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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

Optimization of the first wall helium cooling system of the European DCLL using CFD approach

Tomáš Melichar, Otakar Frýbort, Ladislav Vála, Pavel Zácha, David Rapisarda2017

Remote handling of DEMO breeder blanket segments: Blanket transporter conceptual studies

Jonathan Keep, Steve Wood, Neelam Gupta, Matti Coleman, Antony Loving2017

Thermal-hydraulic behaviour of the DEMO divertor plasma facing components cooling circuit

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

Electromagnetic and structure analysis for EAST vacuum vessel with plasma facing components during VDE

Liu Sumei, Sun Jinxin, Lu Mingxuan, Lei Mingzhun, Pei Kun2017

Strong sub-surface plastic deformation induced by high flux plasma in tungsten

D. Terentyev, A. Dubinko, A. Bakaeva, G. De Temmerman2017

Validation of TOKES vapor shield simulations against experiments in the 2MK-200 facility

S. Pestchanyi, R.A. Pitts, V. Safronov2017

Tensile deformation behavior of tungsten fibre-reinforced tungsten composite specimens in as-fabricated state

H. Gietl, J. Riesch, J.W. Coenen, T. Höschen, R. Neu2017

Characterization of the cooling channels of First Wall Mock-up dedicated to the HCPB TBM qualification

A. Abou-Sena, L.V. Boccaccini, B.E. Ghidersa, K. Zinn2017

Effect of engineering constraints on charged particle wall heat loads in DEMO

F. Maviglia, G. Federici, R. Wenninger, R. Albanese, C. Lowry2017

Analysis results of the enhanced heat flux first wall panel elements

S. Tomilov, M. Sviridenko, A. Leshukov, Yu. Strebkov, R. Raffray2017

Development of force reconstruction method on EU ITER TBM based on strain measurements

Christian Zeile, Ivan A. Maione, Pattrick Calderoni2017

Secondary radiation damage and gas production in plasma facing materials under fusion neutron irradiation

Vladimir Khripunov2017

Progress in the initial design activities for the European DEMO divertor: Subproject “Cassette”

J.H. You, G. Mazzone, Ch. Bachmann, D. Coccorese, M. Zucchetti2017

Design of the divertor targets shielding frame of the HELCZA high heat flux experimental complex

P. Zacha, L. Vesely, J. Stepanek2017

Erosion and morphology changes of F82H steel under simultaneous hydrogen and helium irradiation

K. Yakushiji, H.T. Lee, M. Oya, M. Tokitani, Y. Ueda2017

Physics design study of the divertor power handling in 8 m class DEMO reactor

Kazuo Hoshino, Nobuyuki Asakura, Shinsuke Tokunaga, Yuki Homma, Kenji Tobita2017

Summary of the production of the divertor target elements of Wendelstein 7-X

J. Boscary, T. Friedrich, H. Greuner, W. Schulmeyer, G. Ehrke2017

Commissioning phase of high heat flux test facility HELCZA

R. Jílek, J. Prokůpek, P. Gavila, K. Samec, S. Neufuss2017

Status on the W monoblock type high heat flux target with graded interlayer for application to DEMO divertor

M. Richou, F. Gallay, I. Chu, M. Li, J.H. You2017

Time-resolved studies of deuterium release from lithium films exposed to water vapor

S.A. Krat, Yu M. Gasparyan, A.S. Popkov, A.A. Pisarev2017

ITER blanket manifold final design and validation

P. Edwards, B. Calcagno, P. Chappuis, C. Chaullier, R. Raffray2017

Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation

T. Kulsartov, I. Tazhibayeva, Yu. Ponkratov, Yu. Gordienko, E. Nesterov2017

Optimization of electron beam irradiation at HELCZA experiment

Jan Stepanek, Radek Skoda2017

Molten layer characteristics of W materials and film coated W by pulsed laser irradiation

Daisuke Inoue, Kenzo Ibano, Satoru Yoshikawa, Takeru Maeji, Yoshio Ueda2017

Thermal-hydraulic design of water cooled first wall of the fusion reactor under DEMO conditions

Phani Domalapally, Mattia Dellabiancia2017

Thermal performance augmentation by rib-arrays for helium-gas cooled First Wall applications

Sebastian Ruck, Benedikt Kaiser, Frederik Arbeiter2017

Mechanical analysis of WEST divertor support plate

T. Batal, F. Ferlay, S. Burles, S. Larroque, J. Bucalossi2017

Implementation of ferritic steel as in vessel wall: Lessons learnt and follow up

I. Zammuto, L. Giannone, A. Herrmann, A. Houben, S. Vorbrugg2017

Structural analysis of the W7-X cryopump during the superconducting coil fast discharge event

Z. Wang, G. Ehrke, B. Mendelevitch, J. Boscary, R. Stadler2017

Laser energy absorption coefficient and in-situ temperature measurement of laser-melted tungsten

T. Maeji, K. Ibano, S. Yoshikawa, D. Inoue, Y. Ueda2017
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