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Volumn 52, Issue 3, 2007, Pages 375-382

Superconducting Tokamak JT-60SA project for ITER and demo researches

Author keywords

[No Author keywords available]

Indexed keywords

FUSION REACTOR DIVERTORS; HEATING; NEUTRONS; RADIATION; REMOTE CONSOLES; SUPERCONDUCTING MATERIALS;

EID: 35448951731     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST07-A1516     Document Type: Conference Paper
Times cited : (10)

References (16)
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  • 2
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  • 3
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    • Design study of National Centralized Tokamak facility for the demonstration of steady state high-β plasma operation
    • H. TAMAI et al., "Design study of National Centralized Tokamak facility for the demonstration of steady state high-β plasma operation", Nucl. Fusion 45, 1676 (2005).
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    • TAMAI, H.1
  • 4
    • 33845981296 scopus 로고    scopus 로고
    • Overview of the National Centralized Tokamak programme
    • M. KIKUCHI et al., "Overview of the National Centralized Tokamak programme", Nucl. Fusion, 46,S29(2006).
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    • KIKUCHI, M.1
  • 5
    • 0141842722 scopus 로고    scopus 로고
    • Ferromagnetic and resistive wall effects on the beta limit in a tokamak
    • G. KURITA et al., "Ferromagnetic and resistive wall effects on the beta limit in a tokamak", Nucl. Fusion 43, 949 (2003)
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    • KURITA, G.1
  • 6
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    • Progress toward long-pulse high-performance Advanced Tokamak discharges on the DIII-D tokamak
    • M. R. WADE et al., "Progress toward long-pulse high-performance Advanced Tokamak discharges on the DIII-D tokamak", Phys. Plasmas 8, 2208 (2001)
    • (2001) Phys. Plasmas , vol.8 , pp. 2208
    • WADE, M.R.1
  • 7
    • 33644596047 scopus 로고    scopus 로고
    • Ripple Reduction with Ferritic Insert in JFT-2M
    • K. SHINOHARA et al., "Ripple Reduction with Ferritic Insert in JFT-2M", Fusion Sci. Tech., 49 187 (2006)
    • (2006) Fusion Sci. Tech , vol.49 , pp. 187
    • SHINOHARA, K.1
  • 8
    • 35448982824 scopus 로고    scopus 로고
    • Overview of JT-60U Results for Developments of Steady-state Advanced Tokamak Scenario
    • IAEA-CN-149/OV/1-2, IAEA, Chengdu
    • H. TAKENAGA et al., "Overview of JT-60U Results for Developments of Steady-state Advanced Tokamak Scenario", Proc. 21st Int. Conf. of Fusion Energy, IAEA-CN-149/OV/1-2, IAEA, Chengdu, (2006).
    • (2006) Proc. 21st Int. Conf. of Fusion Energy
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  • 9
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    • Regime identification in ASDEX Upgrade
    • L. GIANNONE et al, "Regime identification in ASDEX Upgrade", Plasma Phys. Control. Fusion 46, 835 (2004)
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  • 10
    • 2942560980 scopus 로고    scopus 로고
    • TAKIZUKA, "Roles of aspect ratio, absolute B and effective Z of the H-mode power threshold in tokamaks of the ITPA database
    • ITPA H-mode Power Threshold Database Working Group presented by T
    • ITPA H-mode Power Threshold Database Working Group presented by T. TAKIZUKA, "Roles of aspect ratio, absolute B and effective Z of the H-mode power threshold in tokamaks of the ITPA database", Plasma Phys. Control. Fusion 46, A227 (2004)
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  • 11
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    • Design Optimization for Plasma Control and Assessment of Operation Regime in JT-60SA
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  • 12
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  • 14
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  • 15
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.