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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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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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Experimental estimate of tritium production parameters for RF test blanket module

V. Kapyshev, V. Kovalenko, V. Poliksha, A. Sidorov, N. Yukhnov2008

The modified RF concept of CHC experimental module for testing on H–H iter phase

A.Yu. Leshukov, V.K. Kapyshev, V.G. Kovalenko, S.A. Makarov, Yu.S. Strebkov2008

ITER blanket module shield block design and analysis

D. Mitin, S. Khomyakov, A. Razmerov, Yu. Strebkov2008

Current status on the detailed design and development of fabrication techniques for the ITER blanket shield block in Korea

Duck-Hoi Kim, Seungyon Cho, Mu-Young Ahn, Eun-Seok Lee, Do-Hyeong Kim2008

Structural material properties and dimensional stability of components in first wall components of a breeding blanket module

Takanori Hirose, Mikio Enoeda, Hiroyuki Ogiwara, Hiroyasu Tanigawa, Masato Akiba2008

Deuterium retention and desorption behavior of lithium titanate

T. Hino, D. Sato, Y. Yamauchi, H. Tanigawa, S. Suzuki2008

Preliminary design of Indian Test Blanket Module for ITER

E. Rajendra Kumar, C. Danani, I. Sandeep, Ch. Chakrapani, S.P. Deshpande2008

Current status of design and analysis of Korean Helium-Cooled Solid Breeder Test Blanket Module

Seungyon Cho, Mu-Young Ahn, Duck Hoi Kim, Eun-Seok Lee, Ki Jung Jung2008

The HCLL Test Blanket Module system: Present reference design, system integration in ITER and R&D needs

J.-F. Salavy, G. Aiello, O. David, F. Gabriel, K. Splichal2008

Overview of design and R&D of solid breeder TBM in China

K.M. Feng, C.H. Pan, G.S. Zhang, T. Yuan, Q.J. Wang2008

The MK III actively cooled duct liner for the JET neutral beam line: Thermo-mechanical performance and lifetime estimation

A. Li-Puma, T.T.C. Jones, Y. Krivchenkov, D. Martin, D.J. Wilson2008

Ex-situ tritium removal from JET tiles using RF inductive heating

N. Bekris, J.P. Coad, K. Sugiyama, C. Caldwell-Nichols, R. Rolli2008

Assessment of the He-cooled Test Divertor Module for ITER

V. Widak, P. Norajitra, L.V. Boccaccini, G. Janeschitz2008

Numerical investigation of a brazed joint between W-1%La2O3 and ODS EUROFER components

J. Reiser, P. Norajitra, R. Ruprecht2008

Development of modular helium-cooled divertor for DEMO based on the multi-jet impingement (HEMJ) concept: Experimental validation of thermal performance

J.B. Weathers, L. Crosatti, R. Kruessmann, D.L. Sadowski, S.I. Abdel-Khalik2008

Study on wall recycling behaviour in CPD spherical tokamak

R. Bhattacharyay, H. Zushi, Y. Hirooka, M. Sakamoto, A. Higashijima2008

A tritium diagnostic and trap for JUDITH—First results in disruption simulation experiments with neutron irradiated beryllium during cyclic electron beam testing

A. Schmidt, I. Uytdenhouwen, W. Kühnlein, M. Rödig, G. Pintsuk2008

Heat transfer enhancement in sphere-packed pipes under high Reynolds number conditions

Nao Seto, Kazuhisa Yuki, Hidetoshi Hashizume, Akio Sagara2008

Critical heat flux experiments using a screw tube under DEMO divertor-relevant cooling conditions

K. Ezato, S. Suzuki, M. Dairaku, M. Akiba2008

DNS of turbulent heat transfer under a uniform magnetic field at high Reynolds number

Shin-ichi Satake, Naoshi Yoshida, Tomoaki Kunugi, Kazuyuki Takase, Takuma Kano2008

The Sandia Plasma Materials Test Facility in 2007

J.M. McDonald, T.J. Lutz, D.L. Youchison, F.J. Bauer, R.E. Nygren2008

Experimental study of MHD effects on turbulent flow of Flibe simulant fluid in circular pipe

Junichi Takeuchi, Shin-ichi Satake, Neil B. Morley, Tomoaki Kunugi, Mohamed A. Abdou2008

Behaviour of melted tungsten plasma facing components under ITER-like transient heat loads: Simulations and experiments

B. Bazylev, G. Janeschitz, I. Landman, S. Pestchanyi, N. Klimov2008

Thermal load testing of erosion-monitoring beryllium marker tile for the ITER-Like Wall Project at JET

T. Hirai, J. Linke, M. Rubel, J.P. Coad, E. Wessel2008

Electromagnetic analysis of transient disruption forces on the ITER shield modules

J.D. Kotulski, R.S. Coats, M.F. Pasik2008

Aqueous corrosion in static capsule tests representing multi-metal assemblies in the hydraulic circuit of Tore Supra

M. Lipa, J. Blanchet, D. Feron, F. Cellier2008

Carbon removal in stainless steel wall and graphite sheet by using oxygen glow discharge

Takuya Nomura, Yuji Yamauchi, Yuko Hirohata, Tomoaki Hino2008

Simulation of dust production in ITER transient events

S.E. Pestchanyi, I.S. Landman2008

An overview of fuel retention and morphology in a castellated tungsten limiter

M.J. Rubel, G. Sergienko, A. Kreter, A. Pospieszczyk, E. Wessel2008

Temperature dependence of blistering and deuterium retention in tungsten exposed to high-flux and low-energy deuterium plasma

W.M. Shu, K. Isobe, T. Yamanishi2008

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