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Title: Description of the prototype diagnostic residual gas analyzer for ITER

The diagnostic residual gas analyzer (DRGA) system to be used during ITER tokamak operation is being designed at Oak Ridge National Laboratory to measure fuel ratios (deuterium and tritium), fusion ash (helium), and impurities in the plasma. The eventual purpose of this instrument is for machine protection, basic control, and physics on ITER. Prototyping is ongoing to optimize the hardware setup and measurement capabilities. The DRGA prototype is comprised of a vacuum system and measurement technologies that will overlap to meet ITER measurement requirements. Three technologies included in this diagnostic are a quadrupole mass spectrometer, an ion trap mass spectrometer, and an optical penning gauge that are designed to document relative and absolute gas concentrations.
Authors:
 [1] ;  [2] ; ; ;  [1]
  1. Fusion and Materials for Nuclear Systems Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6169 (United States)
  2. (United States)
Publication Date:
OSTI Identifier:
22308663
Resource Type:
Journal Article
Resource Relation:
Journal Name: Review of Scientific Instruments; Journal Volume: 85; Journal Issue: 11; Other Information: (c) 2014 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CONCENTRATION RATIO; DEUTERIUM; GAS ANALYSIS; HELIUM; ITER TOKAMAK; MASS SPECTROMETERS; ORNL; PLASMA IMPURITIES; RESIDUES; THERMONUCLEAR FUELS; THERMONUCLEAR REACTIONS; TRITIUM; VACUUM SYSTEMS