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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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Experimental durability studies of electrolysis cell materials for a water detritiation system

Yasunori Iwai, Akihiro Hiroki, Toshiaki Yagi, Masao Tamada, Toshihiko Yamanishi2008

Engineering design and R&D of Impurity Influx Monitor (divertor) for ITER

Hiroaki Ogawa, Tatsuo Sugie, Satoshi Kasai, Atsushi Katsunuma, Yoshinori Kusama2008

Study on the technology of CECE–GC system for water detritiation

Sun Ying, Wang Heyi, Sang Ge, Luo Yangming, Xiong Yifu2008

Bend points of hydrogen partial pressure curves obtained by tritium removal simulation tests

Improved characteristics of hydrophobic polytetrafluoroethylene–platinum catalysts for tritium recovery from tritiated water

I. Popescu, Gh. Ionita, I. Stefanescu, C. Varlam, I. Faurescu2008

Tritium sorption and desorption from JET beryllium tiles under temperature, electron radiation and magnetic field

Juris Tīliks, Gunta Ķizāne, Aigars Vītiņš, Elīna Kolodinska, Broņislavs Leščinskis2008

Hydrogen isotope separation capability of low temperature mordenite column for gas chromatograph

Yoshinori Kawamura, Yoshihiro Onishi, Kenji Okuno, Toshihiko Yamanishi2008

The development of standard operating procedures for the SDS of the ITER tritium plant

Kyu-Min Song, Soon Hwan Sohn, Yang Geun Chung, Seungyon Cho, Hiroshi Yoshida2008

Experimental study of detritiation system catalyst poisoning

Fabio Borgognoni, Claudio Rizzello, Silvano Tosti2008

Advanced fuelling system for ITER

Roger Raman2008

Detritiation studies for JET decommissioning

A.N. Perevezentsev, A.C. Bell, J. Williams, P.D. Brennan2008

Recent results of R&D activities on tritium technologies for ITER and fusion reactors at TPL of JAEA

T. Yamanishi, T. Hayashi, W. Shu, Y. Kawamura, M. Yamada2008

Evolution of ITER Tritium Confinement strategy and adaptation to Cadarache site conditions and French regulatory requirements

D. Murdoch, M. Glugla, T. Hayashi, A. Perevesentsev, C. Taylor2008

MoS2 coatings for the narrow support elements of the W-7X nonplanar coils

F. Koch, R. Nocentini, B. Heinemann, S. Lindig, H. Bolt2007

Multi-solid multi-channel Mithrandir (M3) code for thermal–hydraulic modelling of ITER Cable-in-Conduit Superconductors

L. Savoldi Richard, M. Bagnasco, R. Zanino2007

Conceptual design of the enhanced radial field amplifier for plasma vertical stabilisation in JET

V. Toigo, L. Zanotto, M. Bigi, E. Gaio, S.R. Shaw2007

Structural evaluation of the busbar system of Wendelstein 7-X stellarator

B. Giesen, A. Panin, T. Boguszewski, S. Brons, J. Wolters2007

Tolerance evaluation of poloidal shear keys for ITER TF coil

Youkun Fu, Jong Cees, Mitchell Neil2007

Manufacturing of the coil support structure for W7-X

A. Benito, D. Goitia, E. Casado, M. Anderez, G. Di Bartolo2007

FEM analysis of coil support connections in the Wendelstein 7-X magnet system

Grzegorz Krzesiński, Tomasz Zagrajek, Piotr Marek, Romuald Dobosz, Krzysztof J. Kurzydłowski2007

Manufacture of the poloidal field conductor insert coil (PFCI)

W. Baker, C. Keefe, H. Rajainmäki, E. Salpietro2007

Industrial engineering studies for the manufacture of the ITER PF coils

P. Libeyre, P. Decool, O. Guérin, M. Perrella, A. Bourquard2007

Change in properties of superconducting magnet materials by fusion neutron irradiation

Arata Nishimura, Shigehiro Nishijima, Takao Takeuchi, Takeo Nishitani2007

Simulation of voltage and current development in the Wendelstein 7-X coil system taking into account fault conditions

M. Köppen, J. Kißlinger2007

Structural analysis of W7-X: Main results and critical issues

V. Bykov, F. Schauer, K. Egorov, P. van Eeten, D. Zacharias2007

Quality assurance of aluminium weld seams and cast casings of the W7-X coils

M. Schröder, J. Holluba, K. Heyn2007

Test results from the full size prototype test of W7-X joint

K. Rummel, M. Czerwinski, F. Hurd, A. John, M. Vogel2007

Design of the superconducting coil system in JT-60SA

K. Tsuchiya, K. Kizu, T. Ando, H. Tamai, M. Matsukawa2007

A control method of matrix converter for plasma control coil power supply

Katsuhiro Shimada, Jun-Ichi Itoh, Makoto Matsukawa, Kenichi Kurihara2007

Mechanical strength of various cyanate ester/epoxy insulation systems after fast neutron irradiation to the ITER design fluence and beyond

R. Prokopec, K. Humer, R.K. Maix, H. Fillunger, H.W. Weber2007

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