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

Technical Report · Fri Dec 10 04:00:00 EST 1976

DOI:https://doi.org/10.2172/7237901· OSTI ID:7237901

Bixel, J. C.; Kershner, C. J.

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)

• Research Organization: Mound Lab., Miamisburg, OH (USA)
• DOE Contract Number: EY-76-C-04-0053
• OSTI ID: 7237901
• Report Number(s): MLM-2382
• Country of Publication: United States
• Language: English

Related Subjects

052000* -- Nuclear Fuels-- Waste Management
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CALORIMETERS
CATALYSIS
CATALYSTS
CHEMICAL REACTION KINETICS
CHEMICAL REACTIONS
CLEANING
COMPARATIVE EVALUATIONS
CONTAINERS
COST
DECOMPOSITION
DECONTAMINATION
DIRECT ENERGY CONVERTERS
DISSOCIATION
ECONOMICS
ELECTROCHEMICAL CELLS
ELECTROLYSIS
FUEL CELLS
FUEL REPROCESSING PLANTS
GASEOUS WASTES
HYDROGEN ISOTOPES
INFRARED SPECTRA
ISOTOPE SEPARATION
ISOTOPES
ISOTOPIC EXCHANGE
KINETICS
LABELLED COMPOUNDS
LASER ISOTOPE SEPARATION
LIGHT NUCLEI
LYSIS
MANAGEMENT
MEASURING INSTRUMENTS
NUCLEAR FACILITIES
NUCLEI
ODD-EVEN NUCLEI
PHOTOCHEMICAL REACTIONS
PHOTOLYSIS
PROCESSING
RADIATION MONITORS
RADIOACTIVE EFFLUENTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RADIOISOTOPES
REACTION KINETICS
RECOVERY
REGENERATIVE FUEL CELLS
SEPARATION PROCESSES
SPECTRA
TESTING
TRANSPORT
TRITIUM
TRITIUM COMPOUNDS
TRITIUM RECOVERY
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
YEARS LIVING RADIOISOTOPES