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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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全 15,241 件の論文
並び順:新しい順古い順被引用数順

Erosion of macrobrush tungsten armor after multiple intense transient events in ITER

B.N. Bazylev, G. Janeschitz, I.S. Landman, S.E. Pestchanyi2005

Development of an original active thermography method adapted to ITER plasma facing components control

A. Durocher, N. Vignal, F. Escourbiac, J.L. Farjon, F. Cismondi2005

Plasma sprayed tungsten-based coatings and their performance under fusion relevant conditions

Jiří Matějíček, Yoshie Koza, Vladimír Weinzettl2005

High temperature stresses in brazed Glidcop/W model structures of interest for ITER divertor technology

C. Braham, R. Coppola, C. Nardi, M. Valli2005

A mature industrial solution for ITER divertor plasma facing components: Hypervapotron cooling concept adapted to Tore Supra flat tile technology

F. Escourbiac, I. Bobin-Vastra, V. Kuznetsov, M. Missirlian, J. Schlosser2005

Conceptual design of a high temperature water-cooled divertor for a fusion power reactor

L. Giancarli, J.P. Bonal, A. Li Puma, B. Michel, J.F. Salavy2005

Development of a copper alloy to beryllium HIP bonding technology for the ITER first wall

P. Sherlock, A.T. Peacock, A.D. Mc Callum2005

An advanced He-cooled divertor concept: Design, cooling technology, and thermohydraulic analyses with CFD

T. Ihli, R. Kruessmann, I. Ovchinnikov, P. Norajitra, R. Giniyatulin2005

The new electron beam test facility JUDITH II for high heat flux experiments on plasma facing components

Patrick Majerus, Rainer Duwe, Takeshi Hirai, Winfried Kühnlein, Manfred Rödig2005

Activity of the European high heat flux test facility: FE200

I. Bobin-Vastra, F. Escourbiac, M. Merola, P. Lorenzetto2005

Preliminary analysis on a liquid lithium limiter in capillary porous system (CPS) configuration in view of a “litization” experiment on FTU tokamak

M.L. Apicella, G. Mazzitelli, V.B. Lazarev, E.A. Azizov, M. Roccella2005

Design, performance and construction of a 2 MW ion beam test facility for plasma facing components

H. Greuner, H. Bolt, B. Böswirth, T. Franke, R. Süß2005

Spectroscopic studies of homogeneous thin carbon erosion films on mirrors and flakes with a high deuterium content formed in tokamak T-10

N.Yu. Svechnikov, V.G. Stankevich, A.M. Lebedev, K.A. Menshikov, Yu. Kostetski2005

Vacuum plasma-sprayed tungsten on EUROFER and 316L: Results of characterisation and thermal loading tests

H. Greuner, H. Bolt, B. Böswirth, S. Lindig, S. Suzuki2005

EU R&D on divertor components

M. Merola, W. Dänner, M. Pick, The EU ITER Participating Team2005

Thermal modeling of W rod armor

R.E. Nygren2005

Critical heat flux testing on screw cooling tube made of RAFM-steel F82H for divertor application

K. Ezato, S. Suzuki, M. Dairaku, M. Akiba2005

Status of He-cooled divertor development for DEMO

P. Norajitra, R. Giniyatulin, N. Holstein, T. Ihli, B. Zeep2005

Testing of actively cooled mock-ups in several high heat flux facilities—An International Round Robin Test

M. Rödig, I. Bobin-Vastra, S. Cox, F. Escourbiac, D.L. Youchison2005

Design and thermal performance of an improved mechanically attached module for divertor plate of LHD

Y. Kubota, S. Masuzaki, T. Morisaki, K. Tokunaga, N. Noda2005

Manufacture of blanket shield modules for ITER

P. Lorenzetto, B. Boireau, C. Boudot, P. Bucci, S. Tähtinen2005

The MAST improved divertor

A.C. Darke, R.J. Hayward, G.F. Counsell, K. Hawkins2005

Manufacturing and testing in reactor relevant conditions of brazed plasma facing components of the ITER divertor

M. Bisio, V. Branca, M. Di Marco, A. Federici, F. Varone2005

Development of the plasma facing components for the dome-liner component of the ITER divertor

U. Luconi, M. Di Marco, A. Federici, M. Grattarola, G. Pasquale2005

The batch production for superconducting magnet coils of EAST (HT-7U)

Gao Daming, Chen Siyue, Yu Jie, Wu Jiefeng, Wu Yu2005

A low cost joint for the ITER PF coils, design and test results

B. Stepanov, P. Bruzzone, M. Vogel2005

130 kV 130 A high voltage switching mode power supply for neutral beam injectors—Control issues and algorithms

D. Ganuza, F. García, M. Zulaika, A. Perez, T.T.C. Jones2005

Fibreglass unidirectional composite to be used for ITER pre-compression rings

Claudio Nardi, Livio Bettinali, Aldo Pizzuto2005

Updating the design of the feeder components for the ITER magnet system

K. Yoshida, Y. Takahashi, T. Isono, N. Mitchell2005

Magnetic compatibility of standard components for electrical installations: Computation of the background field and consequences on the design of the electrical distribution boards and control boards for the ITER Tokamak building

I. Benfatto, P. Bettini, M. Cavinato, A. De Lorenzi, E. Serra2005
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