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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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Relationship between fabrication parameters and structural characteristics of sintered lithium orthosilicate

C.Y. Chu, K. Bär, J.P. Singh, R.B. Poeppel, M.C. Billone1989

Mechanical properties and deformation of polycrystalline lithium orthosilicate

K. Bär, C.Y. Chu, J.P. Singh, K.C. Goretta, R.B. Poeppel1989

Recent experimental results of the rates of hydrogen permeation through metallic materials in the presence of liquid pb17li alloy: Influence on the performance and design of tritium recovery equipment

A. Viola, P.L. Lolli-Ceroni, G. Pierini1989

Tritium recovery from some ceramic breeding materials

H. Kwast, A. Kout, R.P. Muis, M.P. Stijkel, J.D. Elen1989

Tritium diffusivity in lithium-based ceramic breeders irradiated with neutrons

Kenji Okuno, Hiroshi Kudo1989

Modeling of tritium recovery from ctr solid breeder

Takayuki Terai, Yoichi Takahashi, Satoru Tanaka, Michio Yamawaki

1989

Tritium recovery from neutron irradiated li-pb alloys

Makoto Okamoto, Yoshinori Shibuya, Masao Aida, Yasuhiko Fujii1989

Combined gettering and molten salt process for tritium recovery from lithium

D.K. Sze, P.A. Finn, J. Bartlit, S. Tanaka, M. Yamawaki1989

Tritium dissolution in and release from li2o

Shigeru O'Hira, Takumi Hayashi, Kenji Okuno, Hiroshi Kudo1989

A study of tritium behavior in lithium oxide by ion conductivity measurements

Kenji Noda, Yoshinobu Ishii, Hisayuki Matsui, Hideo Ohno, Hitoshi Watanabe1989

Tritium release from lithium silicate

W. Breitung, M. Briec, H. Werle1989

Tritium recovery from molten LiF-BeF2 salt

Jun Oishi, Hirotake Moriyama, Seiichiro Maeda, Yoshiyuki Asaoka1989

The effect of 14 MeV neutron irradiation on tritium recovery from lithium oxide

Hirotake Moriyama, Jun Oishi, Takayuki Terai, Kazutaka Kawamura1989

Material selection for the titan reversed-field pinch reactor

S. Sharafat, N.M. Ghoniem, P.I.H. Cooke, The TITAN Research Group1989

Mhd flow tailoring in first wall coolant channels of self-cooled blankets

B.F. Picologlou, C.B. Reed, T.Q. Hua, L. Barleon, J.S. Walker1989

Conceptual studies of a two-phase liquid metal cooled blanket system for magnetically confined fusion reactors

Masanori Aritomi, Akira Inoue, Minoru Takahashi, Mitsuo Matsuzaki, Nobuharu Suzuki1989

Research and development of liquid metal systems for a tokamak reactor

B.G. Karasev, I.V. Lavrentjev, A.F. Kolesnichenko, O.A. Lielausis, A.V. Tananaev1989

Mhd enhancement of heat transfer and its relevance to fusion reactor blanket design

S. Sukoriansky, D. Klaiman, H. Branover, E. Greenspan1989

Instabilities of natural convection heat transfer from a horizontal cylinder to potassium under a horizontal magnetic field

N. Takenaka, O. Takahashi, I. Michiyoshi1989

Development of a computational method for the full solution of mhd flow in fusion blankets

Chang N. Kim, Ali H. Hadid, Mohamed A. Abdou1989

Analysis of liquid metal mhd flow using an iterative method to solve the core flow equations

K.A. McCarthy, M.S. Tillack, M.A. Abdou1989

Numerical analysis for laminar and turbulent liquid-metal flow in a transverse magnetic field

Minora Takahashi, Akira Inoue, Masanori Aritomi, Mitsuo Matsuzaki1989

Mhd thermal hydraulic analysis of three-dimensional liquid-metal flows in fusion blanket ducts

T.Q. Hua, B.F. Picologlou, C.B. Reed, J.S. Walker1989

Mhd pressure drop along a nak flow around a stepwise change of tube diameter under a transverse magnetic field

Keiji Miyazaki, Masaaki Nakano, Tomomitsu Horiba, Shoji Inoue, Nobuo Yamaoka1989

A ceramic breeder in a poloidal tube blanket for a tokamak reactor

A. Amici, L. Anzidei, M. Gallina, V. Rado, L. Petrizzi1989

Technical considerations on tritium breeding blanket systems for a fusion power reactor

T. Kuroda, K. Sato, T. Suzuki, T. Tone, M. Seki1989

Prospects of the aqueous self-cooled blanket concept for net

M. Snykers, W.F. Bogaerts, A. Bruggeman, M.J. Embrechts, D. Steiner1989

An aqueous lithium salt blanket option for fusion power reactors

Don Steiner, Georgios Varsamis, Lowell Deutsch, John Rathke, Paul Gierszewski1989

Aqueous tritium breeding blanket with natural lithium

Masabumi Nishikawa, Toshihiko Kawano, Kenzo Munakata, Yukinori Kanda, Hideki Nakashima1989

Mechanical design of the tiber breeding shield

J. Rathke, L. Deutsch1989

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