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Volumn 47, Issue 4, 2005, Pages 1023-1030

Plan and strategy for ITER blanket testing in Japan

Author keywords

[No Author keywords available]

Indexed keywords

DATA ACQUISITION; DECISION MAKING; FUSION REACTIONS; HIGH TEMPERATURE EFFECTS; IRRADIATION; STRATEGIC PLANNING;

EID: 20844440699     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST05-A822     Document Type: Conference Paper
Times cited : (4)

References (14)
  • 1
    • 0346280219 scopus 로고    scopus 로고
    • Design and technology development of solid breeder blanket cooled by supercritical water in Japan
    • M. ENOEDA et al., "Design and technology development of solid breeder blanket cooled by supercritical water in Japan", Nuclear Fusion, volume 43, issue 12, pages 1837 - 1844 (2003) and http://stacks.iop.org/0029- 5515/43/1837
    • (2003) Nuclear Fusion , vol.43 , Issue.12 , pp. 1837-1844
    • Enoeda, M.1
  • 2
    • 0346666751 scopus 로고    scopus 로고
    • Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H
    • S. JITSUKAWA et al., "Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H", J. Nucl. Mater., 307-311, (2002) 179-186.
    • (2002) J. Nucl. Mater. , vol.307-311 , pp. 179-186
    • Jitsukawa, S.1
  • 3
    • 3343024744 scopus 로고    scopus 로고
    • Issues and advances in SiCf/SiC composites development for fusion reactors
    • B. Riccardi, et al., "Issues and advances in SiCf/SiC composites development for fusion reactors", J. Nucl. Mater., 329-333 (2004) 56-65.
    • (2004) J. Nucl. Mater. , vol.329-333 , pp. 56-65
    • Riccardi, B.1
  • 4
    • 0036941145 scopus 로고    scopus 로고
    • Vanadium alloys - Overview and recent results
    • T. Muroga et al. "Vanadium alloys - overview and recent results", J. Nucl. Mater., 307-311, 547 (2002).
    • (2002) J. Nucl. Mater. , vol.307-311 , pp. 547
    • Muroga, T.1
  • 5
    • 17544371889 scopus 로고    scopus 로고
    • Design and development of ceramic breeder demo blanket
    • Yokohama, Japan, 19-24 October 1998, FTP/29
    • M. ENOEDA, et al., "Design and Development of Ceramic Breeder Demo Blanket", IAEA-CN-69, 17th Fusion Energy Conference, Yokohama, Japan, 19-24 October 1998, FTP/29(1998).
    • (1998) IAEA-CN-69, 17th Fusion Energy Conference
    • Enoeda, M.1
  • 6
    • 17544374049 scopus 로고    scopus 로고
    • Design of test blanket system for ITER module testing
    • H. MIURA, et al., "Design of Test Blanket System for ITER Module Testing", JAERI-Tech 97-051 (1997).
    • (1997) JAERI-tech , vol.97 , Issue.51
    • Miura, H.1
  • 7
    • 18744402864 scopus 로고    scopus 로고
    • Russian Li/V self-cooled test blanket module
    • 01. 03
    • Design Description Document "Russian Li/V self-cooled Test Blanket Module" (01. 03. 2001)
    • (2001) Design Description Document
  • 11
    • 3342922740 scopus 로고    scopus 로고
    • Recent progress in the development of electrically insulating coating for a liquid lithium blanket
    • B.A. Pint et al., Recent progress in the development of electrically insulating coating for a liquid lithium blanket, J. Nucl. Mater., 329-333, (2004) 119
    • (2004) J. Nucl. Mater. , vol.329-333 , pp. 119
    • Pint, B.A.1
  • 12
    • 17544368251 scopus 로고    scopus 로고
    • Experimental study of tritium recovery from liquid lithium by yttrium
    • to be presented at (May, Tokyo)
    • M. Kinoshita, S. Fukada, N. Yamashita, T. Muroga, M. Nishikawa, "Experimental study of tritium recovery from liquid lithium by yttrium", to be presented at ISFNT-7 (May, 2005, Tokyo)
    • (2005) ISFNT-7
    • Kinoshita, M.1    Fukada, S.2    Yamashita, N.3    Muroga, T.4    Nishikawa, M.5


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.