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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

Design study of the “HIBLIC-I” reactor cavity

Y. Fujii-E, Y. Itoh, N. Nakamura, H. Nakashima, T. Suzuki1987

Experimental simulation of plasma disruption with an electron beam

Giordano Rigon, Pietro Moretto, Francesco Brossa1987

Liquid metal chemical reaction safety in fusion facilities

S.J. Piet, D.W. Jeppson, L.D. Muhlestein, M.S. Kazimi, M.L. Corradini1987

Rotating liquid blanket for a toroidal fusion reactor

R.W. Moir1987

The Dense Z Pinch as a fusion power reactor: Pressure vessel integrity and power density considerations

S.P. Walker, M. Javadi1987

Plasma engineering for the Next European Torus

N. Mitchell, E. Salpietro1987

Lifetime analysis for fusion reactor first walls and divertor plates

T. Horie, S. Tsujimura, A. Minato, T. Tone1987

Improvement of an electron beam facility as a heat source for disruption simulation experiments

Masahiro Seki, Seiichiro Yamazaki, Akio Minato, Tomoyoshi Horie, Tatsuzo Tone1987

A thermal cycling durability test of tungsten copper duplex structures for use as a divertor plate

M. Seki, M. Ogawa, A. Minato, K. Fukaya, N. Miki1987

Thermal shock tests of tungsten by H+-beam bombardment

M. Shibui, J. Ohmori, Y. Sawada, T. Kuroda, Y. Oka1987

Thermomechanical behavior of graphite and coating materials subjected to a high heat flux

K. Ioki, M. Yamada, M. Nishikawa, T. Uchikawa, H. Yamao1987

Analysis of the magnetomechanical behavior of a ferromagnetic beam plate

K. Miya, T. Rizawa, K. Someya, A. Minato, T. Tone1987

Application of the time—space finite element method to the thermomechanical analysis of the first wall

T. Teramae, H. Oomura, K. Miya, M. Akiyama1987

Thermomechanical behavior of the first wall subjected to plasma disruption

H. Hashizume, K. Miya, M. Seki, K. Ioki1987

The JT-60 diagnostic system

H. Yokomizo, H. Takeuchi, T. Sugie, N. Ogiwara, Y. Suzuki1987

The JT-60 radio-frequency heating system: description and R&D results

T. Nagashima, K. Uehara, H. Kimura, T. Imai, H. Shirakata1987

The JT-60 neutral beam injection system

S. Matsuda, M. Akiba, M. Araki, M. Dairaku, K. Watanabe1987

The JT-60 central control system

I. Kondo, T. Kimura, I. Yonekawa, K. Kurihara, Y. Suzuki1987

JT-60 power supplies

R. Shimada, M. Tsuneoka, T. Matsukawa, T. Aoyagi, S. Tamura1987

The JT-60 tokamak machine

M. Ohta, T. Abe, N. Akino, T. Ando, K. Yano1987

Construction and testing of JT-60

H. Kishimoto, H. Aikawa, A. Oikawa, N. Miya, R. Hosoda1987

An overview of the JT-60 project

M. Yoshikawa1987
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