Tritium retention in jet cryopanel samples

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The possibility that tritium might exchange with water trapped in aluminum anodize cryopanels in JET prompted a test program at the Tritium Systems Test Assembly, TSTA, Los Alamos, New Mexico. JET furnished two test pieces of cryopanel which were exposed to tritium at approximately liquid nitrogen temperature and 25 torr pressure for nearly two weeks. One specimen was removed and the retained tritium was measured. The second specimen was subjected to several increasing temperature vacuum bakeouts and the effectiveness of the bakeouts were inferred from the pressure history of the chamber. When the retained tritium in the second specimen was ... continued below

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Pages: (7 p)

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Walthers, C.R.; Jenkins, E.M. (Los Alamos National Lab., NM (United States)); Mayaux, C. & Obert, W. (JET Joint Undertaking, Oxfordshire, England (GB)) January 1, 1991.

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The possibility that tritium might exchange with water trapped in aluminum anodize cryopanels in JET prompted a test program at the Tritium Systems Test Assembly, TSTA, Los Alamos, New Mexico. JET furnished two test pieces of cryopanel which were exposed to tritium at approximately liquid nitrogen temperature and 25 torr pressure for nearly two weeks. One specimen was removed and the retained tritium was measured. The second specimen was subjected to several increasing temperature vacuum bakeouts and the effectiveness of the bakeouts were inferred from the pressure history of the chamber. When the retained tritium in the second specimen was measured it was found that nearly 95% of the tritium, as measured in the first specimen, had been removed during the vacuum bakeouts. If the tritium retained in the cryopanel without bakeout were scaled to JET conditions according to a linear pressure time relationship, the tritium expected to become trapped in the JET cryopanels would be approximately 0.6 gram. Testing is currently underway at TSTA which will determine the tritium retention to be expected under more realistic JET operating conditions and which will assess the effectiveness of various bake or purge schemes in removing the trapped tritium. 2 refs., 2 figs.

Physical Description

Pages: (7 p)

Notes

OSTI; NTIS; INIS; GPO Dep.

Source

  • 4. topical meeting on tritium technology in fission, fusion, and isotopic applications, Albuquerque, NM (United States), 30 Sep - 4 Oct 1991

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  • Other: DE92000205
  • Report No.: LA-UR-91-3017
  • Report No.: CONF-910920--4
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5182845
  • Archival Resource Key: ark:/67531/metadc1059800

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Office of Scientific & Technical Information Technical Reports

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  • January 1, 1991

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  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 7:06 p.m.

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Walthers, C.R.; Jenkins, E.M. (Los Alamos National Lab., NM (United States)); Mayaux, C. & Obert, W. (JET Joint Undertaking, Oxfordshire, England (GB)). Tritium retention in jet cryopanel samples, article, January 1, 1991; New Mexico. (digital.library.unt.edu/ark:/67531/metadc1059800/: accessed December 14, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.