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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

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

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全 15,142 件の論文

並び順:新しい順古い順被引用数順

Potential and limits of water-cooled Pb–17Li blankets and divertors for a fusion power plant

M.A Fütterer, L Barleon, L Giancarli, A.Li Puma, G Vella2000

Improved modules for the blanket of RTO/RC ITER

F Elio, K Ioki, A Cardella2000

Long-term activation potential of the steel eurofer as structural material of a demo breeder blanket

Eric Daum, Ulrich Fischer2000

Experimental investigations on the thermal and mechanical behaviour of a binary beryllium pebble bed

M. Dalle Donne, A. Goraieb, G. Piazza, F. Scaffidi-Argentina2000

Measurements of the effective thermal conductivity of a Li4SiO4 pebble bed

M. Dalle Donne, A. Goraieb, G. Piazza, G. Sordon2000

Conceptual study on high performance blanket in a spherical tokamak fusion-driven transmuter

Yixue Chen, Yican Wu

2000

Mechanical behavior of Li4SiO4 in a blanket typical geometry

L Bühler, J Reimann, E Arbogast, K Thomauske2000

Advanced helium cooled pebble bed blanket with SiCf/SiC as structural material

L.V. Boccaccini, U. Fischer, S. Gordeev, S. Malang2000

Isotope exchange reaction on solid breeder materials

A Baba, M Nishikawa, T Eguchi, T Kawagoe2000

The blanket technology investigation in China

FW/Blanket and vacuum vessel for RTO/RC ITER

K Ioki, V Barabash, A Cardella, F Elio, M Yamada2000

Lithium cooled blanket of RF DEMO reactor

I.R. Kirillov, RF DEMO team2000

Candidate blanket concepts for a European fusion power plant study

L Giancarli, M Ferrari, M.A Fütterer, S Malang2000

The international fusion materials irradiation facility IFMIF — an overview of user aspects

E Daum, K Ehrlich, S Jitsukawa, H Matsui, A Möslang2000

Major achievements of the European shield blanket R&D during the ITER EDA, and their relevance for future next step machines

W Dänner, A Cardella, L Jones, P Lorenzetto, F Tavassoli2000

Thermal and mechanical behaviour of diagnostic windows subjected to intense heat fluxes

P Zaccaria, S Dal Bello2000

Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module

Dennis L Youchison, Mark T North, James E Lindemuth, Jimmie M McDonald, Thomas J Lutz2000

Free surface heat transfer and innovative designs for thin and thick liquid walls

A.Y. Ying, N. Morley, S. Smolentsev, K. Gulec, P. Fogarty2000

Plasma shield dynamics and target erosion in disruption simulation experiments

H Würz, S Pestchanyi, F Kappler2000

Neutron effects on properties and annealing of low-Z materials

C.H. Wu, J.P. Bonal, H. Werle2000

Thermal fatigue equipment to test joints of materials for high heat flux components

E. Visca, S. Libera, A. Orsini, B. Riccardi, M. Sacchetti2000

High heat flux test of actively cooled tungsten-coated carbon divertor mock-ups

K Tokunaga, N Yoshida, Y Kubota, N Noda, L Plöchl2000

ARIES-ST plasma-facing component design and analysis

M.S Tillack, X.R Wang, J Pulsifer, I Sviatoslavsky, the ARIES Team2000

Material mixing on W/C twin limiter in TEXTOR-94

T Tanabe, T Ohgo, M Wada, M Rubel, B Schweer2000

Forced convective heat transfer in square-ribbed coolant channels with helium gas for fusion power reactors

Thermal fatigue damage of the divertor plate

Satoshi Suzuki, Koichiro Ezato, Kazuyoshi Sato, Kazuyuki Nakamura, Masato Akiba2000

Power deposition and margins on the Tore Supra pump limiter and fabrication of the high heat flux components

J Schlosser, R Mitteau, L Plöchl, C Depit, E Tsitrone2000

Thermomechanical behaviour of actively cooled divertor elements with internal coolant flow return

M. Scheerer, H. Bolt, J. Linke, R. Lison, R. Uhlemann2000

Molybdenum limiters for Extrap-T2 upgrade: surface properties and high heat flux testing

M Rubel, P Brunsell, R Duwe, J Linke2000

Fabrication of monoblock high heat flux components for ITER divertor upper vertical target using hot isostatic pressing diffusion welding

E Rigal, P Bucci, G Le Marois2000

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