Tritium waste control: April-September 1981
Progress reports are presented for the following: electrolysis of tritiated water; impurity removal from combined Electrolysis Catalytic Exchange (CECE) feed water; gas generation measurements on tritiated waste materials; fixation of aqueous tritiated waste in polymer-impregnated concrete; management of high specific activity tritiated liquid wastes; and tritium assay of low specific activity (LSA) laboratory and LSA shoe cover waste. Some of the highlights are as follows: (1) gas generation rates caused by radiolysis of tritium waste materials were determined for polymer and nonpolymer-impregnated, tritiated concrete and fixated and nonfixated, tritiated waste vacuum pump oil; (2) the drum study monitoring the release of tritium from actual burial packages showed that the maximum fractional release rate for the three types of high activity, tritiated liquid waste generated is 1.25 x 10/sup -5/, and the maximum total permeation is 122 mCi after 5.5 y. These two values represent a 9 to 20% increase for the past six months. Tritium release from the polymer-impregnated, tritiated concrete (PITC) and the control (non-PITC) remains very low. Two assays were performed on low specific activity, tritium-contaminated waste generated at Mound. In one, four LSA drums were assayed for total tritium content by leaching the contents with water. The tritium content of all four drums was well within the LSA limit of less than 25 Ci per drum. In the second study a drum of discarded shoe covers from tritium-handling areas was filled with a measureed quantity of water for leaching tritium from the shoe covers. The minimum amount of tritium within the drum was determined. An annual average estimate of tritium removed and buried as LSA shoe cover trash was also made.
- Research Organization:
- Mound Facility, Miamisburg, OH (USA)
- DOE Contract Number:
- AC04-76DP00053
- OSTI ID:
- 5363007
- Report Number(s):
- MLM-2903; ON: DE82016040
- Country of Publication:
- United States
- Language:
- English
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Tritium waste control: April-September 1982
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CATALYSIS
CHALCOGENIDES
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CONCRETES
DATA
DECOMPOSITION
DISSOLUTION
ELECTROLYSIS
EXPERIMENTAL DATA
HYDROGEN ISOTOPES
IMPURITIES
INFORMATION
ISOTOPES
LABELLED COMPOUNDS
LEACHING
LIGHT NUCLEI
LYSIS
MANAGEMENT
MATERIALS
NUCLEI
NUMERICAL DATA
ODD-EVEN NUCLEI
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXIDES
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
PHASE TRANSFORMATIONS
PLASTICS
POLYMERS
POLYOLEFINS
POLYSTYRENE
POLYVINYLS
PROCESSING
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOACTIVE WASTE PROCESSING
RADIOISOTOPES
RADIOLYSIS
REMOVAL
RESEARCH PROGRAMS
SEPARATION PROCESSES
SOLIDIFICATION
SYNTHETIC MATERIALS
TRITIUM
TRITIUM COMPOUNDS
TRITIUM OXIDES
WASTE MANAGEMENT
WASTE PROCESSING
YEARS LIVING RADIOISOTOPES