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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

Planar coil design for the Helios stellarator fusion power plant
Equilibrium optimization of the Helios planar coil stellarator power plant
Core profile prediction and transport analysis of the Helios stellarator fusion power plant
Superconducting planar coils for magnetic field shaping in the Helios Stellarator
Design of the superconducting encircling coils for Helios, the planar coil stellarator

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並び順:新しい順古い順被引用数順

Design of a membrane atmosphere detritiation system using super high permeation module

T. Ishida, T. Hayashi, S. Mori, T. Suzuki, M. Nishi2000

Kinetics and mechanism of hydrogen-induced disproportionation of ZrCo

Masanori Hara, Toshio Okabe, Katsunori Mori, Kuniaki Watanabe2000

Counterflow hydrogen isotope separation facility — data on tritium activities

A.N. Golubkov, A.I. Vedeneev, B.N. Tenyaev, B.M. Andreev, I.N. Selivanenko2000

A Permcat reactor for impurity processing in the JET Active Gas Handling System

M. Glugla, A. Perevezentsev, D. Niyongabo, R.-D. Penzhorn, P. Herrmann2000

Experience gained during the modification of the Caprice system to Caper

M Glugla, R Lässer, T.L Le, R.-D Penzhorn, K.H Simon2000

Zr2Fe and Zr(Mn0.5Fe0.5)2 particle beds for tritium purification and impurity removal in a fusion fuel cycle

Satoshi Fukada, Yoshiki Toyoshima, Masabumi Nishikawa

2000

Model about the separation of molecular species of hydrogen isotopes by cryogenic distillation using the elementary theory of transport phenomena

I. Cristescu, Ioana Cristescu, V. Poenariu, Irina Preda, L. Stefan2000

H2O trapping on various materials studied by AFM and XPS

Kunihiko Chiba, Rumi Ohmori, Hisashi Tanigawa, Toshiaki Yoneoka, Satoru Tanaka2000

On the thermal stability of the zirconium/cobalt–hydrogen system

N Bekris, U Besserer, M Sirch, R.-D Penzhorn2000

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

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