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U.S. Department of Energy
Office of Scientific and Technical Information

Waste management. Savannah River Laboratory quarterly report, July--September 1975

Technical Report ·
OSTI ID:7336452

The technical data summary was completed for a prospective process for treating and storing TRU waste. Tests showed that waste forms stored in closed containers were not adversely affected when subjected to temperatures as high as 240/sup 0/C. Tests indicate that waste supernate flowing through a 10-ft-long by 6-ft-diam column of ''Duolite'' will experience satisfactory /sup 137/Cs removal. Accelerated laboratory tests demonstrated that stress corrosion cracking aggressiveness of liquid wastes depends on relative concentrations of the major constituents. Tests were conducted to determine the rate of aqueous extraction of plutonium from the solvent by groundwater, and sorption of the plutonium from groundwater. Specifications for safety, monitoring, and corrosion control were developed for removing radioactive wastes from annuli of tanks that have leaked. Equipment was designed for gamma spectrometric analyses of beta-gamma emitters in waste packages. Laboratory tests indicated effective retention of /sup 137/Cs by soils from the burial ground and tank forms.

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:
7336452
Report Number(s):
DPST-75-125-3
Country of Publication:
United States
Language:
English