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Title: Divertor for use in fusion reactors

Abstract

A poloidal divertor for a toroidal plasma column ring having a set of poloidal coils co-axial with the plasma ring for providing a space for a thick shielding blanket close to the plasma along the entire length of the plasma ring cross section and all the way around the axis of rotation of the plasma ring. The poloidal coils of this invention also provide a stagnation point on the inside of the toroidal plasma column ring, gently curving field lines for vertical stability, an initial plasma current, and the shaping of the field lines of a separatrix up and around the shielding blanket.

Inventors:
 [1]
  1. (Trenton, NJ)
Issue Date:
Research Org.:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ
OSTI Identifier:
863326
Patent Number(s):
4149931
Assignee:
United States of America as represented by United States (Washington, DC) OSTI
DOE Contract Number:  
AT(11-1)-3073
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
divertor; fusion; reactors; poloidal; toroidal; plasma; column; set; coils; co-axial; providing; space; thick; shielding; blanket; close; entire; length; section; axis; rotation; provide; stagnation; inside; gently; curving; field; lines; vertical; stability; initial; current; shaping; separatrix; fusion reactors; poloidal divertor; plasma current; field lines; plasma column; entire length; toroidal plasma; fusion reactor; vertical stability; poloidal coil; /376/

Citation Formats

Christensen, Uffe R. Divertor for use in fusion reactors. United States: N. p., 1979. Web.
Christensen, Uffe R. Divertor for use in fusion reactors. United States.
Christensen, Uffe R. Mon . "Divertor for use in fusion reactors". United States. https://www.osti.gov/servlets/purl/863326.
@article{osti_863326,
title = {Divertor for use in fusion reactors},
author = {Christensen, Uffe R.},
abstractNote = {A poloidal divertor for a toroidal plasma column ring having a set of poloidal coils co-axial with the plasma ring for providing a space for a thick shielding blanket close to the plasma along the entire length of the plasma ring cross section and all the way around the axis of rotation of the plasma ring. The poloidal coils of this invention also provide a stagnation point on the inside of the toroidal plasma column ring, gently curving field lines for vertical stability, an initial plasma current, and the shaping of the field lines of a separatrix up and around the shielding blanket.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {1}
}

Patent:

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