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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

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1.7

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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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Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron

Makoto Kobayashi, Masashi Shimada, Chase N. Taylor, Dean Buchenauer, Yasuhisa Oya2019

Receiving inspection and tests of the ITER poloidal field #4 cryostat feed-through

Frederic Villecroze, Jean Louis Bersier, Theo Brilleman, Olivier Dumoulin, Lijun Wan2019

Sensitivity of fast ion losses to magnetic perturbations in the European DEMO

J. Varje, T. Kurki-Suonio, A. Snicker, K. Särkimäki, F. Villone2019

Structural verification and manufacturing procedures of the cooling system, for DEMO divertor target (OVT)

G. Mazzone, J-H. You, V. Cerri, D. Coccorese, V. Imbriani2019

Experimental studies of the arc chamber short circuit failure mechanism on the DIII-D neutral beam system

B.J. Crowley, J.P. Beckers, M. Velasco Enriquez, R. Jaspers, T. Wijkamp2019

Study on the endoscopic inspection of ITER thermal shield cooling pipes

Kwanwoo Nam, Namil Her, Won Woo Park, Jong Moon Won, Dong Kwon Kang2019

High temperature microstructural stability of self-passivating W-Cr-Y alloys for blanket first wall application

Elisa Sal, Carmen García-Rosales, Iñigo Iturriza, Iñigo Andueza, Nerea Burgos2019

Enhancements in the structural integrity assessment of plasma facing components

Mike Fursdon, Muyuan Li, Jeong-Ha You2019

Improvements in physics models of AFSI-ASCOT-based synthetic neutron diagnostics at JET

Paula Sirén, Jari Varje, Henri Weisen, Luca Giacomelli, Massimo Nocente2019

Progress on reliability of remote maintenance concept for JA DEMO

Hiroyasu Utoh, Satoshi Kakudate, Ryoji Hiwatari, Youji Someya, Kenji Tobita2019

V&V analyses of the GEANT4 Monte Carlo code toolkit with computational and experimental fusion neutronics benchmarks

Elena Nunnenmann, Ulrich Fischer2019

Progress in nuclear analyses of the ITER TBM Port Plug with Dummy TBMs

Dieter Leichtle, Bastian Weinhorst, Anton Travleev, Lei Lu, Jaap van der Laan2019

Enhanced tritium production in fusion-fission hybrids for the external consumption

Vladimir I. Khripunov, Boris V. Kuteev, Alexey V. Zhirkin2019

Oxide layer formation in reduced activation ferritic steel F82H under DEMO reactor blanket condition

Keisuke Kimura, Jumpei Mochizuki, Seira Horikoshi, Moeki Matsunaga, Takumi Chikada2019

UWAVS first mirror after long plasma cleaning: Surface properties and material re-deposition issues

Andrey Ushakov, Ad Verlaan, Rob Ebeling, Chien-Ching Wu, Peter Verhoeff2019

LTCC magnetic sensors at EPFL and TCV: Lessons learnt for ITER

D. Testa, A. Corne, C. Jacq, T. Maeder, P. Windischofer2019

Standardized integration of ITER diagnostics Equatorial Port Plugs

J. Guirao, M.J. Walsh, V.S. Udintsev, S. Iglesias, A. Blanchard2019

Thermal, electromagnetic and structural analysis of gas baffles for the TCV divertor upgrade

Dario Vaccaro, H. Elaian, H. Reimerdes, M. Baquero, M. Toussaint2019

Strain distribution in the Nb3Sn rectangular wind and react conductor of the European DEMO project, determined by inductive measurements

Chiarasole Fiamozzi Zignani, Luigi Muzzi, Andrea Augieri, Valentina Corato, Davide Uglietti2019

Investigation on the in-situation pipe bending tool for the sector sub-assembly of ITER thermal shield

Kyoung-O Kang, Chang Hyun Noh, Junyoung Hur, Kwanwoo Nam, Dong Kwon Kang2019

Progress in the design of MITICA control and interlock systems

Adriano Luchetta, Nicola Pomaro, Gabriele Manduchi, Cesare Taliercio, Carmelo Vincenzo Labate2019

Progress of the EU activities for the ITER Divertor Inner Vertical Target procurement

Bruno Riccardi, Pierre Gavila, Jose’ Andrade, Frederic Escourbiac, Vladimir Kuznetcov2019

Analysis of supercritical CO2 Brayton power cycles in nuclear and fusion energy

Jan Syblik, Ladislav Vesely, Slavomir Entler, Jan Stepanek, Vaclav Dostal2019

Key conception of the remote maintenance for the target assembly of Advanced Fusion Neutron Source (A-FNS)

Makoto M. Nakamura, S. Sato, M. Ohta, C. Park, A. Kasugai2019

Electrical integration of two 1MW/2s dual-frequency gyrotrons into the EC-system of the TCV tokamak

U. Siravo, S. Alberti, J. Dubray, D. Fasel, A. Perez2019

Cernavoda tritium removal facility: A key tritium supplier for future fusion facilities

Liviu Stefan, Nicolae Trantea, Anisia Bornea, Marius Zamfirache, Iuliana Stefan2019

Integrated power exhaust modelling for DEMO with lithium divertor

M. Poradziński, I. Ivanova-Stanik, G. Pełka, V. Pericoli Ridolfini, R. Zagórski2019

NI P2P powered multi FPGA real-time data processing on tokamak diagnosis systems

Wei Zheng, Xueqing Zhao, Ming Zhang, Feiran Hu, Yuan Pan2019

The ITER In-Vessel Coils – design finalization and challenges

Alexander Vostner, Vincent Bontemps, Anna Encheva, Huan Jin, Vladimir Tronza2019

SPIDER gas injection and vacuum system: From design to commissioning

S. Dal Bello, M. Fincato, M. Breda, L. Grando, F. Siroti2019

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