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Volumn 84, Issue 7-11, 2009, Pages 1438-1441

Thermal control of the liquid lithium divertor for NSTX

Author keywords

Divertor; Lithium; NSTX

Indexed keywords

CARTRIDGE HEATER; COPPER PLATE; DESIGN REQUIREMENTS; DIVERTOR; DIVERTOR TILES; HEAT LOADS; HELIUM COOLING; LIQUID LITHIUM; MELTING TEMPERATURES; NATIONAL SPHERICAL TORUS EXPERIMENTS; NSTX; SURFACE LAYERS; THERMAL CONTROL; THERMAL PERFORMANCE;

EID: 67349245520     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2008.11.098     Document Type: Article
Times cited : (16)

References (22)
  • 2
    • 0028460717 scopus 로고
    • Studies of global energy confinement in TFTR
    • Strachan J.D. Studies of global energy confinement in TFTR. Nucl. Fusion 34 (1994) 1017-1038
    • (1994) Nucl. Fusion , vol.34 , pp. 1017-1038
    • Strachan, J.D.1
  • 3
    • 0035741765 scopus 로고    scopus 로고
    • Observations concerning the injection of a lithium aerosol into the edge of TFTR discharges
    • and references therein
    • Mansfield D.K., Johnson D.W., Grek B., Kugel H.W., Bell M.G., Bell R.E., et al. Observations concerning the injection of a lithium aerosol into the edge of TFTR discharges. Nucl. Fusion 41 (2001) 1821-1832 and references therein
    • (2001) Nucl. Fusion , vol.41 , pp. 1821-1832
    • Mansfield, D.K.1    Johnson, D.W.2    Grek, B.3    Kugel, H.W.4    Bell, M.G.5    Bell, R.E.6
  • 10
    • 34248592412 scopus 로고    scopus 로고
    • Extremely low recycling and high power density handling in CDX-U lithium experiments
    • Kaita R., Majeski R., Doerner R., Gray T., Kugel H., Lynch T., et al. Extremely low recycling and high power density handling in CDX-U lithium experiments. J. Nucl. Mater. 363-365 (2007) 1231-1235
    • (2007) J. Nucl. Mater. , vol.363-365 , pp. 1231-1235
    • Kaita, R.1    Majeski, R.2    Doerner, R.3    Gray, T.4    Kugel, H.5    Lynch, T.6
  • 13
    • 0019345529 scopus 로고
    • A system for handling divertor ion and energy flux based on a lithium droplet cloud
    • Wells W. A system for handling divertor ion and energy flux based on a lithium droplet cloud. Nucl. Technol. Fusion 1 (1981) 120
    • (1981) Nucl. Technol. Fusion , vol.1 , pp. 120
    • Wells, W.1
  • 14
    • 4243824021 scopus 로고    scopus 로고
    • ALPS-advanced limiter-divertor plasma facing systems
    • ALPS Team
    • Mattas R., and ALPS Team. ALPS-advanced limiter-divertor plasma facing systems. Fusion Eng. Des. 49-50 (2000) 127
    • (2000) Fusion Eng. Des. , vol.49-50 , pp. 127
    • Mattas, R.1
  • 15
    • 0032648834 scopus 로고    scopus 로고
    • Exploring novel high power concepts for attractive fusion systems
    • the APEX Team
    • Abdou M.A., and the APEX Team. Exploring novel high power concepts for attractive fusion systems. Fusion Eng. Des. 45 (1999) 145-167
    • (1999) Fusion Eng. Des. , vol.45 , pp. 145-167
    • Abdou, M.A.1
  • 16
    • 7444266403 scopus 로고    scopus 로고
    • Design integration of liquid surface divertors
    • (special issue); also short version: R.E. Nygren et al., Liquid surface divertor designs for fusion reactors, 20th IEEE/NPSS Symposium on Fusion Engineering, ISBN 0-7803-7909-8 (2003) 284-287
    • Nygren R.E., Cowgill D.F., Ulrickson M.A., Nelson B.E., Fogarty P.J., Rognlien T.D., et al. Design integration of liquid surface divertors. Fusion Eng. Des. 72 (2004) 181-221 (special issue); also short version: R.E. Nygren et al., Liquid surface divertor designs for fusion reactors, 20th IEEE/NPSS Symposium on Fusion Engineering, ISBN 0-7803-7909-8 (2003) 284-287
    • (2004) Fusion Eng. Des. , vol.72 , pp. 181-221
    • Nygren, R.E.1    Cowgill, D.F.2    Ulrickson, M.A.3    Nelson, B.E.4    Fogarty, P.J.5    Rognlien, T.D.6
  • 17
    • 7444269174 scopus 로고    scopus 로고
    • A fusion reactor design with a liquid first wall and divertor
    • (special issue) also other papers in this special issue on innovative high-power density concepts for fusion plasma chambers; see also: R.E. Nygren et al., A fusion chamber design with a liquid first wall and divertor, 20th IEEE/NPSS Symposium on Fusion Engineering, ISBN 0-7803-7909-8 (2003) 288-295
    • Nygren R.E., Rognlien T.D., Rensink M.E., Smolentsev S.S., Youssef M.Z., Sawan M.E., et al. A fusion reactor design with a liquid first wall and divertor. Fusion Eng. Des. 72 1-3 (2004) 223-244 (special issue) also other papers in this special issue on innovative high-power density concepts for fusion plasma chambers; see also: R.E. Nygren et al., A fusion chamber design with a liquid first wall and divertor, 20th IEEE/NPSS Symposium on Fusion Engineering, ISBN 0-7803-7909-8 (2003) 288-295
    • (2004) Fusion Eng. Des. , vol.72 , Issue.1-3 , pp. 223-244
    • Nygren, R.E.1    Rognlien, T.D.2    Rensink, M.E.3    Smolentsev, S.S.4    Youssef, M.Z.5    Sawan, M.E.6
  • 21
    • 67349191258 scopus 로고    scopus 로고
    • L. Zakharov, private communications; various presentations to the staff at the Princeton Plasma Physics Laboratory, e.g., Operational and design space of LLD, Li/Mo capillary porous system (CPS) and Li/SS/Cu plate, NSTX Meeting, May 29, 2007, PPPL, Princeton NJ; some are on the website, w3.pppl.gov/∼zakharov.
    • L. Zakharov, private communications; various presentations to the staff at the Princeton Plasma Physics Laboratory, e.g., Operational and design space of LLD, Li/Mo capillary porous system (CPS) and Li/SS/Cu plate, NSTX Meeting, May 29, 2007, PPPL, Princeton NJ; some are on the website, w3.pppl.gov/∼zakharov.
  • 22
    • 34948850282 scopus 로고    scopus 로고
    • High heat flux testing of a helium-cooled tungsten tube with porous foam
    • Youchison D.L., Lutz T.J., Williams B., and Nygren R.E. High heat flux testing of a helium-cooled tungsten tube with porous foam. Fusion Eng. Des. 82 15-24 (2007) 1854-1860
    • (2007) Fusion Eng. Des. , vol.82 , Issue.15-24 , pp. 1854-1860
    • Youchison, D.L.1    Lutz, T.J.2    Williams, B.3    Nygren, R.E.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.