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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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Author index to volume 5

Treatment and disposal of tritium containing waste at mound

Michael L. Rogers1987

Quick replacement of the fusion core parts in a cassette compact toroid reactor

M. Nishikawa, E. Tachibana, K. Watanabe, T. Narikawa, S. Toda1987

Management of tritium-contaminated wastes at the ethel facility: Future trends for routine management practices and experimental research activities

F. Mannone, H. Dworschak1987

Concept of a blanket first wall supported by radial tubes

The impact of D—3He fusion reactors on waste disposal

W.F. Vogelsang, H.Y. Khater1987

Processing and waste disposal needs for fusion breeder blankets systems

P.A. Finn, S. Vogler1987

Simulation studies on plasma position control for the next generation tokamak machines with up-down asymmetry

Masao Kasai, Akihisa Kameari, Fushiki Matsuoka, Kichiro Shinya, Noboru Fujisawa1987

Conditioning and handling of tritiated wastes at Canadian nuclear power facilities

L.S. Krochmalnek, J.P. Krasznai, M. Carney1987

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

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

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