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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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1.7

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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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Initial tritium waste management criteria and assessment for ITER

I.A. Ionesyan, V.K. Kapychev, V.N. Tebus, V.N. Frolov1998

Deposition of heavy water on soil and reemission to the atmosphere

Sumi Yokoyama, Hiroshi Noguchi, Michiko Ichimasa, Yusuke Ichimasa, Satoshi Fukutani1998

Deposition of D2O from air to plant and soil during an experiment of D2O vapor release into a vinyl house

Mariko Atarashi, Hikaru Amano, Michiko Ichimasa, Yusuke Ichimasa1998

Extended monodisperse aerosol modelling for fusion power plant containments

Study of safety concept for a helical-type fusion reactor, FFHR

FFHR Group, T. Uda, A. Sagara, O. Motojima, T. Noda1998

Applications of the CATHARE and CONTAIN codes in parallel runs

P. Sardain, M. Porporat, J.M. Gatt, G. Marbach

1998

Safety approach for plasma anomaly events in fusion reactor: Code development and assessments

T. Honda, H.-W. Bartels, N.A. Uckan, Y. Seki, T. Okazaki1998

ITER divertor heat transfer system and loss of vacuum accident sequence analyses overview

G. Cambi, M.T. Porfiri, H. Jahn, D.G. Cepraga, H.-W. Bartels1998

Response of ITER to loss of vacuum accidents

J.M. Gay, G. Marbach, W. Gulden1998

Temperature distributions in a Tokamak vacuum vessel of fusion reactor after the loss-of-vacuum events occurred

Kazuyuki Takase, Tomoaki Kunugi, Mitsuhiko Shibata, Yasushi Seki1998

An experimental study of ingress-of-coolant accident in fusion reactors

Mohammad Z. Hasan, Masanori Monde, Yuichi Mitsutake, Kazuya Iwamoto1998

Thermofluid experiments on ingress of coolant event

Tomoaki Kunugi, Kazuyuki Takase, Mitsuhiko Shibata, Ryouichi Kurihara, Yasushi Seki1998

Analysis and experimental results on ingress of coolant event in vacuum vessel

Ryoichi Kurihara, Toshio Ajima, Tomoaki Kunugi, Kazuyuki Takase, Fumio Kasahara1998

Design and safety aspects of the cryostat confinement barrier

M.E.P. Wykes, R. Bourque, Y. Nakashima, M. Nakahira, S.J. Piet1998

The safety implications of tokamak dust size and surface area

K.A. McCarthy, D.A. Petti, W.J. Carmack, G.R. Smolik1998

Safety scenario and integrated thermofluid test

Yasushi Seki, Ryoichi Kurihara, Satoshi Nishio, Shuzo Ueda, Mitsuhiko Shibata1998

In-vessel transient analysis code INTRA for ITER accident analyses

H. Jahn, R. Blomquist, W. Gulden, L.-L. Johansson, E. Kajlert1998

ITER inherent/passive ultimate safety margins

Steven J. Piet, Leonid N. Topilski, Hans-Werner Bartels, Andre E. Poucet, David A. Petti1998

ITER reference accidents

H.-W. Bartels, A. Poucet, G. Cambi, C. Gordon, W. VanHove1998

Fusion reactor safety—Issues and perspective

Teruo Inabe, Masahiro Seki, Toshihide Tsunematsu1998

Waste from fusion reactor: A comparison with other energy producing systems

K. Brodén, R. Edwards, M. Lindberg, P. Rocco, M. Zucchetti1998

Detailed conceptual design of the fusion experimental breeder

J.H Huang, L.J Qiu, Joint Design Team of SWIP and ASIPP1998

Neutronics study and analysis of a multifunctional blanket

Bingjia Xiao, Lijian Qiu1998

Design studies on nuclear properties on the Flibe blanket for helical-type fusion reactor FFHR

H Yamanishi, A Sagara, O Motojima, T Noda, FFHR Group1998

Neutronic and photonic analysis of the single box water-cooled lithium lead blanket for a DEMO reactor

G Vella, L Giancarli, E Oliveri, G Aiello1998

Proposal for an alternative type of helium-cooled blanket for DEMO

F Zacchia, N Cerullo, C Fossa1998

Combination of a self-cooled liquid metal breeder blanket with a gas turbine power conversion system

S. Malang, H. Schnauder, M.S. Tillack1998

A fusion study of thermoelectric conversion in magnetic fields

S. Yamaguchi, K. Ikeda, H. Nakamura, K. Kuroda, O. Motojima1998

Design window for shield thermal energy storage for pulsed tokamak fusion reactors

Mohammad Z. Hasan, Masanori Monde, Yuichi Mitsutake, M.A. Islam1998

Basic numerical simulation of TWDEC for a D–3He fusion reactor

M. Ishikawa, T. Kudo, S. Hayashi, T. Yamane, H. Momota1998

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