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  • IOP Publishing  (2)
  • Nakanishi, H.
  • 2005-2009  (2)
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  • IOP Publishing  (2)
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  • 2005-2009  (2)
Year
  • 1
    In: Nuclear Fusion, IOP Publishing, Vol. 49, No. 10 ( 2009-10-01), p. 104015-
    Abstract: Remarkable progress in the physical parameters of net-current free plasmas has been made in the Large Helical Device (LHD) since the last Fusion Energy Conference in Chengdu, 2006 (Motojima et al 2007 Nucl. Fusion 47 S668 ). The beta value reached 5% and a high-beta state beyond 4.5% from the diamagnetic measurement has been maintained for longer than 100 times the energy confinement time. The density and temperature regimes have also been extended. The central density has exceeded 1 × 10 21  m −3 due to the formation of an internal diffusion barrier . The ion temperature has reached 5.2 keV at the density of 1.6 × 10 19  m −3 , which is associated with the suppression of ion heat conduction loss. Although these parameters have been obtained in separated discharges, each fusion-reactor relevant parameter has elucidated the potential of net-current free heliotron plasmas. Diversified studies in recent LHD experiments are reviewed in this paper.
    Type of Medium: Online Resource
    ISSN: 0029-5515 , 1741-4326
    Language: Unknown
    Publisher: IOP Publishing
    Publication Date: 2009
    detail.hit.zdb_id: 2037980-8
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  • 2
    In: Nuclear Fusion, IOP Publishing, Vol. 47, No. 9 ( 2007-09-01), p. 1250-1257
    Abstract: Achieving steady-state plasma operation at high plasma temperatures is one of the important goals of worldwide magnetic fusion research. High temperatures of approximately 1–2 keV, and steady-state plasma sustainment operations have been reported. Recently the steady-state operation regime was greatly extended in the Large Helical Device (LHD). A high-temperature plasma was created and maintained for 54 min with 1.6 GJ in the 2005FY experimental programme. The three-dimensional heat-deposition profile of the LHD helical divertor was modified, and during long-pulse discharges it effectively dispersed the heat load using a magnetic axis swing technique developed at the LHD. A sweep of only 3 cm in the major radius of the magnetic axis position (less than 1% of the major radius of the LHD) was enough to disperse the divertor heat load. The steady-state plasma was heated and sustained mainly by hydrogen minority ion heating using ion cyclotron range of frequencies and partially by electron cyclotron of fundamental resonance frequency. By accumulating the small flux of charge-exchanged neutral particles during the long-pulse operation, a high energy ion tail which extended up to 1.6 MeV was observed. This is the first experimental evidence of high energetic ion confinement of MeV range in helical devices. The long-pulse operations lasted until a sudden increase in radiation loss occurred, presumably because of metal wall flakes dropping into the plasma. The sustained line-averaged electron density and temperature were approximately 0.8 × 10 19  m −3 and 2 keV, respectively, at a 1.3 GJ discharge (#53776) and 0.4 × 10 19  m −3 and 1 keV at a 1.6 GJ discharge (#66053). The average input power was 680 kW and 490 kW, and the plasma duration was 32 min and 54 min, respectively. These successful long operations show that the heliotron configuration has a high potential as a steady-state fusion reactor.
    Type of Medium: Online Resource
    ISSN: 0029-5515 , 1741-4326
    Language: Unknown
    Publisher: IOP Publishing
    Publication Date: 2007
    detail.hit.zdb_id: 2037980-8
    Location Call Number Limitation Availability
    BibTip Others were also interested in ...
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