Tritium waste control: October 1980-March 1981. [Catalytic exchange detritiation; fixation of aqueous tritiated wastes in polymer impregnated concrete]
The Combined Electrolysis Catalytic Exchange (CECE) pilot system was operated for 88 days and processed over 500 liters of tritiated water. Two complete electrolysis systems, each using a General Electric Company solid polymer electrolyte (SPE) cell, have been built. One of these is being used for the 10 Ci/ml tritiated water test and the other as a control with nontritiated water. The first SPE failed after seven weeks of exposure to the 10 Ci/ml water. A new SPE was installed and has been operated for eight weeks without failure at 10 Ci/ml. Analyses for 10 types of impurities were made on each of 15 Effluent Recovery System (ERS) liquid waste samples. A pilot-scale system for removal of these impurities has been designed and is being built. Gas generation rates caused by radiolysis of tritium waste materials were determined for polymer and nonpolymer impregenated tritiated concrete, and fixated and nonfixated tritiated waste vacuum pump oil. The construction of the new addition to the liquid waste handling facility was completed. The inert-atmosphere gloveboxes and other equipment are being installed for the polystyrene impregnated, tritiated-concrete wastewater process. The study of tritium release from representative burial packages was continued. The two wastewater drums which have the highest tritium release (29.8 mCi and 98.2 mCi) also contain the highest amounts of tritium, originally 34,480 Ci and 52,128 Ci, respectively. The tritium release from the polymer-impregnated, tritiated concrete (PITC) and the control (non-PITC) remain too low to be illustrated on the current figures.
- Research Organization:
- Monsanto Research Corp., Miamisburg, OH (USA)
- DOE Contract Number:
- AC04-76DP00053
- OSTI ID:
- 5913507
- Report Number(s):
- MLM-2844; ON: DE82002088; TRN: 82-000327
- Country of Publication:
- United States
- Language:
- English
Similar Records
Tritium control: April-September 1983
Trittium waste control: April-September 1979
Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTE PROCESSING
RESEARCH PROGRAMS
SOLIDIFICATION
TRITIUM
CATALYSIS
CONCRETES
DEGASSING
ELECTROLYSIS
POLYSTYRENE
RADIOLYSIS
TRITIUM COMPOUNDS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
DECOMPOSITION
HYDROGEN ISOTOPES
ISOTOPES
LABELLED COMPOUNDS
LIGHT NUCLEI
LYSIS
MANAGEMENT
MATERIALS
NUCLEI
ODD-EVEN NUCLEI
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
PHASE TRANSFORMATIONS
PLASTICS
POLYMERS
POLYOLEFINS
POLYVINYLS
PROCESSING
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOISOTOPES
SYNTHETIC MATERIALS
WASTE MANAGEMENT
WASTE PROCESSING
YEARS LIVING RADIOISOTOPES
060700* - Fusion Fuels- Waste Management- (1980-1987)
052001 - Nuclear Fuels- Waste Processing