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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.« less

Inventors:
 [1];  [2];  [3]
  1. Somerset, NJ
  2. (Hopewell Township, Mercer County, NJ)
  3. Titusville, NJ
Issue Date:
Research Org.:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ
OSTI Identifier:
875193
Patent Number(s):
H24
Assignee:
United States of America as represented by United States (Washington, DC)
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
toroidal; midplane; neutral; beam; armor; plasma; limiter; tokamak; fusion; reactor; magnetic; coil; inner; wall; evacuated; toriodal; chamber; heated; fusing; magnetically; confined; shield; provided; shine-thru; deposition; forms; semicircular; enclosure; outer; surface; shaped; match; closely; practical; limiting; flux; toroidally; indented; bean-shaped; plurality; graphite; plates; pair; coupled; upper; sections; plate; positioned; intimate; contact; adjacent; form; closed; planar; structure; entire; periphery; circular; adapted; coupling; heat; sensing; thermocouples; circulating; water; conduit; cooling; center; portion; receive; enclose; section; diagnostic; loop; minimize; power; confinement; incident; circulating water; center portion; confinement chamber; magnetic coil; outer periphery; inner wall; magnetic flux; outer surface; fusion reactor; plasma confinement; intimate contact; neutral beam; magnetically confined; plasma deposition; plasma limiter; toroidal chamber; tokamak fusion; flux surface; plate positioned; graphite plates; shaped plasma; beam heated; /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 = {1986},
month = {1}
}

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