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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

公式サイト

Impact Factor

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

Hydrogen extraction from Pb–17Li: results with a 800 mm high packed column

N Alpy, A Terlain, V Lorentz2000

Tritium recovery from an ITER ceramic test blanket module — process options and critical R&D issues

H. Albrecht, E. Hutter2000

Status and research progress at the Tritium Laboratory Karlsruhe

R.-D Penzhorn, N Bekris, P Coad, L Dörr, A Peacock2000

Tritium inventory in the first wall of JET

A.T Peacock, P.A Andrew, D Brennan, J.P Coad, M Pick2000

Tritium technology for blankets of fusion power plants

Michael A Fütterer, Helmut Albrecht, Pierre Giroux, Manfred Glugla, Dai-Kai Sze2000

Neutronics performance of high-temperature refractory alloy helium-cooled blankets for fusion application

M.Z Youssef, C Wong2000

Heat deposition, damage, and tritium breeding characteristics in thick liquid wall blanket concepts

M.Z Youssef, M.A Abdou2000

Helium-cooled refractory alloys first wall and blanket evaluation

C.P.C Wong, R.E Nygren, C.B Baxi, P Fogarty, S Zinkle2000

Neutronic, thermal–hydraulic and stress analysis of RF lithium cooled test blanket module for ITER

I.V Vitkovsky, M.M Golovanov, V.A Divavin, I.R Kirillov, O.L Schipakin2000

Tritium inventory and permeation in the ITER breeding blanket

V. Violante, S. Tosti, C. Sibilia, F. Felli, C. Alvani2000

ARIES-ST breeding blanket design and analysis

ARIES Team, M.S. Tillack, X.R. Wang, J. Pulsifer, D.K. Sze2000

Application of high temperature mass spectrometry and work function measurement to evaluation of thermochemical performance of ceramic breeders

Atsushi Suzuki, Kenji Yamaguchi, Takayuki Terai, Michio Yamawaki2000

Hydrogen and deuterium permeation measurements on the double-wall tubes material for the water-cooled Pb–17Li DEMO blanket

E Serra, E Rigal, G Benamati2000

Nuclear analysis for a flowing Li2O particulate blanket without structural first wall

M.E Sawan, H.Y Khater, D.-K Sze2000

Design and development of the Flibe blanket for helical-type fusion reactor FFHR

A. Sagara, H. Yamanishi, S. Imagawa, T. Muroga, O. Motojima2000

Effect of ITER blanket manufacturing process on the properties of the 316L(N)-IG steel

B.S Rodchenkov, Y.S Strebkov, G.M Kalinin, O.A Golosov2000

Development of FM steels diffusion bonding technologies for blanket manufacturing applications

E Rigal, G Le Marois, T Lechler, G Reimann, P Weimar2000

Thermomechanical behaviour of ceramic breeder and beryllium pebble beds

J. Reimann, E. Arbogast, M. Behnke, S. Müller, K. Thomauske2000

Neutronic shielding analysis of the water-cooled lithium lead test blanket module in the ITER machine

M Rapisarda2000

The fracture mechanics behaviour of the WCLL blanket segment

Claudio Nardi, A Palmieri2000

Enhancement of tritium release from ceramic breeders with impregnated catalytic additives

Kenzo Munakata, Atsushi Baba, Takahiro Kawagoe, Toshiharu Takeishi, Kenji Okuno2000

EVOLVE—an advanced first wall/blanket system

R.F. Mattas, S. Malang, H. Khater, S. Majumdar, D.K. Sze2000

Numerical and experimental prediction of the thermomechanical performance of pebble beds for solid breeder blanket

Zi Lu, Alice Y Ying, Mohamed A Abdou2000

Evaluation of mock-ups before manufacture of a shield block prototype by powder HIP

Anders Lind, Carl Gustaf Hjorth, Ulrika Håkansson, Patrick Lorenzetto2000

Ceramic helium-cooled blanket test module

A Leshukov, V Kovalenko, G Shatalov, G Goroshkin, A Obukhov2000

Manufacturing of a semi-scale blanket box mock-up of the European HCPB blanket

T Lechler, H.-J Fiek, S Gordeev, K Schleisiek2000

HIP technologies for fusion reactor blankets fabrication

G Le Marois, L Federzoni, P Bucci, P Revirand2000

Novel liquid blanket configurations and their hydrodynamic analyses for innovative confinement concepts

K. Gulec, M.A. Abdou, R.W. Moir, N.B. Morley, A. Ying2000

Performance of the TAURO blanket system associated with a liquid-metal cooled divertor

H Golfier, G Aiello, M.A Fütterer, A Gasse, J Szczepanski2000

High power density self-cooled lithium–vanadium blanket

Y Gohar, S Majumdar, D Smith2000
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