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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

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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Accelerators and beam dynamics

W.B. Herrmannsfeldt, Edward P. Lee1996

Session summary and comments for overviews and systems

Grant Logan1996

HIF95 participants list

HIF95 committee members

Exploration and assesment of design windows for a Tokamak-based volumetric neutron source

S.K. Ho, M.A. Abdou1996

Effects of an electrically conducting first wall on the blanket loading during a Tokamak plasma disruption

T. Jordan, D. Schneider1996

Three-dimensional analysis of antenna sheaths

J.R. Myra, D.A. D'Ippolito, Y.L. Ho1996

Design of tungsten/copper graded composite for high heat flux components

Yoshiyasu Itoh, Masashi Takahashi, Hirohisa Takano1996

Short term dynamics of the reaction between beryllium and steam on the PFCs coating of ITER

D.A. Sarigiannis, F. Andritsos1996

Analysis for loss of coolant accident in a fusion reactor

T. Hino, Y. Hirohata, T. Yamashina1996

Study on thermal fatigue testing of a prototypical first wall component

M. Merola, R. Matera, G. Vieider1996

Measurements and calculations of neutron leakage spectra through copper slabs bombarded with 14 MeV neutrons

J. Jordanova, O. Penchev1996

Analogue feedback control system of RFX

P. Fiorentin, E. Gaio, G. Marchiori, V. Toigo1996

Decay heat removal in the ITER outline design

H.-W. Bartels, E. Cheng, M. Gaeta, B. Merrill, D. Petti1996

An experimental and numerical investigation of post-CHF heat transfer for one-sided heat load with highly sub-cooled flow boiling

V. Divavin, V. Tanchuk, A. Shrubok, R. Watson, J. González1996

Tritium retention in graphite inner wall of JT-60U

K. Masaki, K. Kodama, T. Ando, M. Saidoh, K. Okuno1996

Transient electromagnetic analysis in tokamaks using typhoon code

A.V. Belov, N.I. Doinikov, A.E. Duke, V.V. Kokotkov, S.E. Sytchevsky1996

Present activities for the preparation of a Japanese draft of structural design guidelines for the experimental fusion reactor

K. Miya, Y. Muto, H. Takatsu, K. Hada, S. Kinoshita1996

Compatibility aspects of the Pb-17Li martensitic steel-H2O system

A study of time-dependent, low energy (2 × 10-4 eV<E<0.2eV) neutron spectra and tritium breeding in 3He + C blanket of a fusion reactor

Sanjay Gupta, Feroz Ahmed, Suresh Garg1996

Convective heat transfer enhancement when using gas-solid particle two phase coolant for the Tokamak type reactor first wall cooling

A.M. Epinatiev, V.V. Perevezentsev, A.V. Razmerov1996

Low pressure tritium interaction with Inconel 625 and AISI 316 L stainless steel surfaces: an evaluation of the recombination and adsorption constants

A. Perujo, K. Douglas, E. Serra1996

Development of cryosorption pump for neutral beam injector

Y. Oka, T. Takanashi, R. Akiyama, O. Kaneko, T. Kuroda1996

Summary of Japan-US workshop on high heat flux components and plasma surface interactions for next fusion devices

T. Hino, M. Akiba1996

Some aspects of volumetric neutron source based on tokamak with ‘warm’ magnet system and inner radiation shield

O.G. Filatov, V.V. Filatov, Ye.G. Kuzmin, A.N. Makhankov, V.E. Zhogolev1996

Ignitor neutronics and activation

P. Batistoni, P. Corsaro, S. Rollet, M. Zucchetti1996

An investigation into the possibility of performing radiography with gamma rays emitted from water made radioactive by irradiation with 14 MeV D-T fusion neutrons

Donald L. Smith, Yujiro Ikeda, Yoshitomo Uno1996

Maintenance of a commercial fusion power station and its implications for safety

D.V. Sherwood, J. Pearcey, H.M. Thompson, J.-Ch. Sublet, N.P. Taylor1996

Geometry free of singularities for fusion duplex components

R. Viola, E.B. Deksnis1996

Weldability of neutron-irradiated type 316 stainless steel

K. Watanabe, S. Jitsukawa, S. Hamada, T. Kodaira, A. Hishinuma1996

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