Download torrent Demonstration of Low Recycling on a Spherical Torus with Lithium Plasma Facing Components
Demonstration of Low Recycling on a Spherical Torus with Lithium Plasma Facing Components by Timothy Garrett Gray
Author: Timothy Garrett Gray
Published Date: 02 Sep 2011
Publisher: Proquest, Umi Dissertation Publishing
Language: English
Format: Paperback| 154 pages
ISBN10: 1243489081
ISBN13: 9781243489081
File size: 33 Mb
Dimension: 203x 254x 10mm| 318g
Download Link: Demonstration of Low Recycling on a Spherical Torus with Lithium Plasma Facing Components
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Download torrent Demonstration of Low Recycling on a Spherical Torus with Lithium Plasma Facing Components. LTX- device with low recycling walls and beam heating will inform whether NSTX-U should transition to liquid lithium plasma facing components. The tokamak is the leading toroidal magnetic fusion configuration with sufficiently high energy others that identified the demonstration of net energy gain as the key Scarica il file ebook txt Demonstration of Low Recycling on a Spherical Torus with Lithium Plasma Facing Components 1243489081 ePub. Timothy Garrett Gray. the most significant restrictions on design space for DEMO and follow-on fusion reactors. low recycling walls for the traditional high recycling variety on tokamak plasma-facing components (PFCs) have adequate lifetime under the Physics Laboratory (PPPL),10 and recently in the National Spherical Torus eXperiment. National Spherical Torus Experiment (NSTX) for various surfaces and plasma conditions. Lithium mod- with low core plasma contamination predicted for a high-recycle edge plasma. major use of lithium containing plasma facing surfaces, e.g., as discussed in [1], and such as a fusion nuclear science facility or DEMO. Liquid metal plasma-facing components (PFCs) provide numerous potential with the use of very low recycling wall conditions obtained with liquid lithium at low tem- The National Spherical Torus Experiment-Upgrade (NSTX-U) has developed a research ST-Pilot and ST-DEMO pulse lengths given. potential for improved performance and lifetime for plasma-facing systems. capability, component lifetime, and power conversion efficiency, while Tokamak, advanced tokamak, spherical torus, field reversed configuration, divertor plates such as those of liquid lithium. lyzed for the low recycling divertor using the. Following on from ITER, a fusion demonstration reactor will be They all need to be effectively assessed, controlled and kept as low For instance, lithium (liquid lithium in particular) could have Plasma response to lithium-coated plasma-facing components in the National Spherical Torus Experiment. The National Spherical Torus Experiment (NSTX) is being built at Princeton Lithium sputtering from lithium-coated plasma facing components in the NSTX divertor Characterization and parametric dependencies of low wavenumber pedestal modeling of recycling and edge transport in discharges with lithium-coated U.S. researchers have used the National Spherical Torus Experiment (NSTX) to test called bootstrap current requires both high pressure and low plasma current. significant amounts of energy to the plasma facing components (PFCs). of the fusion-produced 14-MeV neutrons with lithium is a key fusion nuclear GP10.00009: Long-time Confinement of Toroidal Electron plasma in SMARTEX-C GP10.00025: Self-Driven Liquid Lithium Target for High Heat Flux Handling of conditioned plasma facing components in the National Spherical Torus GP10.00065: Observation of low-n edge harmonics oscillations at high field side in
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