Plasma wall interaction and tritium retention in TFTR

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The Tokamak Fusion Test Reactor (TFTR) has been operating safely and routinely with deuterium-tritium fuel for more than two years. In this time, TFTR has produced an impressive number of record breaking results including core fusion power, {approximately} 2 MW/m{sup 3}, comparable to that expected for ITER. Advances in wall conditioning via lithium pellet injection have played an essential role in achieving these results. Deuterium-tritium operation has also provided a special opportunity to address the issues of tritium recycling and retention. Tritium retention over two years of operation was approximately 40%. Recently, the in-torus tritium inventory was reduced by half ... continued below

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28 p.

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Skinner, C.H.; Amarescu, E. & Ascione, G. August 1, 1996.

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Description

The Tokamak Fusion Test Reactor (TFTR) has been operating safely and routinely with deuterium-tritium fuel for more than two years. In this time, TFTR has produced an impressive number of record breaking results including core fusion power, {approximately} 2 MW/m{sup 3}, comparable to that expected for ITER. Advances in wall conditioning via lithium pellet injection have played an essential role in achieving these results. Deuterium-tritium operation has also provided a special opportunity to address the issues of tritium recycling and retention. Tritium retention over two years of operation was approximately 40%. Recently, the in-torus tritium inventory was reduced by half through a combination of glow discharge cleaning, moist-air soaks, and plasma discharge cleaning. The tritium inventory is not a constraint in continued operations. The authors present recent results from TFTR in the context of plasma wall interactions and deuterium-tritium issues.

Physical Description

28 p.

Notes

INIS; OSTI as DE96012020

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  • 12. international conference on plasma surface interactions in controlled fusion devices, Saint-Raphael (France), 20-26 May 1996

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  • Other: DE96012020
  • Report No.: PPPL--3189
  • Report No.: CONF-960569--7
  • Grant Number: AC02-76CH03073
  • Office of Scientific & Technical Information Report Number: 270817
  • Archival Resource Key: ark:/67531/metadc664933

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Office of Scientific & Technical Information Technical Reports

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

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  • August 1, 1996

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  • June 29, 2015, 9:42 p.m.

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  • April 15, 2016, 6:49 p.m.

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Skinner, C.H.; Amarescu, E. & Ascione, G. Plasma wall interaction and tritium retention in TFTR, article, August 1, 1996; Princeton, New Jersey. (digital.library.unt.edu/ark:/67531/metadc664933/: accessed December 15, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.