Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Research and development activities Waste Fixation Program. Quarterly progress report, July--September 1977

Technical Report ·
DOI:https://doi.org/10.2172/6418319· OSTI ID:6418319
Through the Waste Fixation Program, the Pacific Northwest Laboratory is conducting research on the solidification of high-level radioactive waste. A major goal of this program is to develop reliable solidified waste forms and processes for their manufacture. The research and development activities of the past quarter are described. Over 25,500 lb of glass incorporating simulated defense waste was manufactured in a joule-heated ceramic melter this quarter. In one 86-hr period of continuous operation, 15,000 lb of glass was manufactured. The melting rate in the in-can melting process was found to be approximately proportional to the diameter of the canister, being 50, 70 and 90 kg/hr in canisters with 12-, 16-, and 20-in. diameters. A new, highly instrumented, high-capacity effluent system was installed that serves all of the calciners and melters in the engineering development laboratory. Preliminary leach tests of waste glass in salt brine at 250/sup 0/C and 1000 psi yielded leach rates of between 2 x 10/sup -4/ and 7 x 10/sup -4/ g/cm/sup 2/-day -- about the same as other similarly tested materials such as granite, alumina, and LWR fuel pellets. A Pb--10Sn alloy continued to appear superior to plain lead as a metal matrix material for waste glass marbles, based upon an examination of the interfacial area after heat treatments.
Research Organization:
Battelle Pacific Northwest Labs., Richland, WA (USA)
DOE Contract Number:
EY-76-C-06-1830
OSTI ID:
6418319
Report Number(s):
PNL-2265-3
Country of Publication:
United States
Language:
English