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

Research and development activities waste fixation program. Quarterly progress report, April--June 1977

Technical Report ·
DOI:https://doi.org/10.2172/6619441· OSTI ID:6619441
Through the Waste Fixation Program, the Pacific Northwest Laboratory is directing research on the solidification of high-level radioactive waste. A major goal of this program is to develop reliable waste glass compositions and processes for their manufacture. This progress report describes the research and development activities of the past quarter: A 36-in.-diam spray calciner coupled to a 210 KWA electrical resistance in-can melter, capable of accepting canisters 24 in. in diameter by approximately 9 ft long, was placed in operation. In initial tests, a waste feed rate of 210 liters/hour and a melting rate of 60 kg glass/hour were demonstrated. Leach rates of multiple samples from five nonradioactive simulated waste glass canisters (runs ICM-16, -18, -20, and -34) show good uniformity for the glass in the 8 to 16 in. diameter canisters. X-ray diffraction measurements on supercalcine containing 3 wt% /sup 244/Cm show that the radiation is causing the apatite phase to become amorphous. Fluorite and tetragonal phases are unaffected after three months. Self-decontamination of waste canisters (WSEP canisters SS-7 and PG-2) in a mini-wet basin was demonstrated. In the first 150 days, 86% of the initial smearable contamination was removed. Simulated waste glass marbles, encapsulated in an A1-12Si matrix were examined microscopically after 10-day heat treatments at 300 and 500/sup 0/C. No reaction between the glass and metal matrix was observed.
Research Organization:
Battelle Pacific Northwest Labs., Richland, WA (USA)
DOE Contract Number:
EY-76-C-06-1830
OSTI ID:
6619441
Report Number(s):
PNL-2265-2
Country of Publication:
United States
Language:
English