FusionPapers
図版検索AI要約wiki日本の研究装置ジャーナルChatGPTAbout
© 2026 FUSIONPAPERS
About法務情報
ジャーナル一覧に戻る
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
AI解説分析論文一覧
全 15,142 件の論文
並び順:新しい順古い順被引用数順

Thermohydraulic experiments on a water jet into vacuum during ingress of coolant event in a fusion experimental reactor

M. Ogawa, T. Kunugi1995

Tritium permeation through helium-heated steam generators of ceramic breeder blankets for DEMO

Michael A. Fütterer, Xavier Raepsaet, Eric Proust1995

Comparative radiological assessment of SiCf/SiC composites as structural materials in nuclear fusion technology

H.W. Scholz, M. Zucchetti1995

Assessment of radiological hazards of tungsten divertors

S.K. Ho, M.D. Lowenthal1995

Source terms due to the activated corrosion products in primary cooling loops of ITER

G. Cambi, D.G. Cepraga, S. Ciattaglia, L. Di Pace, G. Cavallone1995

Radioactive waste produced by demonstration and commercial fusion reactors extrapolated from ITER and advanced databases

Weston M. Stacey, Nolan E. Hertel, Edward A. Hoffman
1995

SEAFP: passive removal of the decay heat

F. Andritsos, A. Angelini, H.W. Bartels, W. Daenner, M. Zucchetti1995

Fusion reactor design parameters relevant to the passive removal of decay heat

F. Andritsos1995

Calculation and classification of the radioactive waste inventory in the structural components of a compact ignition fusion machine

D.G. Cepraga, G. Cambi, S.A.M.M. Siddiqui1995

Waste management strategies for fusion materials

H. Dworschak, P. Rocco, M. Zucchetti1995

Shield water system design options to improve the safety of fusion reactor blankets

K.M. Crosswait, J.E. Meyer1995

Experimental study of 210Po release from 17Li83Pb eutectic

O. Schipakin, N. Borisov, S. Churkin1995

Design standard issues for ITER in-vessel components

Saurin Majumdar1995

The effect of composition on volatility from a copper alloy

K.A. McCarthy, G.R. Smolik, R.S. Wallace, K. Messick1995

Consequence modelling of postulated upper-bound accidents in a fusion power plant

N.P. Taylor, C.B.A. Forty, W.E. Han, J.-Ch. Sublet, I. Cook1995

Report on the European Safety and Environmental Assessment of Fusion Power (SEAFP)

J. Raeder1995

Conceptual design of helium recycling control system in a divertor of a tokamak reactor

Mieko Kashiwagi, Shunji Ido1995

Impact of improvements in HYLIFE-II on safety, performance and cost

M.A. Hoffman, Y.T. Lee1995

Liquid-metal-cooled divertor for ARIES

E. Muraviev1995

Thermomechanical design of the grazing incidence metal mirror of the Prometheus-L IFE reactor

N.M. Ghoniem, A. El-Azab1995

A preliminary study of a D—T tokamak fusion reactor with advanced blanket using the compact fusion advanced Brayton (CFAB) cycle

K. Yoshikawa, M. Ohnishi, Y. Yamamoto, H. Toku, M. Nagatsu1995

Conceptual design of a poloidal field coil system and operation scenario for an inductively operated day-long pulsed tokamak reactor

J.F. Wang, T. Yamamoto, T. Amano, Y. Ogawa, N. Inoue1995

Transmutation of the actinide neptunium-237 with a hybrid reactor

K.M. Feng, J.H. Huang1995

Preliminary analysis of MHD—Brayton cycle applied to fusion reactors (CFAR)

Motoo Ishikawa, Yoshitaka Inui, Juro Umoto, Kiyoshi Yoshikawa1995

Blanket and divertor design for force free helical reactor (FFHR)

A. Sagara, O. Motojima, K. Watanabe, S. Imagawa, H. Tikaraishi1995

Using the shield for thermal energy storage in pulsar

G.T. Sager, D.-K. Sze, C.P.C. Wong, C.G. Bathke, L. Waganer1995

The logic behind thick, liquid-walled, fusion concepts

Ralph W. Moir1995

Energetic and economic balance for an inertial fusion power plant

Nicola Cerullo, Salvatore Lanza, Marco Vezzani1995

Overview of the Russian Demo plant study

Yu.A. Sokolov1995

Contributions of the National Ignition Facility to the development of inertial fusion energy

M. Tobin, G. Logan, T. Diaz De La Rubia, V. Schrock, R. Bangerter1995
前へ1...474475476477478479480...505次へ