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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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並び順:新しい順古い順被引用数順

Application of fracture mechanical assessment to in-wall shield ribs in ITER vacuum vessel

Yu-Gyeong Kim, Hyun-Soo Kim, Chul-Kyu Park, Gwang-Ho Kim, Yoon-Suk Chang2017

Thermal radiation analysis of DEMO tokamak

Boštjan Končar, Martin Draksler, Oriol Costa Garrido, Botond Meszaros2017

Progress in EU-DEMO in-vessel components integration

F. Cismondi, P. Agostinetti, G. Aiello, J. Aubert, C. Zeile2017

ADITYA upgrade vacuum vessel: Design, construction, testing, installation and operation

K.A. Jadeja, S.B. Bhatt, Kulav Rathod, K.M. Patel, D. Bora2017

The impact on remote maintenance of varying the aspect ratio and number of TF coils for DEMO

Dan Wolff, Matti Coleman, David Cooper, Oliver Crofts, Antony Loving2017

Specific design and structural issues of single crystalline first mirrors for diagnostics

Yury Krasikov, Anatoly Panin, Andrey Litnovsky, Philippe Mertens, Michael Schrader

2017

Irradiation tests of radiation hard materials for ITER blanket remote handling system

Makiko Saito, Hiroshi Kozaka, Takahito Maruyama, Yuto Noguchi, Satoshi Kakudate2017

Pre-assembly and dimensional inspection at factory of JT-60SA Cryostat Vessel Body Cylindrical Section

Santiago Cabrera, Mercedes Medrano, Javier Alonso, José Botija, Akira Sakasai2017

Accuracy improvement studies for remote maintenance manipulators

Yongbo Wang, Huapeng Wu, Heikki Handroos, Ming Li, Jonathan Keep2017

Qualification, manufacturing and assembly of the WEST divertor structure and coils

Louis Doceul, Jérôme Bucalossi, Francis Bouquey, Cyril Brun, Bertrand Zago2017

Design of a standalone joint module toward real EAST in-vessel operation use

Liang Du, Jiabo Feng, Tan Chen, Weijun Zhang2017

Analysis and experimental justification of electrical connector for ITER blanket module

I. Poddubnyi, V. Kolganov, V. Elkin, S. Khomiakov, R. Raffray2017

Engineering analyses of Divertor Thomson scattering system

Ivan Kirienko, Igor Buslakov, Victor Modestov, Alexander Nemov, Philip Andrew2017

Static stiffness modelling of EAST articulated maintenance arm using matrix structural analysis method

Shanshuang Shi, Huapeng Wu, Yuntao Song, Heikki Handroos, Bingyan Mao2017

Multiphysics engineering analysis for high field side reflectometry

A. Nemov, A. Novokshenov, A. Lagutkina, S. Sycheva, V. Lukyanov2017

Progress on the design development and prototype manufacturing of the ITER In-vessel coils

A. Encheva, H. Omran, A. Devred, A. Vostner, J. Jin2017

Application of unmanned aerial vehicles for radiological inspection

Alberto Vale, Rodrigo Ventura, Paulo Carvalho2017

Neutral beam remote cutting & welding development

Luke Thomson, Jerome Woodwark, Cameron Kennedy, Alex Muir, Chang-Hwan Choi2017

Local copper coating of the connectors of the divertor target elements of Wendelstein 7-X

P. Junghanns, J. Boscary, M. Busch, B. Mendelevitch, R. Stadler2017

Effect of steady state and ELMy heat loads on the PFC of DEMO

Yuri Igitkhanov, Renate Fetzer2017

Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules

J. Aubert, G. Aiello, P. Arena, R. Boullon, A. Morin2017

Design options to mitigate deep cracking of tungsten armor

Muyuan Li, Jeong-Ha You2017

Study of deuterium retention in Be-W coatings with distinct roughness profiles

R. Mateus, A. Hakola, V. Tiron, C. Porosnicu, E. Alves2017

Ablation properties of plasma facing materials using thermal plasmas

H. Kim, P.Y. Oh, B.R. Kang, H.M. Lim, B.G. Hong2017

Melt infiltrated tungsten–copper composites as advanced heat sink materials for plasma facing components of future nuclear fusion devices

A.v. Muller, D. Ewert, A. Galatanu, M. Milwich, J.H. You2017

Investigations on tungsten heavy alloys for use as plasma facing material

R. Neu, H. Maier, M. Balden, S. Elgeti, I. Zammuto2017

Dust remobilization experiments on the COMPASS tokamak

V. Weinzettl, J. Matejicek, S. Ratynskaia, P. Tolias, M. Peterka2017

Microwave response of ITER vacuum windows

Johan W. Oosterbeek, Philippe Maquet, Antoine Sirinelli, Victor S. Udintsev, Mike J. Walsh2017

Analysis of steady state thermal-hydraulic behaviour of the DEMO divertor cassette body cooling circuit

P.A. Di Maio, S. Garitta, J.H. You, G. Mazzone, E. Vallone2017

ITER-like divertor target for DEMO: Design study and fabrication test

F. Crescenzi, H. Greuner, S. Roccella, E. Visca, J.H. You2017

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