Tritium Waste Control Project progress report: April--June 1976. [LIS; electrolysis; monitor; shipping container; catalytic exchange]

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Tritiated Liquid Waste Decontamination (Molecular Excitation): A preliminary economic study of water detritiation by laser isotope separation indicates possible advantages over the catalytic exchange process. The electric power requirements are a factor of 5 lower, resulting in a 50-percent reduction in operating costs. Capital costs for the two methods appear comparable. Additional attempts were made to determine the ir spectrum of HTO around the ..nu../sub 1/ band. However, carbon dioxide impurity obscured the HTO absorption around 2265 cm/sup -1/ making it impossible to obtain a high quality spectrum for use in the LIS experiments. Electrolysis of High Level Tritiated Water: … continued below

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27 pages

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Bixel, J. C. & Kershner, C. J. December 10, 1976.

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Tritiated Liquid Waste Decontamination (Molecular Excitation): A preliminary economic study of water detritiation by laser isotope separation indicates possible advantages over the catalytic exchange process. The electric power requirements are a factor of 5 lower, resulting in a 50-percent reduction in operating costs. Capital costs for the two methods appear comparable. Additional attempts were made to determine the ir spectrum of HTO around the ..nu../sub 1/ band. However, carbon dioxide impurity obscured the HTO absorption around 2265 cm/sup -1/ making it impossible to obtain a high quality spectrum for use in the LIS experiments. Electrolysis of High Level Tritiated Water: In an experiment using a regenerative cell on water containing approximately 0.3 g tritium, about 21 ml of water was electrolyzed but the solid polymer electrolyte ruptured and cell components were damaged beyond repair. Tritium Monitor Development and Calibration: The calibration system design was modified to allow procurement and fabrication of the major components during FY-1976. Shipping Container Development for Tritiated Liquid Waste: The bourdon tube pressure gage was replaced with a pressure transducer for double containment. A calorimeter was completed for tritium assay of contents. Catalytic Exchange Detritiation Studies: The Englehard hydrophobic, catalyst for HT/H/sub 2/O exchange is being tested. An experiment to establish the height of one equilibrium plate was completed. (DLC)

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27 pages

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  • December 10, 1976

Added to The UNT Digital Library

  • Feb. 10, 2019, 8:45 p.m.

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  • Jan. 25, 2021, 3:34 p.m.

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Bixel, J. C. & Kershner, C. J. Tritium Waste Control Project progress report: April--June 1976. [LIS; electrolysis; monitor; shipping container; catalytic exchange], report, December 10, 1976; United States. (https://digital.library.unt.edu/ark:/67531/metadc1448379/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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