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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

Dynamic analysis of Compact Helical System power supply and designs of its upgrade

Shugo Tanahashi, Shuichi Yamada1992

Eddy current heating analysis of the ITER TF coil cases

A. Youtsos, L. Bottura1992

Pellet fueling system for ITER

M.J. Gouge, K.D. St. Onge, S.L. Milora, P.W. Fisher, S.K. Combs1992

Test results of X2242 and X2274 high power tetrodes with the JT-60 ICRF amplifier in a frequency range of 110–130 MHz

Shinichi Moriyama, Yoshiro Ogawa, Tsuneyuki Fujii, Katsuto Anno, Takayoshi Yamane1992

Plasma coupling test of the RF heating system in JT-60

K. Uehara, Y. Ikeda, M. Saigusa, K. Sakamoto, S. Shinozaki1992

Rectangular waveguide launchers for ion-cyclotron-resonance heating of tokamaks

A.B. Murphy1992

A self-cooled liquid metal blanket for a tokamak reactor

Haruki Madarame1992

Author index to volumes 16, 17 and 18

1991

Quantification and disposal of radioactive waste from ITER operation

G. Olsson, L. Devell, B. Johnsson, W. Gulden1991

Afterheat in fusion structural materials and thermal transient scenarios in ITER

F. Andritsos, M. Zucchetti1991

Evaluation of SS316 first wall material for activation and afterheat for maintenance purposes

I. Schreinlechner, I. Šmid, G. Weimann1991

Risk evaluation of critical in-vessel accident sequences for a next step tokamak machine

G. Cambi, G. Cavallone, T. Palma, S. Sarto1991

A comparison of radioactive waste from an experimental fast fission reactor and an experimental D-T fusion reactor

M. Koch, M.S. Kazimi1991

Basis criteria and current procedures for routine management of tritiated wastes at the JRC-Ispra

F. Mannone1991

Comparison of predicted doses due to a continuous HTO release

H.-W. Bartels1991

Some considerations on tritium control for the European ceramic BIT DEMO blanket

X. Raepsaet, E. Proust, V. Violante1991

Verification of dose rate calculation and selection study on low activation concrete in fusion facilities

Koji Oishi, Yujiro Ikeda, Kazuaki Kosako, Kiyoshi Minami, Tomoo Nakamura1991

Radioactivity effects of Pb17Li in fusion power reactors

G. Casini, P. Rocco, M. Zucchetti1991

Lithium-lead/water interaction. Large break experiments

C. Savatteri, A. Gemelli1991

Radiation protection concepts of Large Helical Device (LHD) facility

Hiroyuki Handa, Katsumi Hayashi, Yuichi Ogawa, Yoichi Sakuma, Osamu Sato1991

Temperature transients in reference tokamak reactors following loss of coolant

W.E. Han, I. Cook1991

Analysis of loss-of-coolant and loss-of-flow accidents in the divertor cooling system of NET/ITER

H.Th. Klippel, E.M.J. Komen1991

Benefits of natural convection in solid breeder blankets with poloidal coolant channels under LOFA conditions

Alice Y. Ying, A.Rene Raffray, Mohamed A. Abdou1991

LOCA, LOFA and LOVA analyses pertaining to NET/ITER safety design guidance

Edgar Ebert, Jürgen Raeder1991

A risk perspective on fusion safety phenomena

I. Cook, C.G. Gimblett1991

Trends in fusion reactor safety research

J. Stephen Herring, Douglas F. Holland, Steven J. Piet1991

Outlines of a development proposal for the NET shielding blanket assembly

B. Bielak, D. Besson, F. Carre, W. Daenner, P. Thomas1991

Pebble bed, helium cooled, molten salts breeder blanket concept for a tokamak reactor

P.G. Avanzini, N. Cerullo, G. Guglielmini, S. Simonetti, F. Zacchia1991

Dynamic tritium inventory of a NET/ITER fuel cycle with lithium salt solution blanket

Gert Spannagel, Paul Gierszewski1991

Water radiolysis under NET conditions

P. Lorenzetto, E. Bjergbakke, B. Hickel1991
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