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Title: Toroidal midplane neutral beam armor and plasma limiter

Abstract

For use in a tokamak fusion reactor having a midplane magnetic coil on the inner wall of an evacuated toriodal chamber within which a neutral beam heated, fusing plasma is magnetically confined, a neutral beam armor shield and plasma limiter is provided on the inner wall of the toroidal chamber to shield the midplane coil from neutral beam shine-thru and plasma deposition. The armor shield/plasma limiter forms a semicircular enclosure around the midplane coil with the outer surface of the armor shield/plasma limiter shaped to match, as closely as practical, the inner limiting magnetic flux surface of the toroidally confined, indented, bean-shaped plasma. The armor shield/plasma limiter includes a plurality of semicircular graphite plates each having a pair of coupled upper and lower sections with each plate positioned in intimate contact with an adjacent plate on each side thereof so as to form a closed, planar structure around the entire outer periphery of the circular midplane coil. The upper and lower plate sections are adapted for coupling to heat sensing thermocouples and to a circulating water conduit system for cooling the armor shield/plasma limiter.The inner center portion of each graphite plate is adapted to receive and enclose a section ofmore » a circular diagnostic magnetic flux loop so as to minimize the power from the plasma confinement chamber incident upon the flux loop.

Inventors:
 [1]; ;  [2]
  1. Somerset, NJ
  2. Titusville, NJ
Issue Date:
Research Org.:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
875193
Patent Number(s):
H000024
Application Number:
06/739648
Assignee:
United States of America as represented by United States (Washington, DC)
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Patent
Resource Relation:
Patent File Date: 1985 May 31
Country of Publication:
United States
Language:
English
Subject:
tokamak; tokamak fusion reactor; magnetic coil; toriodal chamber; plasma limiter; neutral beam; graphite plate; statutory invention registration; /376/

Citation Formats

Kugel, Henry W., Hand, Jr., Samuel W., and Ksayian, Haig. Toroidal midplane neutral beam armor and plasma limiter. United States: N. p., 1986. Web.
Kugel, Henry W., Hand, Jr., Samuel W., & Ksayian, Haig. Toroidal midplane neutral beam armor and plasma limiter. United States.
Kugel, Henry W., Hand, Jr., Samuel W., and Ksayian, Haig. Wed . "Toroidal midplane neutral beam armor and plasma limiter". United States. https://www.osti.gov/servlets/purl/875193.
@article{osti_875193,
title = {Toroidal midplane neutral beam armor and plasma limiter},
author = {Kugel, Henry W. and Hand, Jr., Samuel W. and Ksayian, Haig},
abstractNote = {For use in a tokamak fusion reactor having a midplane magnetic coil on the inner wall of an evacuated toriodal chamber within which a neutral beam heated, fusing plasma is magnetically confined, a neutral beam armor shield and plasma limiter is provided on the inner wall of the toroidal chamber to shield the midplane coil from neutral beam shine-thru and plasma deposition. The armor shield/plasma limiter forms a semicircular enclosure around the midplane coil with the outer surface of the armor shield/plasma limiter shaped to match, as closely as practical, the inner limiting magnetic flux surface of the toroidally confined, indented, bean-shaped plasma. The armor shield/plasma limiter includes a plurality of semicircular graphite plates each having a pair of coupled upper and lower sections with each plate positioned in intimate contact with an adjacent plate on each side thereof so as to form a closed, planar structure around the entire outer periphery of the circular midplane coil. The upper and lower plate sections are adapted for coupling to heat sensing thermocouples and to a circulating water conduit system for cooling the armor shield/plasma limiter.The inner center portion of each graphite plate is adapted to receive and enclose a section of a circular diagnostic magnetic flux loop so as to minimize the power from the plasma confinement chamber incident upon the flux loop.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jan 01 00:00:00 EST 1986},
month = {Wed Jan 01 00:00:00 EST 1986}
}