英国物理学会
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作者:... G.G. van Eden , M.A. Jaworski , N.J. Lopes Cardozo
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (5)
摘要:To develop realistic liquid lithium divertors for future fusion reactors, this paper aims to improve the understanding of their power handling capabilities. A liquid lithium divertor target prototype, designed to facilitate liquid metal experiments in tokamaks, was tested in...
作者:M.A. Jaworski , B.P. LeBlanc ...
来源:[J].Nuclear Fusion(IF 2.734), 2018, Vol.58 (4)
摘要:The National Spherical Torus Experiment Upgrade (NSTX-U) will advance the physics basis required for achieving steady-state, high-beta, and high-confinement conditions in a tokamak by accessing high toroidal fields (1 T) and plasma currents (1.0–2.0 MA) in a low aspect ratio...
作者:M.A. Jaworski , Y. Hirooka ...
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:... T.W. Morgan , M.A. Jaworski , N.J. Lopes Cardozo
来源:[J].Nuclear Fusion(IF 2.734), 2018, Vol.58 (10)
摘要:A model is formulated to make a first estimate of the maximum tolerable power of liquid lithium (Li) divertor targets, and to gain insight into their behaviour in terms of Li loss rate and surface temperature. The model, formulated as a simple analytical expression, states t...
作者:M.A. Jaworski , R. Kaita ...
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:M.A. Jaworski , M. Chen ...
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:... T. Abrams , M.A. Jaworski , Emily A. Carter
来源:[J].Nuclear Fusion(IF 2.734), 2016, Vol.56 (1)
摘要:Because of lithium’s possible use as a first wall material in a fusion reactor, a fundamental understanding of the interactions between liquid lithium (Li) and deuterium (D) is important. We predict structural and dynamical properties of liquid Li samples with high concentra...
作者:M.A. Jaworski , T. Abrams ...
来源:[J].Nuclear Fusion(IF 2.734), 2013, Vol.53 (8)
摘要:Liquid metal plasma-facing components (PFCs) have been proposed as a means of solving several problems facing the creation of economically viable fusion power reactors. To date, few demonstrations exist of this approach in a diverted tokamak and we here provide an overview o...
作者:... W. Xu , D. Andruczyk , M.A. Jaworski
来源:[J].Nuclear Fusion(IF 2.734), 2011, Vol.51 (10), pp.102002 (4pp)
摘要:Observation of liquid lithium flow in metal trenches has been made using a lithium–metal infused trench (LiMIT) tile and is reported here. The flow is self-pumping and uses thermoelectric magnetohydrodynamics to remove heated lithium and replenish it at a lower temperature. ...

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