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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

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

Japanese universities' activities for PFC development and PMI studies

Tomoaki Hino1998

Erosion behaviour of boron carbide under high-power pulsed fluxes of hydrogen plasma

J. Langner, J. Piekoszewski, M. Sadowski, G.P. Glazunov, J. Stanislawski1998

Hydrogen and helium retention properties of B4C and SiC converted graphites

Y Yamauchi, Y Hirohata, T Hino1998

Influence of high heat flux loading and irradiation on some promising candidate materials for the divertor structure

G.G. Bondarenko, Ya.Ya. Udris1998

Advanced solutions for beryllium and tungsten plasma-facing components

C Ibbott, R Jakeman, T Ando, P Chappuis, G Vieider1998

Thermal fluxes due to plasma-wall interactions: Experimental measurements and numerical analyses

P. Sonato, P. Zaccaria

1998

Experimental studies on the behavior of carbon-containing molecules in the boundary plasma

S. Matsuyama, K. Yamaguchi, S. Tanaka, M. Yamawaki1998

High heat flux tests of mock-ups for ITER divertor application

R Giniatulin, A Gervash, V.L Komarov, A Makhankov, N Yablokov1998

Design of the ITER EDA plasma facing components

A Cardella, S Chiocchio, K Ioki, G Janeschitz, L Giancarli1998

Development of a compact W-shaped pumped divertor in JT-60U

S. Sakurai, N. Hosogane, K. Masaki, K. Kodama, M. Morimoto1998

High heat flux testing of a HIP bonded first wall panel with built-in circular cooling tubes

T Hatano, S Suzuki, K Yokoyama, T Suzuki, H Takatsu1998

Development of plasma facing component for LHCD antenna

Sunao Maebara, Masami Seki, Yoshitaka Ikeda, Satoshi Suzuki, Tsuyoshi Imai1998

Enhancement of subcooled flow boiling critical heat flux for water in tubes with internal twisted tapes under one-sided-heating conditions

Fujio Inasak, Hideki Nariai1998

Numerical analysis of radiative heat flux on large helical device

Mitsuo Higano, Shigenao Maruyama, Toshiyuki Takagi1998

A vented pump limiter for the reversed field pinch RFX

High heat flux thermal–hydraulic analysis of ITER divertor and blanket systems

A.R Raffray, S Chiocchio, K Ioki, D Krassovski, R Tivey1998

BIE analysis of transient heat transfer driven by high heat flux

Takanobu Goto, Masaaki Suzuki1998

Distribution of ionized carbon during simulated plasma disruption using spectroscopy

Toshio Sukegawa, Koji Okamoto, Haruki Madarame1998

Study of material response in disruption simulation experiments with variable irradiation duration

V.N Litunovsky, A.A Drozdov, V.E Kuznetsov, I.B Ovchinnikov, V.A Titov1998

Disruption erosions of various kinds of tungsten

K Nakamura, S Suzuki, T Tanabe, M Dairaku, M Akiba1998

Response of plasma-facing materials to high transient heat loads in a tokamak

H. Bolt, T. Scholz, J. Boedo, K.H. Finken, J. Linke1998

On the utilization of high Z materials as a plasma facing component

T. Tanabe, M. Akiba, Y. Ueda, K. Ohya, V. Philipps1998

EU results on neutron effects on PFC materials

C.H. Wu, J.P. Bonal, H. Kwast, F. Moons, G. Vieider1998

Structural materials joints for ITER in-vessel components

G Le Marois, H Burlet, R Solomon, B Marini, L Briottet1998

Developments and high heat flux tests of divertor components for LHD

Y Kubota, N Noda, A Sagara, R Sakamoto, N Yoshida1998

Local island divertor for the new edge control scenario

A. Komori, N. Ohyabu, A.C. England, D.E. Greenwood, A. Iiyoshi1998

Design, fabrication and testing of an improved high heat flux element, experience feedback on steady state plasma facing components in Tore Supra

J Schlosser, P Chappuis, M Chatelier, A Durocher, E Tsitrone1998

Hydrogen retention properties of polycrystalline tungsten and helium irradiated tungsten

Tomoaki Hino, Kazunori Koyama, Yuji Yamauchi, Yuko Hirohata1998

Overview of the Japanese mock-up tests for ITER high heat flux components

M. Akiba, S. Suzuki1998

Overview of the EU small scale mock-up tests for ITER high heat flux components

G Vieider, V Barabash, A Cardella, P Chappuis, E Visca1998

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