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Title: Tokamak plasma current disruption infrared control system

Abstract

In a magnetic plasma confinment device having an inner toroidal limiter mounted on an inner wall of a plasma containment vessel, an arrangement is provided for monitoring vertical temperature profiles of the limiter. The temperature profiles are taken at brief time intervals, in a time scan fashion. The time scans of the vertical temperature profile are continuously monitored to detect the presence of a peaked temperature excursion, which, according to the present invention, is a precursor of a subsequent major plasma disruption. A fast scan of the temperature profile is made so as to provide a time interval in real time prior to the major plasma disruption, such that corrective action can be taken to reduce the harmful effects of the plasma disruption.

Inventors:
 [1];  [2]
  1. Somerset, NJ
  2. E. Windsor, NJ
Issue Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
OSTI Identifier:
866183
Patent Number(s):
4650632
Assignee:
United States of America as represented by United States (Washington, DC)
Patent Classifications (CPCs):
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
G - PHYSICS G21 - NUCLEAR PHYSICS G21B - FUSION REACTORS
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
tokamak; plasma; current; disruption; infrared; control; magnetic; confinment; device; inner; toroidal; limiter; mounted; wall; containment; vessel; arrangement; provided; monitoring; vertical; temperature; profiles; brief; time; intervals; scan; fashion; scans; profile; continuously; monitored; detect; presence; peaked; excursion; according; precursor; subsequent; major; fast; provide; interval; prior; corrective; action; reduce; harmful; effects; time prior; temperature profiles; plasma current; temperature profile; inner wall; containment vessel; time interval; plasma containment; time intervals; tokamak plasma; temperature excursion; vertical temperature; harmful effects; continuously monitored; continuously monitor; magnetic plasma; limiter mounted; /376/

Citation Formats

Kugel, Henry W, and Ulrickson, Michael. Tokamak plasma current disruption infrared control system. United States: N. p., 1987. Web.
Kugel, Henry W, & Ulrickson, Michael. Tokamak plasma current disruption infrared control system. United States.
Kugel, Henry W, and Ulrickson, Michael. Thu . "Tokamak plasma current disruption infrared control system". United States. https://www.osti.gov/servlets/purl/866183.
@article{osti_866183,
title = {Tokamak plasma current disruption infrared control system},
author = {Kugel, Henry W and Ulrickson, Michael},
abstractNote = {In a magnetic plasma confinment device having an inner toroidal limiter mounted on an inner wall of a plasma containment vessel, an arrangement is provided for monitoring vertical temperature profiles of the limiter. The temperature profiles are taken at brief time intervals, in a time scan fashion. The time scans of the vertical temperature profile are continuously monitored to detect the presence of a peaked temperature excursion, which, according to the present invention, is a precursor of a subsequent major plasma disruption. A fast scan of the temperature profile is made so as to provide a time interval in real time prior to the major plasma disruption, such that corrective action can be taken to reduce the harmful effects of the plasma disruption.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1987},
month = {1}
}

Patent:

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