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Showing 1 to 16 of 16 for “"Plasma Facing Component"”.
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Effects of porosity on surface chemistry, wetting, and percolation in porous tungsten, liquid lithium hybrid plasma facing component system
… continues to be the material of choice for plasma facing components (PFC) in the divertor region of future plasma-burning fusion nuclear devices due to favorable properties such as high melting point, high thermal conductivity and low sputtering yield. However, challenges remain for the use …
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Studies of plasma potential measurements using an ion-sensistive probe
The plasma potential of the scrape-off-layer (SOL) in the tokamak is a key indicator of the erosion rate of the plasma facing component (PFC) material. The Alcator C-Mod SOL plasma potential is currently measured by emissive probes, which is an established potential diagnostic, yet the probes are …
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Development and testing of an in situ method of ion beam analysis for measuring high-Z erosion inside a tokamak using an AIMS diagnostic
While many ex situ measurements exist to measure plasma-facing component (PFC) surfaces of materials extracted from tokamaks, developing a deeper understanding of the dynamics of erosion, redeposition, and fuel retention in these surfaces will require in situ measurements. A first-of-a-kind …
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Chemical sputtering studies of lithiated ATJ graphite
Plasma Facing Component (PFC) materials are crucial to fusion reactor development. There is no one material that functions as an ideal PFC material. As a result, coatings are applied to control the interaction between plasmas and the PFC material. Lithium wall conditioning treatments in the …
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Temperature-Enhanced Low-Energy Ion Sputtering of Liquid Tin: Measurements and Modeling
The potential for liquid Sn as a plasma-facing component in advanced thermonuclear fusion reactors and the observation of temperature-enhanced sputtering of Sn under low energy, light ion bombardment motivated further investigation of the temperature-dependent sputtering properties of Sn under …
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Optimization of the thermal-hydraulic performance of the helium-cooled modular divertor with multiple jets
The divertor is a key plasma-facing component of future commercial magnetic fusion energy (MFE) reactors that helps sustain fusion reactions by removing helium ash particles and impurities from the core plasma. The divertor target plates are therefore subject to high steady-state incident heat …
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An in-situ accelerator-based diagnostic for plasma-material interactions science in magnetic fusion devices
Plasma-material interactions (PMI) in magnetic fusion devices such as fuel retention, material erosion and redeposition, and material mixing present significant scientific and engineering challenges, particularly for the next generation of devices that will move towards reactor-relevant conditions. …
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Experimental and numerical analysis of thermoelectric magnetohydrodynamic driven liquid lithium flow in open channels for fusion applications
The concept of using molten metal as a plasma facing material (PFM) has been widely considered, and liquid lithium, among many choices, has attracted a lot of research interests in recent years. Compared to the traditional solid plasma facing component (PFC) a liquid lithium PFC may effectively …
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In situ and post mortem surface chemistry measurements of boronization in the national spherical torus experiment upgrade
Plasma facing component (PFC) conditioning has been shown to improve plasma performance in tokamaks by reducing impurities in the core. The method of PFC conditioning used in the National Spherical Torus eXperiment Upgrade (NSTX-U) during the 2015-2016 experimental campaign was boron conditioning. …
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Dynamic interactions between energetic D and He ions on lithium-tungsten plasma-facing interfaces
… of highly-dense high-temperature fusion plasmas, a considerably higher demand is placed on the plasma facing components (PFCs) with an increase of fusion power production. Currently within operating experimental reactors, the PFCs need to handle only a few MW/m$^2$ of heat flux and …
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Heat transfer analysis of thermoelectric driven swirling flow
… heat from the divertor region. The solid plasma facing materials (PFM) suffer from the sputtering and thermal stress. An alternative way is to utilize liquid metal especially the liquid lithium as the divertor material. An experiment on CDX-U found that a shallow pool of liquid lithium …
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Response Of Plasma Facing Components In Tokamaks Due To Intense Energy Deposition Using Particle-In-Cell(pic) Methods
<p>Damage to plasma-facing components (PFC) due to various plasma instabilities is still a major concern for the successful development of fusion energy and represents a significant research obstacle in the community. It is of great importance to fully understand the behavior and lifetime …
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Thermal Desorption Spectroscopy Measurements of Hydrogen Retention in Flowing Liquid Lithium
Made available in DSpace on 2017-07-06T18:55:42Z (GMT). No. of bitstreams: 3 Olczak_Wieslaw_W_MS.pdf: 1180395 bytes, checksum: 7d82ac8bfb0643dbe1d1b55c59fa21b5 (MD5) Olczak_Wieslaw_W_MS_ABS.pdf: 40741 bytes, checksum: 152e9b0d550225e9814fc7adb7710818 (MD5) license.txt: 4813 bytes, checksum: …
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Experimental Erosion Study of Lithium-On-Carbon Surfaces for Fusion Devices
Made available in DSpace on 2017-07-06T18:55:56Z (GMT). No. of bitstreams: 3 Racic_Marin_Z_MS.pdf: 1548205 bytes, checksum: d31513136d9968205cdeaa1221700e86 (MD5) Racic_Marin_Z_MS_ABS.pdf: 10694 bytes, checksum: 2cfebabd10663ef4d7f4388fb861ba8b (MD5) license.txt: 4813 bytes, checksum: …
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The design and development of hydrogen isotope extraction technologies for a limit-style liquid lithium loop
As lithium has grown in popularity as a plasma-facing material, efforts have been placed on examining its viability as a first wall candidate. Lithium has proven over numerous studies to improve core confinement, while allowing access to operational regimes previously unattainable while using …
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Development of high energy pulsed plasma simulator for plasma-lithium trench experiment
… lithium infused trench (LiMIT) device, a pulsed plasma source utilizing a theta pinch in conjunction with a coaxial plasma accelerator has been developed. An overall objective of the project is to develop a compact device that can produce 100 MW/m2 to 1 GW/m2 of plasma heat flux (a typical heat …