메뉴 건너뛰기




Volumn 73, Issue 2-4, 2005, Pages 119-125

Primary results of the upgraded actively cooled limiter system of HT-7

Author keywords

Actively cooled limiter; Long plasma discharge

Indexed keywords

BOLTS; GRAPHITE; HEAT FLUX; IMPURITIES; LIMITERS; LOW TEMPERATURE EFFECTS; OPERATIONS RESEARCH; PLASMA THEORY; PLASMAS;

EID: 27744581028     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2005.03.001     Document Type: Article
Times cited : (11)

References (10)
  • 1
    • 0036644722 scopus 로고    scopus 로고
    • Actively cooled plasma facing components for long pulse high power operation
    • R.E. Nygren Actively cooled plasma facing components for long pulse high power operation Fusion Eng. Des. 60 2002 547 564
    • (2002) Fusion Eng. Des. , vol.60 , pp. 547-564
    • Nygren, R.E.1
  • 2
    • 14344274166 scopus 로고    scopus 로고
    • Actively cooled plasma facing components in tore supra
    • on behalf of Tore Supra team
    • P. Garin on behalf of Tore Supra team Actively cooled plasma facing components in tore supra Fusion Eng. Des. 56-57 2001 117 123
    • (2001) Fusion Eng. Des. , vol.56-57 , pp. 117-123
    • Garin, P.1
  • 3
    • 0141454828 scopus 로고    scopus 로고
    • Overview of steady-state operation on the tore supra tokamk
    • for the Tore Supra Team
    • G. Martin for the Tore Supra Team Overview of steady-state operation on the tore supra tokamk Nucl. Fusion 43 2003 817 821
    • (2003) Nucl. Fusion , vol.43 , pp. 817-821
    • Martin, G.1
  • 4
    • 0141514049 scopus 로고    scopus 로고
    • Preliminary results and lessons learned from upgrading the Tore Supra actively cooled plasma facing components of CBEL project)
    • J.J. Cordier Preliminary results and lessons learned from upgrading the Tore Supra actively cooled plasma facing components of CBEL project) Fusion Eng. Des. 66-68 2003 59 67
    • (2003) Fusion Eng. Des. , vol.66-68 , pp. 59-67
    • Cordier, J.J.1
  • 5
    • 0011508616 scopus 로고    scopus 로고
    • LHD helical divertor and its performance
    • Proceedings of 10th International Toki Conference on Plasma Physics and Controlled Nuclear Fusion (ITC-10) January 18-22, Toki-City, Japan Society of Plasma Science and Nuclear Fusion Research
    • N. Noda, R. Sakamoto, and Y. Kubota LHD helical divertor and its performance Proceedings of 10th International Toki Conference on Plasma Physics and Controlled Nuclear Fusion (ITC-10), vol. 3 January 18-22, Toki-City, Japan Society of Plasma Science and Nuclear Fusion Research J. Plasma Fusion Res. Ser. 2000 180
    • (2000) J. Plasma Fusion Res. Ser. , vol.3 , pp. 180
    • Noda, N.1    Sakamoto, R.2    Kubota, Y.3
  • 6
    • 13644284137 scopus 로고    scopus 로고
    • Fabrication and high heat flux testing of super mechanically joined divertor plate for LHD
    • Proceedings of 10th International Toki Conference on Plasma Physics and Controlled nuclear fusion (ITC-10) January 18-22, Toki-City, Japan Society of Plasma Science and Nuclesr Fusion Research
    • Y. Kubota, N. Noda, and S. Satoh Fabrication and high heat flux testing of super mechanically joined divertor plate for LHD Proceedings of 10th International Toki Conference on Plasma Physics and Controlled nuclear fusion (ITC-10), vol. 3 January 18-22, Toki-City, Japan Society of Plasma Science and Nuclesr Fusion Research J. Plasma Fusion Res. Ser. 2000 246
    • (2000) J. Plasma Fusion Res. Ser. , vol.3 , pp. 246
    • Kubota, Y.1    Noda, N.2    Satoh, S.3
  • 7
    • 3142709404 scopus 로고    scopus 로고
    • Temperature change and power deposition analysis of HT-7 tokainak limiter during long pulse plasma discharge
    • J.S. Hu, J.G. Li, and X.D. Zhang Temperature change and power deposition analysis of HT-7 tokainak limiter during long pulse plasma discharge High Power Laser Particle Beams 16 5 2004 597 602 (in Chinese)
    • (2004) High Power Laser Particle Beams , vol.16 , Issue.5 , pp. 597-602
    • Hu, J.S.1    Li, J.G.2    Zhang, X.D.3
  • 9
    • 17144437764 scopus 로고    scopus 로고
    • Selection of candidate doped graphite materials as plasma facing components for HT-7U devices
    • Quangui Guo, and Jiangang Li Selection of candidate doped graphite materials as plasma facing components for HT-7U devices J. Nucl. Mater. 313 2003 144 148
    • (2003) J. Nucl. Mater. , vol.313 , pp. 144-148
    • Quangui, G.1    Jiangang, L.2
  • 10
    • 0037340443 scopus 로고    scopus 로고
    • Impurity generation and suppression during IBW heating in HT-7
    • J. Li, Y.P. Zhao, and B.N. Wan Impurity generation and suppression during IBW heating in HT-7 J. Nucl. Mater. 313-316 2003 1188 1191
    • (2003) J. Nucl. Mater. , vol.313-316 , pp. 1188-1191
    • Li, J.1    Zhao, Y.P.2    Wan, B.N.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.