Waste management. Savannah River Laboratory quarterly report, January--March 1975
Glass waste forms were prepared from powdered sludge from high activity waste. Techniques were developed for investigation of the bonding mechanism in concrete waste forms. An improved method was developed for leach testing solid waste forms. Tests determined the effect of feed composition on ion exchange removal of cesium. Laboratory tests indicated that /sup 90/Sr, /sup 238/Pu, /sup 106/Ru (for a few years) and NO/sub 2//sup -/ plus NO/sub 3//sup -/ will be the principal hazardous components in salt solution after removal of /sup 137/Cs. Feasibility was demonstrated of zeolite sorption of cesium from supernate, but the process would increase solids to be stored significantly. Solubility of Pu in simulated waste was studied to determine whether nuclides other than /sup 137/Cs must be removed from plant waste supernate to decontaminate the salt. Thermochemical characterization of the three simulated sludges was completed. Simple water washing was indicated by laboratory tests to classify soil from burial-ground plutonium waste trenches, which average approximately 20 nCi/gram, into two distinct fractions: (1) clay-silt (approximately 60 nCi/gram) that comprises only 1/3 of the total soil that could otherwise require storage in durable containers for eventual transport to a national repository, and (2) sand (approximately 1 nCi/gram), 2/3 of the total soil, that could be returned to the burial trenches. Test data permit estimation of the rate of radiolytic formation of gas from cellulosic containers are sorbent materials contaminated with any radionuclide. Natural vibrational characteristics of a Type III tank were analyzed to determine safe operating frequencies for proposed wiped-film evaporators. Tests indicate that high activity waste in tanks could be solidified in retrievable form by reaction with silica.
- 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:
- 7146767
- Report Number(s):
- DPST-75-125-1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
RADIOACTIVE WASTE MANAGEMENT
RESEARCH PROGRAMS
SAVANNAH RIVER PLANT
CESIUM 137
CONCRETES
GLASS
ION EXCHANGE
LEACHING
NITRATES
NITRITES
PLUTONIUM 238
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
RUTHENIUM 106
SLUDGES
SOLID WASTES
SOLIDIFICATION
STRONTIUM 90
ZEOLITES
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
ALPHA DECAY RADIOISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CESIUM ISOTOPES
DISSOLUTION
EVEN-EVEN NUCLEI
HEAVY NUCLEI
INORGANIC ION EXCHANGERS
INTERMEDIATE MASS NUCLEI
ION EXCHANGE MATERIALS
ISOTOPES
MANAGEMENT
MATERIALS
MINERALS
NATIONAL ORGANIZATIONS
NITROGEN COMPOUNDS
NUCLEI
ODD-EVEN NUCLEI
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PLUTONIUM ISOTOPES
PROCESSING
RADIOISOTOPES
RUTHENIUM ISOTOPES
SEPARATION PROCESSES
STORAGE
STRONTIUM ISOTOPES
US AEC
US ERDA
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE PROCESSING
WASTE STORAGE
WASTES
YEARS LIVING RADIOISOTOPES
052001* - Nuclear Fuels- Waste Processing
052002 - Nuclear Fuels- Waste Disposal & Storage