Characterization of off-gases from a small-scale, joule-heated ceramic melter for nuclear waste vitrification. [Ru, Cl, F, /sup 137/Cs]

Conference · Tue Jan 01 00:00:00 EST 1980

OSTI ID:5510987

Woolsey, G. B.; Wilhite, E. L.

This paper confirmed with actual nuclear waste the thermodynamic predictions of the fate of some of the semivolatiles in off-gas. Ruthenium behaves erratically and it is postulated that it migrates as a finely divided solid, rather than as a volatile oxide. Provisions for handling these waste off-gasses will be incorporated in the design of facilities for vitrifying SRP waste.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
• DOE Contract Number: EY-76-C-09-0001
• OSTI ID: 5510987
• Report Number(s): DP-MS-79-92; CONF-800460-1; TRN: 80-007787
• Resource Relation: Conference: 82. annual American Ceramic Society meeting, Chicago, IL, USA, 27 Apr 1980
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTE PROCESSING
VITRIFICATION
CESIUM 137
CHLORINE
DEGASSING
FLUORINE
MELTING
RUTHENIUM
SAVANNAH RIVER PLANT
SLUDGES
VOLATILE MATTER
ALKALI METAL ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CESIUM ISOTOPES
ELEMENTS
HALOGENS
ISOTOPES
MANAGEMENT
METALS
NATIONAL ORGANIZATIONS
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
PHASE TRANSFORMATIONS
PLATINUM METALS
PROCESSING
RADIOISOTOPES
REFRACTORY METALS
TRANSITION ELEMENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE PROCESSING
YEARS LIVING RADIOISOTOPES
052001* - Nuclear Fuels- Waste Processing