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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

公式サイト

Impact Factor

1.7

Citescore

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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全 15,142 件の論文
並び順:新しい順古い順被引用数順

The integral experiment on beryllium with D-T neutrons for verification of tritium breeding

Yury Verzilov, Satoshi Sato, Kentaro Ochiai, Masayuki Wada, Takeo Nishitani2007

Activation and clearance of vanadium alloys and beryllium multipliers in fusion reactors

S.A. Bartenev, A. Ciampichetti, N.G. Firsin, R. Forrest, M. Zucchetti2007

Economic assessment of fusion and fusion-driven subcritical systems based on internalization of external costs and benefits

S. Zhang, D. Huang, L. Hu2007

Comparison and analysis of expert and student views on the use of energy scenarios in communication on fusion research

Gunter Bombaerts, Erik Laes2007

Benchmarking of SNAM with the ITER 3D model

H. Hu, Y. Wu, M. Chen, Q. Zeng, P. Long2007

Benchmarking of MCAM 4.0 with the ITER 3D model

Y. Li, L. Lu, A. Ding, H. Hu, Y. Wu
2007

Safety assessment of energy fluxes on in-vessel components with SAFALY

Jesus Izquierdo, Javier Dies, Jeronimo Garcia, Carlos Tapia, Lina Rodriguez2007

Impact of N-isotope composition control of ferritic steel on classification of radioactive materials from fusion reactor

T. Hayashi, R. Kasada, K. Tobita, S. Nishio, S. Jitsukawa2007

State of the art of fusion material recycling and remaining issues

V. Massaut, R. Bestwick, K. Bróden, L. Di Pace, R. Pampin2007

Quality management for WENDELSTEIN 7-X—Lessons learned

J.-H. Feist, H.-J. Bramow, R. Brockmann, G. Gliege, R. Vilbrandt2007

Filtering of particulates by cracks in containment barriers

W.E. Han2007

Power saving of large scaled helium compressor for fusion device using an adsorption chiller

M. Noguchi, S. Yamada, S. Moriuchi, K. Kuramochi, T. Mito2007

Conceptual design of the cryogenic system for the helical-type fusion power plant FFHR

S. Yamada, A. Sagara, S. Imagawa, T. Mito, O. Motojima2007

Validation of computational fluid dynamics (CFD) tools for the development of a helium-cooled divertor

R. Kruessmann, G. Messemer, P. Norajitra, J. Weggen, K. Zinn2007

A dose rate experiment at JET for benchmarking the calculation direct one step method

M. Angelone, L. Petrizzi, M. Pillon, S. Popovichev, R. Villari2007

Safety design of radiation shielding for JT-60SA

A.M. Sukegawa, S. Sakurai, K. Masaki, K. Kizu, M. Matsukawa2007

Thin slit streaming experiment for ITER by using D-T neutron source

K. Ochiai, S. Sato, M. Wada, N. Kubota, C. Konno2007

Verification of nuclear data for DT neutron induced charged-particle emission reaction of light nuclei

K. Kondo, I. Murata, K. Ochiai, N. Kubota, T. Nishitani2007

Burnup calculation of fusion–fission hybrid energy system with thorium cycle

M. Matsunaka, S. Shido, K. Kondo, H. Miyamaru, I. Murata2007

New burnup calculation system for fusion–fission hybrid reactor

I. Murata, S. Shido, M. Matsunaka, K. Kondo, H. Miyamaru2007

Reliability of the TJ-II power supply system: Collection and analysis of the operational experience data

Jesus Izquierdo, Javier Dies, Jeronimo Garcia, Carlos Tapia, Lina Rodriguez2007

Assessment of occupational radiation exposure (ORE) for hands-on assistance to the remote handling at ITER ports and waste treatment

L. Di Pace, T. Pinna2007

Energy storage system for a pulsed DEMO

J. Lucas, M. Cortés, P. Méndez, J. Hayward, D. Maisonnier2007

Impact of risk analysis on ITER nuclear buildings layout

Laurent Sabathé, Franck Lignini, Lina Rodríguez-Rodrigo, Joëlle Uzan-Elbez, Jean-Philippe Girard2007

He-cooled divertor development for DEMO

P. Norajitra, R. Giniyatulin, T. Ihli, G. Janeschitz, B. Zeep2007

Activation of the IFMIF lithium loop corrosion products

G. Cambi, D.G. Cepraga, M. Frisoni, T. Pinna2007

Corrosion and activation in fusion cooling loops—TRACT

Panos Karditsas, Aristides Caloutsis2007

Deliberating and communicating the potential of fusion power based on long-term foresight knowledge

Erik Laes, Gunter Bombaerts2007

The value of modern decision-making support services to fusion projects

Claude Pascal, Christian Blanchet, Jean-Marc Ollivier2007

Recent progress in DEMO fusion core engineering: Improved segmentation, maintenance and blanket concepts

T. Ihli, L.V. Boccaccini, G. Janeschitz, C. Koehly, P. Sardain2007
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