Tritium waste control: April--September 1977

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A pilot scale system was used in an initial experiment to investigate the combined-electrolysis-catalytic-exchange process (CECE) for the detritiation of water. Data taken during the experiment indicate the process does indeed strip tritium from gaseous hydrogen at the top and concentrate it in water at the bottom of the catalyst-filled column. A high activity tritiated water electrolysis system was designed and built using a solid polymer electrolyte (SPE) cell. The system was successfully operated at currents up to 50 A using deionized tap water. Triplicate samples of cement, cement-plaster (1:1 ratio by weight), and cement-plaster (1:1 ratio by volume) were ... continued below

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Pages: 44

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Creator: Unknown. January 9, 1978.

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Description

A pilot scale system was used in an initial experiment to investigate the combined-electrolysis-catalytic-exchange process (CECE) for the detritiation of water. Data taken during the experiment indicate the process does indeed strip tritium from gaseous hydrogen at the top and concentrate it in water at the bottom of the catalyst-filled column. A high activity tritiated water electrolysis system was designed and built using a solid polymer electrolyte (SPE) cell. The system was successfully operated at currents up to 50 A using deionized tap water. Triplicate samples of cement, cement-plaster (1:1 ratio by weight), and cement-plaster (1:1 ratio by volume) were injected with 386 Ci of tritium. Preliminary results indicate Type III Portland cement retains the tritium slightly better than the cement-plaster mixtures. The tritium release study of actual waste burial packages is continuing. The fractional release is 1 x 10/sup -5/ on a 4-y old package, only 4 x 10/sup -7/ on 3-y old packages, and 1 x 10/sup -9/ on a 1-y old package. Pressure increase and gas composition determinations were repeated for octane (activity = 1000 Ci/liter) with and without tritium fixation using argon as the initial overgas. Pressure buildup measurements for octane without fixation were repeated a third time using hydrogen gas. The rate of pressure increase did not change significantly from previously determined values. Four elemental tritium samples were released into a laboratory to determine the efficiency of the Emergency Containment System. The ventilation system was modified during the fourth experiment to minimize leakage.

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Pages: 44

Notes

Dep. NTIS, PC A03/MF A01.

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  • Report No.: MLM-2484
  • Grant Number: EY-76-C-04-0053
  • DOI: 10.2172/5162109 | External Link
  • Office of Scientific & Technical Information Report Number: 5162109
  • Archival Resource Key: ark:/67531/metadc1052693

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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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Creation Date

  • January 9, 1978

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

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  • Jan. 24, 2018, 1:40 p.m.

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Tritium waste control: April--September 1977, report, January 9, 1978; United States. (digital.library.unt.edu/ark:/67531/metadc1052693/: accessed October 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.