Characteristics of preliminary waste forms for ICPP low activity waste (LAW) fractions after radionuclide separations
- Lockheed Idaho Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering Lab.
Currently at the Idaho Chemical Processing Plant (ICPP) there are about 6,800 m{sup 3} of liquid sodium-bearing and liquid high-level wastes (HLW), and 3,800 m{sup 3} of solid calcined HLW. One of the waste processing options under consideration includes separation of the HLW into high activity and low activity (LAW) wastes, followed by immobilization. Preliminary glasses were synthesized for the sodium-bearing, alumina-bearing, and the zirconia-bearing LAW fractions after radionuclide separations. The glasses were formed by crucible melting of a mixture of reagent chemicals representative of the LAW waste streams and frit additives at 1,200 C for 5 hours, followed by overnight annealing at 550 C and furnace cooling of the melt. These glasses were characterized for density, elastic property, viscosity, chemical durability, structural parameters, and glass phase separation. The results are compared with that of the Hanford`s standard glass ARM-1, Savannah River`s benchmark glass EA, and the ICPP`s grout waste form prepared using the simulated non-radioactive sodium-bearing waste fraction.
- DOE Contract Number:
- AC07-94ID13223
- OSTI ID:
- 264416
- Report Number(s):
- CONF-951155-; ISBN 1-55899-315-0; TRN: 96:016561
- Resource Relation:
- Conference: Fall meeting of the Materials Research Society (MRS), Boston, MA (United States), 27 Nov - 1 Dec 1995; Other Information: PBD: 1996; Related Information: Is Part Of Scientific basis for nuclear waste management 19; Murphy, W.M. [ed.] [Southwest Research Inst., San Antonio, TX (United States)]; Knecht, D.A. [ed.] [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)]; PB: 957 p.; Materials Research Society symposium proceedings, Volume 412
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
05 NUCLEAR FUELS
GLASS
PHYSICAL PROPERTIES
CORROSION RESISTANCE
MECHANICAL PROPERTIES
PHASE STUDIES
WASTE FORMS
HIGH-LEVEL RADIOACTIVE WASTES
SEPARATION PROCESSES
LOW-LEVEL RADIOACTIVE WASTES
VITRIFICATION
MICROSTRUCTURE
ELASTICITY
COMPARATIVE EVALUATIONS
LIQUID WASTES
CHEMICAL COMPOSITION
LEACHING
EXPERIMENTAL DATA