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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

Citescore

3.7

最新論文

  • Planar coil design for the Helios stellarator fusion power plant
  • Equilibrium optimization of the Helios planar coil stellarator power plant
  • Core profile prediction and transport analysis of the Helios stellarator fusion power plant
  • Superconducting planar coils for magnetic field shaping in the Helios Stellarator
  • Design of the superconducting encircling coils for Helios, the planar coil stellarator
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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. Peterka
2017

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

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
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