Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules
- Author
- TANIGAWA, H1 ; HIROSE, T1 ; KOHYAMA, A2 ; KATAYAMA, S3 ; MORI, H5 ; NISHIMOTO, K5 ; KLUEH, R. L6 ; SOKOLOV, M. A6 ; STOLLER, R. E6 ; ZINKLE, S. J6 ; SHIBA, K1 ; KASADA, R2 ; WAKAI, E1 ; SERIZAWA, H3 ; KAWAHITO, Y3 ; JITSUKAWA, S1 ; KIMURA, A2 ; KOHNO, Y4
[1] Japan Atomic Energy Agency, Tokai, Ibaraki 319-1195, Japan
[2] Institute of Advanced Energy, Kyoto University, Uji, Kyoto 611-0011, Japan
[3] Joining and Welding Research Institute, Osaka University, Ibaraki, Osaka 567-0047, Japan
[4] Department of Materials Science and Engineering, Muroran Institute of Technology, Muroran, Hokkaido 050-8585, Japan
[5] Division of Materials & Manufacturing Science, Osaka University, Ibaraki, Osaka 565-0871, Japan
[6] Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831-6132, United States - Conference title
- Proceedings of the Eighth International Symposium on Fusion Nuclear Technology
- Conference name
- International Symposium on Fusion Nuclear Technology (Heidelberg 2007-09-30)
- Author (monograph)
- BOCCACCINI, Lorenzo Virgilio (Editor); JANESCHITZ, Guenter (Editor); LEICHTLE, Dieter (Editor); NEUBERGER, Heiko (Editor); NORAJITRA, Prachai (Editor); RIETH, Michael (Editor)
- Source
Fusion engineering and design. 2008, Vol 83, Num 10-12, pp 1471-1476, 6 p ; ref : 29 ref
- CODEN
- FEDEEE
- ISSN
- 0920-3796
- Scientific domain
- Energy; Metallurgy, welding
- Publisher
- Elsevier, Amsterdam
- Publication country
- Netherlands
- Document type
- Conference Paper
- Language
- English
- Author keyword
- F82H Fabrication HAZ Irradiation effect Over-tempered HAZ RAFM TBM WCSB Weld
- Keyword (fr)
- Acier ferritique Acier martensitique Base de données Enceinte recyclage Haute température Propriété mécanique Recherche et développement Refroidissement Réacteur fusion nucléaire Soudage Soudure Tokamak
- Keyword (en)
- Ferritic steel Martensitic steel Database Blanket High temperature Mechanical properties Research and development Cooling Nuclear fusion reactor Welding Weld Tokamak
- Keyword (es)
- Acero ferrítico Acero martensítico Base dato Recinto reciclaje Alta temperatura Propiedad mecánica Investigación desarrollo Enfriamiento Reactor fusión nuclear Soldadura Soldadura Tokamak
- Classification
- Pascal
- 001 Exact sciences and technology / 001D Applied sciences / 001D06 Energy / 001D06D Energy. Thermal use of fuels / 001D06D04 Installations for energy generation and conversion: thermal and electrical energy. / 001D06D04E Controled nuclear fusion plants
- Discipline
- Energy
- Origin
- Inist-CNRS
- Database
- PASCAL
- INIST identifier
- 21040289
Sauf mention contraire ci-dessus, le contenu de cette notice bibliographique peut être utilisé dans le cadre d’une licence CC BY 4.0 Inist-CNRS / Unless otherwise stated above, the content of this bibliographic record may be used under a CC BY 4.0 licence by Inist-CNRS / A menos que se haya señalado antes, el contenido de este registro bibliográfico puede ser utilizado al amparo de una licencia CC BY 4.0 Inist-CNRS
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DOI
10.1016/j.fusengdes.2008.07.024 
https://dx.doi.org/10.1016/j.fusengdes.2008.07.024
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