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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

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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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並び順:新しい順古い順被引用数順

Thermal effect of periodical bakeout on tritium inventory in first wall and permeation to coolant in reactor life

Katsuhiko Nakahara, Yasushi Seki, Shigetada Kobayashi1989

Safety analysis of the fer fuel circulating system

Yasushi Seki, Hiromasa Iida, Shigetada Kobayashi, Hiroshi Ohmura, Isao Ishikawa1989

TFTR tritium inventory analysis

A.E. Pontau, D.K. Brice, D.A. Buchenauer, R.A. Causey, J.N. Brooks1989

Uranium for hydrogen isotope removal from inert gas streams

W.T. Shmayda, N.P. Kherani1989

Development of zirconium-cobalt beds for recovery, storage and supply of tritium

Satoshi Konishi, Takanori Nagasaki, Nobuhisa Yokokawa, Yuji Naruse1989

Plasma exhaust purification with metal getters

H. Albrecht, R.-D. Penzhorn, Th. Kastner, M. Sirch

1989

Absorption breakthrough of hydrogen isotopes and desorption in a zirconium-vanadium particle bed

N. Mitsuishi, S. Fukada, H. Tokuda, T. Nawata, Y. Takai1989

Simultaneous ion- and gas-driven permeation of hydrogen isotopes through first wall material

K. Yamaguchi, S. Tanaka, M. Yamawaki, T. Namba1989

Analysis of transient permeation behavior of hydrogen isotope caused by abrupt temperature change of first wall and blanket wall material

Michio Yamawaki, Satoru Tanaka, Tsukasa Kiyoshi1989

On the estimation of tritium retention and permeation in metallic first wall

Tetsuo Tanabe1989

Hydrogen isotope separation characteristics of cryogenic distillation column

Mikio Enoeda, Toshihiko Yamanishi, Hiroshi Yoshida, Yuji Naruse, Kenji Muta1989

H2O-HTO isotope separation by distillation of water — a dynamics of HETP of SUS Dixon ring in a small packed column

Ichiro Yamamoto, Akira Kaba, Akira Kanagawa1989

Development of a gas chromatographic system for hydrogen isotope separation

Effect of oxygen on solubility of hydrogen isotopes in titanium

Shinsuke Yamanaka, Taku Tanaka, Shinya Tsuboi, Masanobu Miyake1989

Conceptual design of a closed vacuum pumping system using turbomolecular pump for fusion reactor

A selective pump for hydrogen isotopes based on the superpermeation effect in iron

H. Hackfort1989

Sorption of tritium on surface-modified type-316 stainless steel

Takakuni Hirabayashi, Masakatsu Saeki, Teikichi A. Sasaki, Ki-Woung Sung1989

Tritium permeation through iron

Hideki Hagi, Yasunori Hayashi1989

The TFTR maintenance manipulator

D. Kungl, D. Loesser, P. Heitzenroeder, M. Selig, G. Cerdan1989

Preliminary design of a blanket handling device and evaluation of the feasibility of eliminating the spread of radioactive dust contamination

Ph. Charruyer, H. Djerassi, L. Giancarli, M. Maupou1989

Remote maintenance concepts for net

C. Holloway, E. Salpietro, M. Chazalon1989

Nuclear safety enhancements to the compact ignition tokamak

D.F. Holland, S.J. Brereton, R.E. Lyon1989

Fusion reactor materials to minimize long-lived radioactive waste

Carlo Ponti1989

Radioactivity aspects of fusion reactors

Ceramic turbomolecular pumping system in reactor structure of FER

K. Ioki, A. Kameari, N. Ueda, K. Hikita, Y. Murakami1989

Development and application of charcoal sorbents for cryopumping fusion devices

D.W. Sedgley1989

Integrated plasma exhaust cryotransfer and processing for net

P.J. Dinner, D.K. Murdoch1989

The role of a blanket tritium system on the fusion fuel cycle

D.K. Sze, P. Finn, R. Clemmer, J. Anderson, H. Yoshida1989

Commissioning of the tritium process laboratory at the JAERI

Yuji Naruse, Yuji Matsuda, Kichizo Tanaka, Satoshi Konishi, TPL Operation Group1989

Multi-dimensional neutronics analyses in the double null configuration of net

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