Waste management. Savannah River Laboratory quarterly report, April--June 1975
Laboratory concretes containing high-activity powdered plant wastes have adequate compressive strength, similar to that of concretes containing simulated waste. Type 304L stainless steel was shown at laboratory scale to be satisfactory for use as a melter and primary container for glass-waste mixtures. Glasses containing high-activity powdered plant sludges are similar in microstructure to glasses containing simulated-sludge powder. Cesium sorption by ''Duolite'' ARC-359 is slightly enhanced by low concentrations of NO/sub 2//sup -/, CO/sub 3//sup 2 -/, SO/sub 4//sup 2 -/, and PO/sub 4//sup 3 -/, but not affected by AlO/sub 2//sup -/ or C/sub 2/O/sub 4//sup 2 -/. Batch equilibration tests of ion exchange resins for removal of /sup 90/Sr and Pu from simulated plant waste supernates show that Sr/sup 2 +/ is sorbed by ''Chelex'' 100 and that plutonium is sorbed by ''Duolite'' ARC-359. Tests of the conceptual process to isolate /sup 137/Cs from the bulk of sodium salts in waste supernate showed that radiolysis of ''Duolite'' ARC-359 resin could reduce throughput of the cesium removal process by 16 percent after a year. In simulated supernate, in the presence of approximately 15 percent of the sludge, solubility of SrCO/sub 3/ is approximately 10/sup -6/M. Leachabilities of only 10/sup -5/ and 10/sup -3/ g/(cm/sup 2/)(day) for /sup 90/Sr and /sup 137/Cs, respectively, were observed in monoliths prepared by solidification of waste tank sludge with silica and NaOH in the laboratory. Low temperature (-70/sup 0/F) brittle fracture characteristics were measured for plates of A285-B steel, which is used in waste storage tanks. ''Decon'' 4518 was the most effective of nine reagents in initial tests with Tank 16 sludge for cleaning and decontaminating the interior of waste tanks. Dry (ground-surface) soil effectively sorbs and immobilizes small volumes of postulated leaking solvent-complexed plutonium, but moist (subsurface) soil would permit extensive migration of postulated large volumes.
- 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:
- 7350122
- Report Number(s):
- DPST-75-125-2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
RADIOACTIVE WASTE MANAGEMENT
RESEARCH PROGRAMS
SAVANNAH RIVER PLANT
CESIUM 137
CLEANING
CONCRETES
GLASS
ION EXCHANGE
PLUTONIUM
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
RADIOLYSIS
RADIONUCLIDE MIGRATION
RESINS
SLUDGES
SOLIDIFICATION
STEELS
STRONTIUM 90
TANKS
ACTINIDES
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CESIUM ISOTOPES
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CONTAINERS
DECOMPOSITION
ELEMENTS
ENVIRONMENTAL TRANSPORT
EVEN-EVEN NUCLEI
INTERMEDIATE MASS NUCLEI
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
MANAGEMENT
MASS TRANSFER
MATERIALS
METALS
NATIONAL ORGANIZATIONS
NUCLEI
ODD-EVEN NUCLEI
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
PHASE TRANSFORMATIONS
POLYMERS
PROCESSING
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOISOTOPES
STORAGE
STRONTIUM ISOTOPES
TRANSURANIUM ELEMENTS
US AEC
US ERDA
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE PROCESSING
WASTE STORAGE
YEARS LIVING RADIOISOTOPES
052001* - Nuclear Fuels- Waste Processing
052002 - Nuclear Fuels- Waste Disposal & Storage