Experimental procedure for examining the kinetics of tritium gas conversion to tritiated water

Technical Report · Mon Feb 01 04:00:00 EST 1982

DOI:https://doi.org/10.2172/5657897· OSTI ID:5657897

Phillips, J. E.; Easterly, C. E.

Research equipment has been designed, fabricated, and evaluated for determining the conversion rate of tritium gas to tritiated water for initial tritium gas concentrations ranging from the maximum permissible concentration of tritium gas for occupational exposures of 7.4 x 10/sup -5/ TBq/m/sup 3/ to 3.7 x 10/sup 2/ TBq/m/sup 3/. The equipment includes a vacuum system coupled to a gas handling system for preparing up to 15 reaction vessels having identical tritium gas concentrations. Measured concentrations in 4 or 5 prepared flasks were within 1.6% of their mean. Measured concentrations in all 5 flasks were within 8% of the mean. Good control of the tritium concentration was also achieved. A system was required for sampling tritiated water and tritium gas. Efficient collection of HTO was desired and reproducible collection of HTO and HT were essential. Collection efficiencies for tritiated water of at least 99% were obtained reproducibly. Collection efficiencies of tritium gas were also 99% or greater and reproducible.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5657897
• Report Number(s): ORNL/TM-7670; ON: DE82006814
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
420203* -- Engineering-- Handling Equipment & Procedures
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHEMICAL REACTIONS
DESIGN
EQUIPMENT
HIGH VACUUM
HYDROGEN ISOTOPES
ISOTOPES
LABELLED COMPOUNDS
LABORATORY EQUIPMENT
LIGHT NUCLEI
MATERIALS HANDLING EQUIPMENT
NUCLEI
ODD-EVEN NUCLEI
OPERATION
OXIDATION
RADIATION PROTECTION
RADIOISOTOPES
SAMPLING
TRITIUM
TRITIUM COMPOUNDS
VACUUM SYSTEMS
YEARS LIVING RADIOISOTOPES