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Title: Divertor target for magnetic containment device

Abstract

In a plasma containment device of a type having superconducting field coils for magnetically shaping the plasma into approximately the form of a torus, an improved divertor target for removing impurities from a "scrape off" region of the plasma comprises an array of water cooled swirl tubes onto which the scrape off flux is impinged. Impurities reflected from the divertor target are removed from the target region by a conventional vacuum getter system. The swirl tubes are oriented and spaced apart within the divertor region relative to the incident angle of the scrape off flux to cause only one side of each tube to be exposed to the flux to increase the burnout rating of the target. The divertor target plane is oriented relative to the plane of the path of the scrape off flux such that the maximum heat flux onto a swirl tube is less than the tube design flux. The containment device is used to contain the plasma of a tokamak fusion reactor and is applicable to other long pulse plasma containment systems.

Inventors:
 [1]
  1. (Garden City, NY)
Publication Date:
Research Org.:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
OSTI Identifier:
864297
Patent Number(s):
US 4343760
Assignee:
United States of America as represented by United States (Washington, DC)
DOE Contract Number:  
EY-76-C-02-3073
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
divertor; target; magnetic; containment; device; plasma; type; superconducting; field; coils; magnetically; shaping; approximately; form; torus; improved; removing; impurities; scrape; region; comprises; array; water; cooled; swirl; tubes; flux; impinged; reflected; removed; conventional; vacuum; getter; oriented; spaced; apart; relative; incident; angle; tube; exposed; increase; burnout; rating; plane; path; maximum; heat; design; contain; tokamak; fusion; reactor; applicable; pulse; systems; removing impurities; target region; target plane; field coils; heat flux; spaced apart; fusion reactor; plasma containment; field coil; water cooled; containment device; maximum heat; plasma comprises; tokamak fusion; divertor target; conventional vacuum; magnetic containment; /376/

Citation Formats

Luzzi, Jr., Theodore E. Divertor target for magnetic containment device. United States: N. p., 1982. Web.
Luzzi, Jr., Theodore E. Divertor target for magnetic containment device. United States.
Luzzi, Jr., Theodore E. 1982. "Divertor target for magnetic containment device". United States. https://www.osti.gov/servlets/purl/864297.
@article{osti_864297,
title = {Divertor target for magnetic containment device},
author = {Luzzi, Jr., Theodore E.},
abstractNote = {In a plasma containment device of a type having superconducting field coils for magnetically shaping the plasma into approximately the form of a torus, an improved divertor target for removing impurities from a "scrape off" region of the plasma comprises an array of water cooled swirl tubes onto which the scrape off flux is impinged. Impurities reflected from the divertor target are removed from the target region by a conventional vacuum getter system. The swirl tubes are oriented and spaced apart within the divertor region relative to the incident angle of the scrape off flux to cause only one side of each tube to be exposed to the flux to increase the burnout rating of the target. The divertor target plane is oriented relative to the plane of the path of the scrape off flux such that the maximum heat flux onto a swirl tube is less than the tube design flux. The containment device is used to contain the plasma of a tokamak fusion reactor and is applicable to other long pulse plasma containment systems.},
doi = {},
url = {https://www.osti.gov/biblio/864297}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1982},
month = {Fri Jan 01 00:00:00 EST 1982}
}