NDLI: Evaluation of material erosion from plasma-facing surfaces in hard disruptions via simulated ablation due to heat flux in electrothermal discharges

Content Provider	IEEE Xplore Digital Library
Author	Echols, J.R. Winfrey, A.L.
Copyright Year	2013
Description	Author affiliation: Nucl. Eng. Program, Virginia Tech, Blacksburg, VA, USA (Echols, J.R.; Winfrey, A.L.)
Abstract	Advanced fusion energy systems require the development of materials able to resist high operating temperatures, high neutron irradiation, and high thermo-mechanical stresses. Additional requirements for fusion materials include low absorption cross-sections, high thermal conductivity, and minimal swelling. Graphite, beryllium, lithium, stainless steel, tungsten, copper, and molybdenum are among the materials and alloy/ceramic components proposed for use in fusion reactors. Even with advances in the reliability of non-disruptive plasma systems, plasma-facing components, such as the diverter and first wall, must withstand abnormal hard disruption events as well as normal operational conditions. Sustained operation of fusion devices necessitates understanding long-term effects of materials response to high heat fluxes experienced during disruptions. The high heat flux effects on fusion reactor suitable materials is investigated herein by simulating heat flux deposition to materials of the interior liners inside electrothermal (ET) plasma sources, which produce high-density $(10^{23}-10^{27}/m^{3})$ plasmas with heat fluxes of up to 125 $GW/m^{2}$ over a period of 100μs relevant to expected heat fluxes during hard disruptions. Radiative heat flux to the inner wall of the ET source ablates the wall material, forming a dense vapor of excited atoms or molecules dissociated from the wall, followed by their ionization. The ETFLOW is a 1D time dependent code which models ET sources, the plasma formation and flow inside the source. Additionally, it calculates the incident and deposited heat flux, the amount of ablated mass, the pressure, velocity and number densities of the species. Erosion of selected materials has been studied over a range of heat fluxes comparable to expected heat fluxes during hard disruptions in future tokamaks. Computational experiments using heat fluxes between $10GW/m^{2}$ and 125 $GW/m^{2}$ have shown low total erosion for low-z materials (Li, Be, C) and higher erosion for high-z materials (Fe, Cu, Mo, W). The time rate of material erosion for various ranges of heat fluxes shows increased erosion with time evolution over the 150 ms pulse length of the simulated disruption event. At the highest values of heat flux simulated, low-z materials were found to ablate almost identically. At all simulated values of heat flux, the ablation of high-z materials correlated positively with z-number.
Starting Page	1
Ending Page	5
File Size	758497
Page Count	5
File Format	PDF
e-ISBN	9781479901715
DOI	10.1109/SOFE.2013.6635503
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	2013-06-10
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Materials Heating Tungsten Discharges (electric) Fusion reactors Plasma sources high energy density plasma fusion disruption electrothermal plasma high heat flux erosion plasma-facing surfaces
Content Type	Text
Resource Type	Article

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1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
3	National Digital Library of India Office, Indian Institute of Technology Kharagpur	The administrative and infrastructural headquarters of the project	Dr. B. Sutradhar bsutra@ndl.gov.in
4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
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