Leaching characteristics of actinides from simulated reactor waste glass

Conference · Tue Oct 24 04:00:00 EDT 1978

OSTI ID:6792136

Weed, H C; Coles, D G; Bradley, D J; Mensing, R W; Schweiger, J S

Two methods for measuring the leach rates of simulated high level waste glass are compared. One is a modification of the standard IAEA method and the other is a one-pass method in which fresh leachant solution is pumped over the sample at a controlled flow rate and temperature. For times up to 3 days, there is close agreement between results from the two methods at 25.0C. Leach rates from the one-pass method show no correlation with flow rate at 25.0C, but at 75.0C leach rate increases with flow rate. Np-237 rates at 75.0C are greater than those at 25.0C, but /sup 239/Pu rates at 75.0C are less than or equal to those at 25.0C. Resorption of /sup 239/Pu associated with (SiO/sub 2/)/sub x/ polymers at high temperature is suggested as a possible cause.

• Research Organization: California Univ., Livermore (USA). Lawrence Livermore Lab.
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6792136
• Report Number(s): UCRL-81147; CONF-781121-12
• Country of Publication: United States
• Language: English

Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDES
BORON COMPOUNDS
BOROSILICATES
DISSOLUTION
ELEMENTS
ENVIRONMENTAL TRANSPORT
GLASS
HIGH-LEVEL RADIOACTIVE WASTES
LEACHING
MANAGEMENT
MASS TRANSFER
METALS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
RADIONUCLIDE MIGRATION
SEPARATION PROCESSES
SILICON COMPOUNDS
UNDERGROUND DISPOSAL
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES