Stripper system performance in the replacement tritium facility

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Description

The Replacement Tritium Facility (RTF) at the Savannah River Site in the United States was designed and built to handle kilogram levels of tritium. The RTF was started up in January 1994. All the design objectives were achieved. To minimize tritium release to the environment, the tritium handling process is installed inside nitrogen-atmosphere gloveboxes. Any tritium that might leak from the process to the gloveboxes is recovered by stripper systems. The tritium concentration in the gloveboxes is normally maintained at below 0.1 Ci/m{sup 3}. During a large tritium leak from the process to the glovebox, the stripper system lowered the ... continued below

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12 p.

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Heung, L.K. January 1, 1995.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 49 times . More information about this article can be viewed below.

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Description

The Replacement Tritium Facility (RTF) at the Savannah River Site in the United States was designed and built to handle kilogram levels of tritium. The RTF was started up in January 1994. All the design objectives were achieved. To minimize tritium release to the environment, the tritium handling process is installed inside nitrogen-atmosphere gloveboxes. Any tritium that might leak from the process to the gloveboxes is recovered by stripper systems. The tritium concentration in the gloveboxes is normally maintained at below 0.1 Ci/m{sup 3}. During a large tritium leak from the process to the glovebox, the stripper system lowered the tritium concentration in the glovebox from about 8,000 Ci/m{sup 3} to about 100 Ci/m{sup 3} in one hour. After that the tritium concentration decreased very slowly. It required 5 days of stripping before the concentration was down to about 10 Ci/m{sup 3}.

Physical Description

12 p.

Notes

INIS; OSTI as DE95010974

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  • 5. topical meeting on tritium technology in fission, fusion and isotopic applications, Ispra (Italy), 28 May - 3 Jun 1995

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  • Other: DE95010974
  • Report No.: WSRC-MS--94-0470
  • Report No.: CONF-950506--10
  • Grant Number: AC09-89SR18035
  • Office of Scientific & Technical Information Report Number: 53668
  • Archival Resource Key: ark:/67531/metadc693300

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • January 1, 1995

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  • Aug. 14, 2015, 8:43 a.m.

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  • Feb. 9, 2016, 7:06 p.m.

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Heung, L.K. Stripper system performance in the replacement tritium facility, article, January 1, 1995; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc693300/: accessed October 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.