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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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Structural evaluation of the NET/ITER outboard blanket box

R.R. Jakeman, S. Chiocchio, M. Lazzaretti, M. Reale1991

Neutronic and thermomechanical analysis of the water-cooled lithium-lead blanket design for a DEMONET reactor

P. Leroy, L. Baraer, L. Giancarli, Ph. Labbé, J. Quintric-Bossy1991

Influence of irradiation on structure and properties of lithium-lead eutectic — Possible material for ITER reactor blanket

V.N. Tebus, Yu.N. Sokursky, S.V. Lukashin, L.D. Panteleev, A.A. Bochvar1991

Mass transfer coefficient of tritium from molten lithium-lead alloy (Li17Pb83) to environmental gas under neutron irradiation

Takayuki Terai, Shin'ichi Nagai, Toshiaki Yoneaka, Yoichi Takahashi1991

Experimental calibration of electromagnetic flowmeters for Pb17Li

C. Arrighi, F. Monteleone1991

An estimation of MHD effects in the European water-cooled lithium-lead blanket

R. Moreau, P. Leroy1991

A liquid metal experimental loop for MHD pressure drop and compatibility studies

J.P. Qian, K.Z. Sun, W.H. Jiang, X.L. Xu, J.N. Liu1991

Liquid metal flow in arbitrary thin-walled channels under a strong transverse variable magnetic field

Comparison of the core flow approximation and full solution approach for MHD flow in non-symmetric and multiple adjacent ducts

K.A. McCarthy, A.Y. Ying, N.B. Morley, M.A. Abdou1991

Evaporation of lead and lithium from molten Pb17Li — Transport of aerosols

H Feuerstein, H Gräbner, J Oschinski, S Horn, S Bender1991

Design and operation of NEXTEL-1: an experimental loop for continuous corrosion monitoring of structural materials for NET

I.A.L. Vancoillie, W.F. Bogaerts, K. Agema, J.H. Zheng, P. Lorenzetto1991

Corrosive effects of Pb17Li/water interaction

P. Agostini, G. Benamati1991

Corrosion studies on type AISI 316L stainless steel and other materials in lithium-salt solutions

J.H. Zheng, W.F. Bogaerts, K. Agema, K. Phlippo, P. Lorenzetto1991

Material compatibility tests with flowing Pb17Li eutectic

H.U. Borgstedt, G. Frees, Z. Peric1991

Trends in liquid metal breeder blanket development

Haruki Madarame1991

Experimental studies of active temperature control in solid breeder blankets

M.S. Tillack, A.R. Raffray, A.Y. Ying, M.A. Abdou, P.E. Huemer1991

Experimental thermo-mechanical testing apparatus for a DEMO relevant blanket design of a ceramic cladded pin

G. Dell'Orco, G.C. Bertacci1991

Electromagnetic forces caused by disruptions in the Karlsruhe demo solid breeder blanket and in the test module for NET/ITER

L.V. Boccaccini1991

Three-dimensional neutronic analysis of the European ceramic BIT DEMO blanket

L. Giancarli, L. Petrizzi, C. Diop, V. Rado1991

Thermal hydraulic analysis of the basic breeder module of the European ceramic BIT DEMO blanket

S. Cevolani, E. Proust, F. Vallette1991

Thermal control of solide breeder blankets

A.R. Raffray, A. Ying, Z. Gorbis, M.S. Tillack, M.A. Abdou1991

The evolution of US helium-cooled blankets

C.P.C. Wong, E.T. Cheng, K.R. Schultz1991

First adaptation of the European ceramic B.I.T. blanket design to the updated DEMO specifications

L. Anzidei, P. Cecchi, S. Cevolani, M. Gallina, J. Mercier1991

Design of an experiment to model the thermal-hydraulics of a poloidal pin bundle for a helium cooled BIT blanket

S. Cevolani, G. Dell'Orco1991

Problems and solutions for design and construction of a pin-type ceramic blanket module

F. Zacchia, M. Grattarola, F. Rosatelli, G. Simbolotti1991

Ceramic sphere-pac breeder design for fusion blankets

P.J. Gierszewski, J.D. Sullivan1991

The Karlsruhe solid breeder blanket and the test module to be irradiated in ITER/NET

M.Dalle Donne, E. Bojarsky, U. Fischer, M. Küchle, E. Bogusch1991

Canadian ceramic breeder sphere-pac technology: capability and recent results

J.D. Sullivan, C.L. Brayman, R.A. Verrall, J.M. Miller, A. Slavin1991

Analysis of tritium release from LiAlO2 in the TEQUILA experiment, using the MISTRAL code

A. Badawi, A.R. Raffray, M.A. Abdou1991

Inpile tritium release from ceramic breeder materials in TRIDEX experiments 1–6

W. Krug, H.G. Bays, H. Jünemann, W. Krauthausen, H. Werle1991

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