Tritium waste control project progress report, October--December 1975. [Tritiated waste decontamination by molecular excitation; catalytic exchange detritiation studies; development of shipping containers for tritiated liquid waste]

Technical Report · Fri Jul 30 04:00:00 EDT 1976

DOI:https://doi.org/10.2172/7268048· OSTI ID:7268048

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

In the tritiated liquid waste decontamination by molecular excitation studies, further calculations were performed on the hydrogen atom-water exchange reactions. Assembly and testing of the cell to be used for the measurement of the HTO IR spectrum were completed. As a result of findings from trial loadings using HD as a surrogate for HT in the oxidation system, it is believed that larger quantities of HTO will be required to obtain the desired ir spectrum. This appears to be a result of a significant adsorption of the water on the inner surface of the spectrometer cell. In the catalytic exchange detritiation studies, leak checking and cold operational testing of the experimental apparatus were completed. Modifications were made to improve the operability and reliability of the system as originally designed by Engelhard Minerals and Chemicals Corp. A computer program was prepared for the calculation of twelve hydrogen isotopic compounds in thermodynamic equilibrium. This program based on the free energy minimization technique produced data on the equilibrium concentrations of tritium compounds from reactants with various T/D/H/O ratios (e.g., T/H = approximately 10/sup -8/ to approximately 10/sup -2/) at temperatures ranging from 300 to 800/sup 0/K. The bourdon tube pressure gage on the prototype shipping container has been replaced with a 316 stainless steel pressure transducer to decrease the mechanical vulnerability of the package. Procedures have been established for usage and safety testing the primary container and a safety analysis review for the complete assembly in the AL-Ml outer shipping container has been initiated.

• Research Organization: Mound Lab., Miamisburg, Ohio (USA)
• DOE Contract Number: E(33-1)-GEN-53
• OSTI ID: 7268048
• Report Number(s): MLM-2337
• Country of Publication: United States
• Language: English

Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CLEANING
CONTAINERS
DECONTAMINATION
HYDROGEN ISOTOPES
INFRARED SPECTRA
ISOTOPES
LABELLED COMPOUNDS
LIGHT NUCLEI
LIQUID WASTES
MANAGEMENT
NUCLEI
ODD-EVEN NUCLEI
PROCESSING
RADIOACTIVE WASTE PROCESSING
RADIOISOTOPES
RESEARCH PROGRAMS
SEPARATION PROCESSES
SPECTRA
TRANSPORT
TRITIUM
TRITIUM COMPOUNDS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
YEARS LIVING RADIOISOTOPES