Long Term Retention of Deuterium and Tritium in Alcator C-Mod

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We estimate the total in-vessel deuterium retention in Alcator C-Mod from a run campaign of about 1090 plasmas. The estimate is based on measurements of deuterium retained on 22 molybdenum tiles from the inner wall and divertor. The areal density of deuterium on the tiles was measured by nuclear reaction analysis. From these data, the in-vessel deuterium inventory is estimated to be about 0.1 gram, assuming the deuterium coverage is toroidally symmetric. Most of the retained deuterium is on the walls of the main plasma chamber, only about 2.5% of the deuterium is in the divertor. The D coverage is ... continued below

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4 p.

Creation Information

FIORE,C.; LABOMBARD,B.; LIPSCHULTZ,B.; PITCHER,C.S.; SKINNER,C.H. & WAMPLER,WILLIAM R. November 3, 1999.

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  • Sandia National Laboratories
    Publisher Info: Sandia National Labs., Albuquerque, NM, and Livermore, CA (United States)
    Place of Publication: Albuquerque, New Mexico

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Description

We estimate the total in-vessel deuterium retention in Alcator C-Mod from a run campaign of about 1090 plasmas. The estimate is based on measurements of deuterium retained on 22 molybdenum tiles from the inner wall and divertor. The areal density of deuterium on the tiles was measured by nuclear reaction analysis. From these data, the in-vessel deuterium inventory is estimated to be about 0.1 gram, assuming the deuterium coverage is toroidally symmetric. Most of the retained deuterium is on the walls of the main plasma chamber, only about 2.5% of the deuterium is in the divertor. The D coverage is consistent with a layer saturated by implantation with ions and charge-exchange neutrals from the plasma. This contrasts with tokamaks with carbon plasma-facing components (PFC's) where long-term retention of tritium and deuterium is large and mainly in the divertor due to codeposition with carbon eroded by the plasma. The low deuterium retention in the C-Mod divertor is mainly due to the absence of carbon PFC's in C-Mod and the low erosion rate of Mo.

Physical Description

4 p.

Notes

INIS; OSTI as DE00015016

Medium: P; Size: 4 pages

Source

  • 18th Symposium on Fusion Engineering, Albuquerque, NM (US), 10/25/1999--10/30/1999

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  • Report No.: SAND99-2869C
  • Grant Number: AC04-94AL85000
  • Office of Scientific & Technical Information Report Number: 15016
  • Archival Resource Key: ark:/67531/metadc626269

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  • November 3, 1999

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  • June 16, 2015, 7:43 a.m.

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  • April 10, 2017, 8:14 p.m.

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FIORE,C.; LABOMBARD,B.; LIPSCHULTZ,B.; PITCHER,C.S.; SKINNER,C.H. & WAMPLER,WILLIAM R. Long Term Retention of Deuterium and Tritium in Alcator C-Mod, article, November 3, 1999; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc626269/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.