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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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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. Walker

1989

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

Iter/tiber helium-cooled solid and liquid breeder test module designs and evaluations

C.P.C. Wong, E.T. Cheng, R.L. Creedon, B.A. Engholm, K.R. Schultz1989

A new 3He gas loop blanket for fusion reactor systems

Eiji Takada, Tetsuo Iguchi, Masaharu Nakazawa1989

Examination of mhd fluid flow in geometric elements of a fusion reactor blanket using the core flow approach

M.S. Tillack1989

Computer code for analyzing liquid metal mhd flow in rectangular duct under strong transverse magnetic field

Haruki Madarame, Tsuyoshi Hagiwara1989

The breeding shield design for the technology test reactor TIBER-II

M.E. Sawan, J.D. Lee1989

IN-situ tritium release experiments from solid breeding materials (TTTEx) — tritium diffusion coefficients and surface reaction on lithium aluminate

Satoru Tanaka, Atsushi Kawamoto, Michio Yamawaki, Takayuki Terai, Minoru Saito1989

Current experimental activities for solid breeder development

Carl E. Johnson, Glenn W. Hollenberg, Nicole Roux, Hitoshi Watanabe1989

The impact of new experimental data on the design of Pb-17Li/Water breeding blankets

Radiolysis and corrosion aspects of the aqueous self-cooled blanket concept

A. Bruggeman, M. Snykers, W.F. Bogaerts, R. Waeben, D. Steiner1989

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