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作者:R. Kaita , S.M. Kaye ...
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (10)
摘要:The National Spherical Torus Experiment (NSTX) has undergone a major upgrade, and the NSTX Upgrade (NSTX-U) Project was completed in the summer of 2015. NSTX-U first plasma was subsequently achieved, diagnostic and control systems have been commissioned, the H-mode accessed, magn...
作者:R. Kaita , T.K. Gray ...
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (11)
摘要:Steady-state fusion power plant designs present major divertor technology challenges, including high divertor heat flux both in steady-state and during transients. In addition to these concerns, there are the unresolved technology issues of long term dust accumulation and as...
作者:R. Kaita , R. Maingi
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (7)
摘要:By employing a neutral gas shielding (NGS) model to characterize impurity granule injection, the ablation rates for three different species of granule: lithium, boron, and carbon, are determined. Utilizing the duration of ablation events recorded on experiments performed at ...
作者:R. Kaita , J.E. Menard ...
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (7)
摘要:The National Spherical Torus Experiment-Upgrade (NSTX-U) is the most powerful spherical torus facility at PPPL, Princeton USA. The major mission of NSTX-U is to develop the physics basis for an ST-based Fusion Nuclear Science Facility (FNSF). The ST-based FNSF has the promis...
作者:R. Kaita , D.P. Stotler ...
来源:[J].Nuclear Fusion(IF 2.734), 2016, Vol.56 (1)
摘要:Lithium-coated high- Z substrates are planned for use in the NSTX-U divertor and are a candidate plasma facing component (PFC) for reactors, but it remains necessary to characterize the gross Li erosion rate under high plasma fluxes (>1023 m−2 s−1<...
作者:R. Kaita , T. Kozub ...
来源:[J].Nuclear Fusion(IF 2.734), 2009, Vol.49 (5), pp.055014 (7pp)
摘要:Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relative increase (an enhancement factor of 5–10) in Ohmic tokamak confinement ever observed. The confinement results from CDX-U do not agree with existing scaling laws, and cannot easily be...
作者:R. Kaita , H. Kugel ...
来源:[J].Nuclear Fusion(IF 2.734), 2009, Vol.49 (6), pp.065006 (6pp)
摘要:Experiments in NSTX have now demonstrated the coupling of toroidal plasmas produced by the technique of coaxial helicity injection (CHI) to inductive sustainment and ramp-up of the toroidal plasma current. In these discharges, the central Ohmic transformer was used to apply an in...
作者:R. Kaita , B. LeBlanc ...
来源:[J].Nuclear Fusion(IF 2.734), 2009, Vol.49 (8), pp.085028 (10pp)
摘要:The first experimental assessment of low-Z impurity transport in a neutral beam heated, high-confinement H-mode plasma sustained in a low-field, low-aspect ratio spherical tokamak, was performed at the National Spherical Torus Experiment (NSTX). The injected impurities penet...
作者:R. Kaita , H.W. Kugel ...
来源:[J].Nuclear Fusion(IF 2.734), 2009, Vol.49 (9), pp.095025 (10pp)
摘要:Experiments conducted in high-performance 1.0 and 1.2 MA 6 MW NBI-heated H-mode discharges with a high magnetic flux expansion radiative divertor in NSTX demonstrate that significant divertor peak heat flux reduction and access to detachment may be facilitated naturally in a...
作者:R. Kaita , E. Kolemen ...
来源:[J].Nuclear Fusion(IF 2.734), 2011, Vol.51 (1), pp.012001 (4pp)
摘要:Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high-power density divertors. A novel 'snowflake' divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry be...

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