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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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Criteria for defining low activation materials in fusion reactor applications

P Rocco, M Zucchetti1991

Tritium transport in the water cooled Pb17Li blanket concept of DEMO

F Reiter, S Tominetti, A Perujo1991

Electromagnetic effects induced by plasma disruptions in the NET vacuum vessel

R Albanese, L Bottura, E Coccorese, R Martone, G Rubinacci1991

When the age of fusion?

Stephen O Dean1991

Note from the editors

Robert W Conn1991

Finite element analysis with an axisymmetric model of the tritium diffusion in a ceramic blanket solution of a commercial tokamak

S. Abou Said, M. Caira, C. Caroli, V. Violante1991

Dynamics and energy flow in a disrupting tokamak plasma

B.J. Merrill, S.C. Jardin, M. Ulrickson, M. Bell1991

On modelling of marangoni convection flows in simulated plasma disruptions

G. Tsotridis, H. Rother, E.D. Hondros1991

Small scale lithium-lead/water-interaction studies

O. Kranert, H. Kottowski1991

Engineering aspects of a steady state tokamak reactor (SSTR)

S. Nishio, T. Ando, Y. Ohara, S. Mori, Y. Seki1991

Afterheat transient in ITER after a total loss of coolant accident

F. Andritsos, M. Zucchetti1991

Thermal reradiation in the NET/ITER plasma chamber

Superconductors for the NET coils

N. Mitchell, L. Bottura1991

Surface ripple of resolidified stainless steel after disruption load

Haruki Madarame, Toshio Sukegawa, Tadao Ogawa, Toshihiko Koseki1991

Thermal shock tests on various materials of plasma facing components for FER/ITER

M. Seki, M. Akiba, M. Araki, K. Yokoyama, H. Ise1991

Thermal shock problems of bonded structure for plasma facing components

M. Shibui, T. Kuroda, Y. Kubota1991

Heat load on the divertor plate of JT-60 during normal and abnormal operations

T. Ando, H. Takatsu, H. Nakamura, K. Itami, M. Yamamoto1991

Development of high conductive C/C composite tiles for plasma facing armor

K. Ioki, K. Namiki, S. Tsujimura, M. Toyoda, H. Takatsu1991

High heat flux test on first wall materials

Seiichiro Yamazaki, Takeshi Kobayashi, Sinji Koga, Masahiro Seki, Hideyuki Takatsu1991

Progress of R & D activities on plasma facing low Z materials and components for NET

H. Bolt, M. Budd, A. Cardella, B. Shaw, E. Zolti1991

Plasma—wall interaction and its effect on material selection

Takaichi Kawamura1991

Author index to volume 14

Studies with respect to the estimation of liquid metal blanket safety

H. Kottowski, O. Kranert, C. Savatteri, C. Wu, M. Corradini1991

Fusion reactor blanket with Li17Pb83 eutectic

A. Antipenkov, A. Butko, A. Chepovski, I. Danilov, Yu. Strebkov1991

Tritium inventory and recovery for a self-cooled PbLi blanket

MHD flow in liquid-metal-cooled blankets

L. Barleon, V. Casal, L. Lenhart1991

Self-cooled blanket concepts using Pb7Li as liquid breeder and coolant

S. Malang, H. Deckers, U. Fischer, H. John, K. Rust1991

A water cooled, lithium lead breeding blanket for a DEMO fusion reactor

G. Casini, Ph. Labbe, M. Rieger, L. Baraer, M. Zucchetti1991

Compatibility of eutectic with structural materials

A. Antipenkov, V. Belous, I. Danilov, G. Kalinin, V. Zemlyankin1991

Deposition behavior of ferrous alloys in molten lead-lithium

P.F Tortorelli1991

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