Waste management. Savannah River Laboratory quarterly report, October--December 1974

Technical Report · Tue Jan 01 04:00:00 EST 1974

OSTI ID:7146769

The Technical Data Summary describing a prospective process for monolithic waste solidification and retrievable surface storage was prepared as a reference case for design and cost studies. Process development and demonstrations are continuing with actual plant waste at small scale, and with simulated waste at full scale. Tests demonstrated /sup 137/Cs removal from supernates from four plant waste tanks by the two-column ion exchange process. Stored high activity waste sludges from three plant tanks were processed into washed powders in the laboratory and incorporated into 108 concrete test castings. The concentration of powdered sludge was shown to be the dominant factor affecting the compressive strength of concrete waste forms. Evaluations indicate that ''Cor-Ten A'' and Type 304 stainless steel are promising container materials for solid waste forms. Prospective materials for retrievable waste-form containers were tested for compatibility with waste-containing glasses and concretes. Semiwork tests indicate the feasibility of wiped-film evaporators for plant concentration of wastes, and design is proceeding for full-scale evaporators for tank-top operation. Neutron thermalization was shown to be a promising technique for online monitoring of residual water in salt cake from plant evaporators. Tests demonstrated that neither an ultrasonic nor a thermal flowmeter could detect early salt pluggage in the waste concentrate transfer system. Measurements of onset of ductile crack extension for A285-B mild steel alloy, used in construction of the Type I and Type II waste storage tanks in the plant, indicate that a crack located in high stress regions of the tanks (knuckle weld zone) would have to be at least 16 inches long to undergo ductile extension at 85 percent of yield stress. Agreement is close between the measured onset stresses for extension and theoretically predicted values.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, S.C. (USA). Savannah River Lab.
• DOE Contract Number: E(07-2)-1
• OSTI ID: 7146769
• Report Number(s): DPST-74-125-4
• Country of Publication: United States
• Language: English

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12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALKALI METAL ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CESIUM 137
CESIUM ISOTOPES
CONCRETES
CONTAINERS
GLASS
ION EXCHANGE
ISOTOPES
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEI
ODD-EVEN NUCLEI
PHASE TRANSFORMATIONS
PROCESSING
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
RADIOISOTOPES
RESEARCH PROGRAMS
SAVANNAH RIVER PLANT
SLUDGES
SOLIDIFICATION
STORAGE
US AEC
US ERDA
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE PROCESSING
WASTE STORAGE
YEARS LIVING RADIOISOTOPES