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Divertor IR thermography on Alcator C-Mod.

J L Terry1, B LaBombard, D Brunner

  • 1Plasma Science and Fusion Center, MIT, Cambridge, Massachusetts 02139, USA. terry@psfc.mit.edu

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|November 2, 2010
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Summary

Infrared thermography on Alcator C-Mod tokamak measures divertor heat flux. Modifications and in situ calibration enabled accurate measurements despite challenging conditions similar to ITER.

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Area of Science:

  • Plasma physics
  • Fusion energy research
  • Thermometry

Background:

  • Alcator C-Mod presents thermography challenges mirroring ITER, including low-emissivity surfaces and complex geometry.
  • Accurate measurement of divertor heat flux is crucial for fusion reactor design and operation.

Purpose of the Study:

  • To develop and validate an infrared (IR) thermography system for measuring incident divertor heat flux in the Alcator C-Mod tokamak.
  • To address challenges posed by low-emissivity surfaces, surface films, and geometric complexities.

Main Methods:

  • Modified a 6° toroidal sector of the C-Mod divertor with a 2° toroidal ramp to avoid shadowing.
  • Employed a toroidally displaced IR camera, thermocouples, and calorimeters for surface temperature and heat flux measurements.
  • Performed in situ calibration of the IR camera sensitivity using embedded thermocouples to account for emissivity variations.

Main Results:

  • Successfully obtained time histories of surface temperatures.
  • Computed incident heat flux profiles using the calibrated thermography data.
  • Demonstrated a method to correct for emissivity changes caused by surface coatings.

Conclusions:

  • The implemented IR thermography system provides accurate measurements of divertor heat flux in challenging tokamak environments.
  • The modifications and calibration techniques developed are applicable to future fusion devices like ITER.
  • This work advances the capability for in-situ heat flux measurement in fusion research.