Tritium Removal by Laser Heating and Its Application to Tokamaks

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Description

A novel laser heating technique has recently been applied to removing tritium from carbon tiles that had been exposed to deuterium-tritium (DT) plasmas in the Tokamak Test Fusion Reactor (TFTR). A continuous wave neodymium laser, of power up to 300 watts, was used to heat the surface of the tiles. The beam was focused to an intensity, typically 8 kW/cm{sup 2}, and rapidly scanned over the tile surface by galvanometer-driven scanning mirrors. Under the laser irradiation, the surface temperature increased dramatically, and temperatures up to 2,300 degrees C were recorded by an optical pyrometer. Tritium was released and circulated in ... continued below

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248 Kilobytes pages

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Skinner, C.H.; Gentile, C.A.; Guttadora, G.; Carpe, A.; Langish, S.; Young, K.M. et al. November 16, 2001.

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Description

A novel laser heating technique has recently been applied to removing tritium from carbon tiles that had been exposed to deuterium-tritium (DT) plasmas in the Tokamak Test Fusion Reactor (TFTR). A continuous wave neodymium laser, of power up to 300 watts, was used to heat the surface of the tiles. The beam was focused to an intensity, typically 8 kW/cm{sup 2}, and rapidly scanned over the tile surface by galvanometer-driven scanning mirrors. Under the laser irradiation, the surface temperature increased dramatically, and temperatures up to 2,300 degrees C were recorded by an optical pyrometer. Tritium was released and circulated in a closed-loop system to an ionization chamber that measured the tritium concentration. Most of the tritium (up to 84%) could be released by the laser scan. This technique appears promising for tritium removal in a next-step DT device as it avoids oxidation, the associated deconditioning of the plasma facing surfaces, and the expense of processing large quantities of tritium oxide. Some engineering aspects of the implementation of this method in a next-step fusion device will be discussed.

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248 Kilobytes pages

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INIS; OSTI as DE00792841

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  • Other Information: PBD: 16 Nov 2001

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  • Report No.: PPPL-3630
  • Grant Number: AC02-76CH03073
  • DOI: 10.2172/792841 | External Link
  • Office of Scientific & Technical Information Report Number: 792841
  • Archival Resource Key: ark:/67531/metadc742173

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Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • November 16, 2001

Added to The UNT Digital Library

  • Oct. 19, 2015, 7:39 p.m.

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  • April 18, 2016, 1:10 p.m.

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Skinner, C.H.; Gentile, C.A.; Guttadora, G.; Carpe, A.; Langish, S.; Young, K.M. et al. Tritium Removal by Laser Heating and Its Application to Tokamaks, report, November 16, 2001; Princeton, New Jersey. (digital.library.unt.edu/ark:/67531/metadc742173/: accessed December 11, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.