Research and Development Activities Waste Fixation Program. Quarterly progress report, July--September 1976

Technical Report · Mon Aug 01 04:00:00 EDT 1977

DOI:https://doi.org/10.2172/7211264· OSTI ID:7211264

McElroy, J L

Two engineering-scale in-can melting runs were completed. One run evaluated the melting of PW-8a-2 type waste containing cesium and ruthenium with 76-101 type frit. The other run established a melting rate of 30.9 kg/hr for an 8-in.-diam can containing a drop-in fin assembly made from an alloy having an expansion coefficient similar to that of the glass. High sodium feed was successfully spray calcined by lowering the calciner chamber temperature and using an additive in the feed material. The fluidized-bed calciner testing continued with emphasis on developing several mechanical components and engineering a hot cell installation and a full-scale prototype. A variable speed, weigh belt-type solids feeder was evaluated as a frit feeding device. A 76-183 melt composition was developed for PW-7a waste. Leach testing of thermally treated glasses was continued and feeders were evaluated. Comprehensive examination of 72-68 glass samples annealed for 1 year has been completed and has indicated no significant change over the results observed at 2 months. Additionally, characterization and identification work performed on the high-neodymium rare earth phase has indicated that an apatite-type structure exists within the temperature range of 500 to 750/sup 0/C but only after a minimum time of 1 week at temperature. Preliminary impact tests on a gravity-sintered 304 stainless steel matrix demonstrate that the majority of the cracks go around, not through, the Al/sub 2/O/sub 3/ supercalcine cores. Gravity sintering parameters for stainless steel matrices have been reduced to 1050/sup 0/C for 8 hr in a stagnant atmosphere, and both stainless steel Al/sub 2/O/sub 3/ and pure stainless steel spheres have been successfully fabricated.

• Research Organization: Battelle Pacific Northwest Labs., Richland, Wash. (USA)
• DOE Contract Number: EY-76-C-06-1830
• OSTI ID: 7211264
• Report Number(s): BNWL-2243
• Country of Publication: United States
• Language: English

Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALKALI METALS
CALCINATION
CERAMICS
CESIUM
CHEMICAL REACTIONS
DECOMPOSITION
DISSOLUTION
ELEMENTS
GLASS
LEACHING
MANAGEMENT
METALS
PHASE TRANSFORMATIONS
PLATINUM METALS
PROCESSING
PYROLYSIS
RADIOACTIVE WASTE PROCESSING
REFRACTORY METALS
RESEARCH PROGRAMS
RUTHENIUM
SEPARATION PROCESSES
SOLIDIFICATION
TRANSITION ELEMENTS
WASTE MANAGEMENT
WASTE PROCESSING