing Wu, Guanghui Zhang, Manquan Fang, Tao Tang2021

Concept design of the control method for the NBI acceleration grid power supply-conversion system of CFETR

Dongyu Wang, Shu Yang, Ming Zhang, Shaoxiang Ma, Yuan Pan2021

WEST operation with real time feed back control based on wall component temperature toward machine protection in a steady state tungsten environment

R. Mitteau, C. Belafdil, C. Balorin, X. Courtois, B. Santraine2021

Radioactivation analysis of 14 MeV neutron generator facility

H.L. Swami, S. Vala, M. Abhangi, Ratnesh Kumar, R. Srinivasan2021

Plasma irradiation experiment on the metal pebble flow in the TPDsheet-U

Takeru Ohgo, Takuya Goto, Toshikio Takimoto, Akira Tonegawa, Junichi Miyazawa2021

Real-time feedback control system for ADITYA-U horizontal plasma position stabilisation

Rohit Kumar, Pramila Gautam, Shivam Gupta, R.L. Tanna, Y.C. Saxena2021

Feasibility study on tritium recoil barrier for neutron reflectors of research and test reactors

Inesh Kenzhina, Etsuo Ishitsuka, Hai Quan Ho, Naoki Sakamoto, Yevgeni Chikhray2021

RF discharge mirror cleaning system development for ITER diagnostics

Pavel Shigin, Nikita Babinov, Gregory De Temmerman, Alessandro Danisi, Michael Walsh2021

Development of bolting tool for remote handling of ITER first wall central bolt

Yuto Noguchi, Kentaro Nakata, Nobukazu Takeda2021

Poloidal distribution of penalty factors for DEMO Single Module Segment with limiters in normal operation

M.L. Richiusa, W. Arter, M. Firdaouss, J. Gerardin, Z. Vizvary2021

ITER assembly phase: Progress toward first plasma

Bernard Bigot2021

Pressure suppression system influence on vacuum vessel thermal-hydraulics and on source term mobilization during a multiple first Wall – Blanket pipe break

Matteo D’Onorio, Gianfranco Caruso2021

Parametric study of the TF coil design for the European DEMO

Rainer Wesche, Xabier Sarasola, Roberto Guarino, Kamil Sedlak, Pierluigi Bruzzone2021

Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident

Cristiano Ciurluini, Fabio Giannetti, Emanuela Martelli, Alessandro Del Nevo, Gianfranco Caruso2021

Current status of tokamak T-15MD

P.P. Khvostenko, I.O. Anashkin, E.N. Bondarchuk, A.N. Chudnovsky, A.V. Sushkov2021

Experimental results of multiple shattered pellet injection systems in KSTAR

SooHwan Park, KunSu Lee, HyunMyung Lee, JaeIn Song, SiWoo Yoon2021

Fabrication technologies implemented for the European test blanket modules: Status for HCPB and WCLL

Laurent Forest, Noel Thomas, Laurence Cogneau, Jérôme Tosi, Melchior Simon-Perret2021

Heat pipe technology based divertor plasma facing component concept for European DEMO

Wen Wen, Bradut-Eugen Ghidersa, Wolfgang Hering, Jörg Starflinger, Robert Stieglitz2021

Current status and future perspectives of EU ceramic breeder development

Oliver Leys, Julia M. Leys, Regina Knitter2021

Hydrogen safety retrofit of ASDEX Upgrade pellet centrifuge - Explosion prevention on fuelling devices

B. Ploeckl, M. Sochor, A. Herrmann, S. Kilian, M. Uhlmann2021

Towards a 1.5 MW, 140 GHz gyrotron for the upgraded ECRH system at W7-X

Konstantinos A. Avramidis, Zisis C. Ioannidis, Gaetano Aiello, Patrick Bénin, Robert C. Wolf2021

Performance of exhaust detritiation system for a fusion test device in the initial phase of the operation

Masahiro Tanaka, Naoyuki Suzuki, Hiromi Kato, Hiroki Chimura2021

1 MV power supplies integration issues in MITICA experiment, the ITER Heating Neutral Beam Injector prototype

Marco Boldrin, Matteo Valente, Samuele Dal Bello, Luca Grando, Andrea Garbuglia2021

Preliminary studies for the conceptual design of the quench detection system for the DTT TF superconducting magnets

Chiarasole Fiamozzi Zignani, Giuseppe Messina, Luigi Morici2021

Monitoring the plasma radiation profile with real-time bolometer tomography at JET

Diogo R. Ferreira, Pedro J. Carvalho, Ivo S. Carvalho, Chris Stuart, Peter J. Lomas2021

The redesign and implementation of data acquisition and control system for EAST NBI

Yu Gu, Xiaodan Zhang, Yuanzhe Zhao, Yong Xie2021

ECRH system upgrade design using dual frequency gyrotrons for EAST

Handong Xu, Weiye Xu, Dajun Wu, Miaohui Li, Tao Zhang2021

Analysis of fusion propulsion system for Earth-to-Mars mission

Jun Song, Zhibin Chen, Qiusun Zeng, Yunqing Bai, Yican Wu2021

Operating scenario of 3GWth class FFHR power plant with bypass controlled supercritical CO2 gas turbine power generation system

S. Ishiyama, H. Chikaraishi, A. Sagara2021

Fabrication of an ultrafine-grained W-ZrC-Re alloy with high thermal stability

B.L. Zhao, Z.M. Xie, R. Liu, H. Wang, Changan Chen2021
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