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Measurements of impurity concentrati...
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Boyle, Dennis Patrick.
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Measurements of impurity concentrations and transport in the Lithium Tokamak Experiment.
紀錄類型:
書目-電子資源 : Monograph/item
正題名/作者:
Measurements of impurity concentrations and transport in the Lithium Tokamak Experiment./
作者:
Boyle, Dennis Patrick.
出版者:
Ann Arbor : ProQuest Dissertations & Theses, : 2016,
面頁冊數:
142 p.
附註:
Source: Dissertation Abstracts International, Volume: 78-04(E), Section: B.
Contained By:
Dissertation Abstracts International78-04B(E).
標題:
Plasma physics. -
電子資源:
http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=10167489
ISBN:
9781369218381
Measurements of impurity concentrations and transport in the Lithium Tokamak Experiment.
Boyle, Dennis Patrick.
Measurements of impurity concentrations and transport in the Lithium Tokamak Experiment.
- Ann Arbor : ProQuest Dissertations & Theses, 2016 - 142 p.
Source: Dissertation Abstracts International, Volume: 78-04(E), Section: B.
Thesis (Ph.D.)--Princeton University, 2016.
This thesis presents new measurements of core impurity concentrations and transport in plasmas with lithium coatings on all-metal plasma facing components (PFCs) in the Lithium Tokamak Experiment (LTX). LTX is a modest-sized spherical tokamak uniquely capable of operating with large area solid and/or liquid lithium coatings essentially surrounding the entire plasma (as opposed to just the divertor or limiter region in other devices).
ISBN: 9781369218381Subjects--Topical Terms:
3175417
Plasma physics.
Measurements of impurity concentrations and transport in the Lithium Tokamak Experiment.
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Source: Dissertation Abstracts International, Volume: 78-04(E), Section: B.
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This thesis presents new measurements of core impurity concentrations and transport in plasmas with lithium coatings on all-metal plasma facing components (PFCs) in the Lithium Tokamak Experiment (LTX). LTX is a modest-sized spherical tokamak uniquely capable of operating with large area solid and/or liquid lithium coatings essentially surrounding the entire plasma (as opposed to just the divertor or limiter region in other devices).
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Lithium (Li) wall-coatings have improved plasma performance and confinement in several tokamaks with carbon (C) PFCs, including the National Spherical Torus Experiment (NSTX). In NSTX, contamination of the core plasma with Li impurities was very low (<0.1%) despite extensive divertor coatings. Low Li levels in NSTX were found to be largely due to neoclassical forces from the high level of C impurities. Studying impurity levels and transport with Li coatings on stainless steel surfaces in LTX is relevant to future devices (including future enhancements to NSTX-Upgrade) with all-metal PFCs.
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The new measurements in this thesis were enabled by a refurbished Thomson scattering system and improved impurity spectroscopy, primarily using a novel visible spectrometer monitoring several Li, C, and oxygen (O) emission lines. A simple model was used to account for impurities in unmeasured charge states, assuming constant density in the plasma core and constant concentration in the edge. In discharges with solid Li coatings, volume averaged impurity concentrations were low but non-negligible, with~2-4% Li, ~0.6-2% C, ~0.4-0.7% O, and Z eff<1.2.
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Transport was assessed using the TRANSP, NCLASS, and MIST codes. Collisions with the main H ions dominated the neoclassical impurity transport, unlike in NSTX, where collisions with C dominated. Furthermore, neoclassical transport coefficients calculated with NCLASS were similar across all impurity species and differed no more than a factor of two, in contrast to NSTX where they differed by an order of magnitude. However, time-independent simulations with MIST indicated that unlike NSTX, neoclassical theory did not fully capture the impurity transport and anomalous transport likely played a significant role in determining impurity profiles.
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