skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Plasma/liquid metal interactions during tokamak operation.

Abstract

One of the critical technological challenges of future tokamak fusion devices is the ability for plasma-facing components to handle both normal and abnormal plasma/surface interaction events that compromise their lifetime and operation of the machine. Under normal operation plasma/surface interactions that are important include: sputtering, particle implantation and recycling, He pumping and ELM (edge localized modes)-induced erosion. In abnormal or off-normal operation: disruptions and vertical displacement events (VDEs) are important. To extend PFC lifetime under these conditions, liquid-metals have been considered as candidate PFCs (Plasma-Facing Components), including: liquid lithium, tin-lithium, gallium and tin. Liquid lithium has been measured to have nonlinear increase of physical sputtering with rise in temperature. Such increase can be a result of exposure to ELM-level particle fluxes. The significant increase in particle flux to the divertor and nearby PFCs can enhance sputtering erosion by an order of magnitude or more. In addition from the standpoint of hydrogen recycling and helium pumping liquid lithium appears to be a good candidate plasma-facing material (PFM). Advanced designs of first wall and divertor systems propose the application of liquid-metals as an alternate PFC to contend with high-heat flux constraints of large-scale tokamak devices. Additional issues include PFC operation under disruptionsmore » and long temporal instabilities such as VDEs. A comprehensive two-fluid model is developed to integrate core and SOL (scrape-off layer) parameters during ELMs with PFC surface evolution using the HEIGHTS package. Special emphasis is made on the application of lithium as a candidate plasma-facing liquid-metal.« less

Authors:
; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
957382
Report Number(s):
ANL/ET/CP-116239
TRN: US201002%%950
DOE Contract Number:
DE-AC02-06CH11357
Resource Type:
Conference
Resource Relation:
Journal Name: Fusion Sci. Technol.; Journal Volume: 47; Journal Issue: 3 ; Apr. 2005; Conference: 16th ANS Topical Meeting on the Technology of Fusion (TOFE); Sep. 14, 2004 - Sep. 16, 2004; Madison, WI
Country of Publication:
United States
Language:
ENGLISH
Subject:
08 HYDROGEN; DIVERTORS; FIRST WALL; GALLIUM; HELIUM; HYDROGEN; LIFETIME; LIQUID METALS; LITHIUM; PUMPING; RECYCLING; SOLS; SPUTTERING; TOKAMAK DEVICES

Citation Formats

Hassanein, A., Allain, J. P., Insepov, Z., Konkashbaev, I., and Energy Technology. Plasma/liquid metal interactions during tokamak operation.. United States: N. p., 2005. Web.
Hassanein, A., Allain, J. P., Insepov, Z., Konkashbaev, I., & Energy Technology. Plasma/liquid metal interactions during tokamak operation.. United States.
Hassanein, A., Allain, J. P., Insepov, Z., Konkashbaev, I., and Energy Technology. Fri . "Plasma/liquid metal interactions during tokamak operation.". United States. doi:.
@article{osti_957382,
title = {Plasma/liquid metal interactions during tokamak operation.},
author = {Hassanein, A. and Allain, J. P. and Insepov, Z. and Konkashbaev, I. and Energy Technology},
abstractNote = {One of the critical technological challenges of future tokamak fusion devices is the ability for plasma-facing components to handle both normal and abnormal plasma/surface interaction events that compromise their lifetime and operation of the machine. Under normal operation plasma/surface interactions that are important include: sputtering, particle implantation and recycling, He pumping and ELM (edge localized modes)-induced erosion. In abnormal or off-normal operation: disruptions and vertical displacement events (VDEs) are important. To extend PFC lifetime under these conditions, liquid-metals have been considered as candidate PFCs (Plasma-Facing Components), including: liquid lithium, tin-lithium, gallium and tin. Liquid lithium has been measured to have nonlinear increase of physical sputtering with rise in temperature. Such increase can be a result of exposure to ELM-level particle fluxes. The significant increase in particle flux to the divertor and nearby PFCs can enhance sputtering erosion by an order of magnitude or more. In addition from the standpoint of hydrogen recycling and helium pumping liquid lithium appears to be a good candidate plasma-facing material (PFM). Advanced designs of first wall and divertor systems propose the application of liquid-metals as an alternate PFC to contend with high-heat flux constraints of large-scale tokamak devices. Additional issues include PFC operation under disruptions and long temporal instabilities such as VDEs. A comprehensive two-fluid model is developed to integrate core and SOL (scrape-off layer) parameters during ELMs with PFC surface evolution using the HEIGHTS package. Special emphasis is made on the application of lithium as a candidate plasma-facing liquid-metal.},
doi = {},
journal = {Fusion Sci. Technol.},
number = 3 ; Apr. 2005,
volume = 47,
place = {United States},
year = {Fri Apr 01 00:00:00 EST 2005},
month = {Fri Apr 01 00:00:00 EST 2005}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: