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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

Blanket material and technology developments toward DEMO under the Broader Approach framework

Takeo Nishitani, Toshihiko Yamanishi, Hiroyasu Tanigawa, Masaru Nakamichi, Kentaro Ochiai2014

Engineering design of the IFMIF EVEDA reference test cell and key components

Kuo Tian, Frederik Arbeiter, Yuming Chen, Volker Heinzel, Martin Mittwollen2014

The start-up and observation of the Li target in the EVEDA Li test loop

H. Kondo, T. Kanemura, T. Furukawa, Y. Hirakawa, E. Wakai2014

Effect of potential factors in manufacturing process on mechanical properties of F82H

Hideo Sakasegawa, Hiroyasu Tanigawa, Hisashi Tanigawa, Takanori Hirose2014

Optical absorption defects created in SiO2 by Si, O and He ion irradiation

Piedad Martin, David Jimenez-Rey, Rafael Vila, Fernando Sánchez, Rafael Saavedra2014

Metallurgical analysis of lithium test assembly operated for 1200 h

Tomohiro Furukawa, Hiroo Kondo, Takuji Kanemura, Yasuhi Hirakawa, Hiroshi Horiike2014

Progress of the ECRH Upper Launcher design for ITER

D. Strauss, G. Aiello, A. Bruschi, R. Chavan, B. Weinhorst2014

Non-linear failure analysis of HCPB blanket for DEMO taking into account high dose irradiation

J. Aktaa, S. Kecskés, P. Pereslavtsev, U. Fischer, L.V. Boccaccini2014

Microstructural characterization of a diffusion-bonded joint for 9Cr-ODS and JLF-1 reduced activation ferritic/martensitic steels

H.Y. Fu, T. Nagasaka, T. Muroga, A. Kimura, J.M. Chen2014

Compatibility of Ni and F82H with liquid Pb–Li under rotating flow

A. Kanai, C. Park, K. Noborio, R. Kasada, H. Tanigawa2014

Microstructures and mechanical properties of mechanically alloyed V–4Cr–4Ti alloy dispersion strengthened by nano-particles

P.F. Zheng, T. Nagasaka, T. Muroga, J.M. Chen2014

Evaluation of applicability of laser-based distance meter to measure Li-jet thickness for IFMIF/EVEDA project

Takuji Kanemura, Hiroo Kondo, Eiji Hoashi, Sachiko Yoshihashi-Suzuki, Eiichi Wakai2014

Depth-dependent nanoindentation hardness of reduced-activation ferritic steels after MeV Fe-ion irradiation

Ryuta Kasada, Satoshi Konishi, Kiyohiro Yabuuchi, Shuhei Nogami, Hiroyasu Tanigawa2014

Impact properties of electron beam welds of V–4Ti–4Cr alloys NIFS-HEAT-2 and CEA-J57

Valentyn Tsisar, Takuya Nagasaka, Marion Le Flem, Olga Yeliseyeva, Takeo Muroga2014

Influence of Cr content on the diffusive transport parameters and trapping of hydrogen in Fe alloys

I. Peñalva, G. Alberro, F. Legarda, R. Vila, C.J. Ortiz2014

Performance characterization of the FLEX low pressure helium facility for fusion technology experiments

Georg Schlindwein, Frederik Arbeiter2014

Joining techniques for a reduced activation 12Cr steel for inertial fusion energy

R.M. Hunt, B. El-Dasher, B.W. Choi, S.G. Torres2014

Oxidation behaviour of bulk W-Cr-Ti alloys prepared by mechanical alloying and HIPing

C. García-Rosales, P. López-Ruiz, S. Alvarez-Martín, A. Calvo, J. Brinkmann2014

Mechanical properties of similar and dissimilar weldments of RAFMS and AISI 316L (N) SS prepared by electron beam welding process

S.K. Albert, C.R. Das, Shiju Sam, P. Mastanaiah, Rajendra Kumar2014

Tritium transport calculations for the IFMIF Tritium Release Test Module

Jana Freund, Frederik Arbeiter, Ali Abou-Sena, Fabrizio Franza, Keitaro Kondo2014

Physical properties of F82H for fusion blanket design

Takanori Hirose, Takashi Nozawa, R.E. Stoller, Dai Hamaguchi, L.L. Snead2014

Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group

Derek Stork, Pietro Agostini, Jean-Louis Boutard, Derek Buckthorpe, Steven J. Zinkle2014

Fusion materials science and technology research opportunities now and during the ITER era

S.J. Zinkle, J.P. Blanchard, R.W. Callis, C.E. Kessel, B.D. Wirth2014

Radiological assessment of the limits and potential of reduced activation ferritic/martensitic steels

Hiroyasu Tanigawa, Yoji Someya, Hideo Sakasegawa, Takanori Hirose, Kentaro Ochiai2014

Neutron irradiation effects on tungsten materials

Akira Hasegawa, Makoto Fukuda, Shuhei Nogami, Kiyohiro Yabuuchi2014

Current status of technology development for fabrication of Indian Test Blanket Module (TBM) of ITER

T. Jayakumar, E. Rajendra Kumar2014

Alternative analysis for fuel storage and delivery in the ITER Tritium Plant

Min Ho Chang, Sei-Hun Yun, Hyun-Goo Kang, Seungyon Cho, Manfred Glugla2014

Fuskite® preliminary experimental tests based on permeation against vacuum for hydrogen recovery as a potential application in Pb15.7Li loop systems

R. Sacristán, G. Veredas, I. Bonjoch, I. Peñalva, F. Legarda2014

Theoretical prediction of thermodynamic properties of tritiated beryllium molecules and application to ITER source term

F. Virot, M. Barrachin, S. Souvi, L. Cantrel2014

Hydrogen and water vapor adsorption properties on cation-exchanged mordenite for use to a tritium recovery system

Yoshinori Kawamura, Yuki Edao, Yasunori Iwai, Takumi Hayashi, Toshihiko Yamanishi2014
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