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:
- Issue Date:
- Research Org.:
- Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- US Atomic Energy Commission (AEC)
- OSTI Identifier:
- 863326
- Patent Number(s):
- 4149931
- Application Number:
- 05/379870
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21B - FUSION REACTORS
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- DOE Contract Number:
- AT(11-1)-3073
- Resource Type:
- Patent
- Resource Relation:
- Patent File Date: 1973 Jul 16
- 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 = {Mon Jan 01 00:00:00 EST 1979},
month = {Mon Jan 01 00:00:00 EST 1979}
}
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