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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

TRIEX facility: An experimental loop to test tritium extraction systems from lead lithium

A. Aiello, A. Ciampichetti, M. Utili, G. Benamati2007

Helium loop for the HCPB Test Blanket Module

H. Neuberger, X. Jin, L.V. Boccaccini, B.E. Ghidersa, R. Meyder2007

Performance of modified pulse-operated piezoelectric valves for the gas inlet system of RFX

A. Masiello, S. Dal Bello, M. Fincato, F. Rossetto2007

Pressurizing behavior on ingress of coolant into pebble bed of blanket of Fusion DEMO reactor

Daigo Tsuru, Mikio Enoeda, Masato Akiba2007

Non-stoichiometory and vaporization characteristic of Li2.1TiO3.05 in hydrogen atmosphere

Tsuyoshi Hoshino, Masaru Yasumoto, Kunihiko Tsuchiya, Kimio Hayashi, Takayuki Terai2007

Installation of liquid phase catalytic exchange columns for the Wolsong tritium removal facility

K.M. Song, S.H. Sohn, D.W. Kang, S.W. Paek, D.H. Ahn

2007

Measurement of thermal expansion of Li2TiO3 pebble beds

Hisashi Tanigawa, Mikio Enoeda, Masato Akiba2007

The performance of a trickle-bed reactor packed with a Pt/SDBC catalyst mixture for the CECE process

Seungwoo Paek, Do-Hee Ahn, Heui-Joo Choi, Kwang-Rag Kim, Soon Hwan Sohn2007

In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3–SiO2 including CrPO4

M. Nakamichi, T.V. Kulsartov, K. Hayashi, S.E. Afanasyev, A.N. Kolbaenkov2007

Experimental investigation of liquid-metal flows through a sudden expansion at fusion-relevant Hartmann numbers

L. Bühler, S. Horanyi, E. Arbogast2007

Application of discrete element method to study mechanical behaviors of ceramic breeder pebble beds

Zhiyong An, Alice Ying, Mohamed Abdou2007

Adaptation of the HCPB DEMO TBM as breeding blanket for ITER: Neutronic and thermal analyses

D. Aquaro, N. Cerullo, I. Ciucci, D. Morellini2007

Integrated thermo-fluid analysis towards helium flow path design for an ITER solid breeder blanket module

A. Ying, M. Narula, R. Hunt, M. Abdou, I. Komada2007

Measurement and analysis of neutron and gamma-ray flux spectra in a neutronics mock-up of the HCPB Test Blanket Module

K. Seidel, P. Batistoni, U. Fischer, H. Freiesleben, R. Villari2007

A 2D finite element modelling of tritium permeation for the HCLL DEMO blanket module

F. Gabriel, Y. Escuriol, F. Dabbene, O. Gastaldi, L. Giancarli2007

Tritium management in HCLL-PPCS model AB blanket

I. Ricapito, A. Aiello, A. Ciampichetti, G. Benamati, M. Zucchetti2007

Thermal–hydraulic analysis of the HCLL DEMO blanket

G. Aiello, F. Gabriel, L. Giancarli, G. Rampal, J.-F. Salavy2007

The JET high frequency pellet injector project

Alain Geraud, M. Dentan, A. Whitehead, P. Butcher, I. Vinyar2007

Numerical investigation of liquid metal flows in rectangular sudden expansions

C. Mistrangelo, L. Bühler2007

The production and delivery of inertial fusion energy power plant fuel: The cryogenic target

A.S. Bozek, N.B. Alexander, D. Bittner, L. Carlson, B.A. Vermillion2007

The test blanket modules project in Europe: From the strategy to the technical plan over next 10 years

Y. Poitevin, L.V. Boccaccini, G. Dell’Orco, E. Diegele, M. Zmitko2007

EU fuel cycle development priorities for ITER

D. Murdoch, I. Cristescu, C. Day, M. Glugla, A. Mack2007

Verification to recover tritium in neutron-irradiated Li by Y plate

Satoshi Fukada, Yasushi Maeda, Mika Kinoshita, Takeo Muroga2007

Chemical form of released tritium from solid breeder materials under the various purge gas conditions

T. Kinjyo, M. Nishikawa, N. Yamashita, T. Koyama, M. Enoeda2007

Nuclear performance analyses for HCPB test blanket modules in ITER

U. Fischer, P. Pereslavtsev, P. Kotiluoto, F. Wasastjerna2007

Experimental validation of a method for performance monitoring of the impurity processing stage in the TEP system of ITER

B. Bornschein, D. Corneli, M. Glugla, K. Günther, K.H. Simon2007

Commissioning of water detritiation and cryogenic distillation systems at TLK in view of ITER design

I. Cristescu, Ioana R. Cristescu, L. Dörr, M. Glugla, W. Wurster2007

Hydrogen permeation through membranes with cracks in protection layer

A. Pisarev, I. Tsvetkov, S. Yarko2007

Design of the ITER torus prototype cryopump

V. Hauer, J.-C. Boissin, Chr. Day, H. Haas, M. Wykes2007

Overview of the last progresses for the European Test Blanket Modules projects

J.-F. Salavy, L.V. Boccaccini, R. Lässer, R. Meyder, A. Aiello2007

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