Immobilization of IFR salt wastes in mortar
Portland cement-base mortars are being considered for immobilizing chloride salt wastes produced by the fuel cycles of Integral Fast Reactors (IFR). The IFR is a sodium-cooled fast reactor with metal alloy fuels. It has a close-coupled fuel cycle in which fission products are separated from the actinides in an electrochemical cell operating at 500/degree/C. This cell has a liquid cadmium anode in which the fuels are dissolved and a liquid salt electrolyte. The salt will be a mixture of either lithium, potassium, and sodium chlorides or lithium, calcium, barium, and sodium chlorides. One method being considered for immobilizing the treated nontransuranic salt waste is to disperse the salt in a portland cement-base mortar that will be sealed in corrosion-resistant containers. For this application, the grout must be sufficiently fluid that it can be pumped into canister-molds where it will solidify into a strong, leach-resistant material. The set times must be longer than a few hours to allow sufficient time for processing, and the mortar must reach a reasonable compressive strength (/approximately/7 MPa) within three days to permit handling. Because fission product heating will be high, about 0.6 W/kg for a mortar containing 10% waste salt, the effects of elevated temperatures during curing and storage on mortar properties must be considered.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6627962
- Report Number(s):
- CONF-880903-45; ON: DE89003950
- Resource Relation:
- Conference: Spectrum '88: international topical meeting on nuclear and hazardous waste management, Pasco, WA, United States, 11 Sep 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CHLORIDES
RADIOACTIVE WASTE MANAGEMENT
IFR REACTOR
MORTARS
TEMPERATURE EFFECTS
BARIUM CHLORIDES
CALCIUM CHLORIDES
FLY ASH
LEACHING
LITHIUM CHLORIDES
MECHANICAL PROPERTIES
POTASSIUM CHLORIDES
SODIUM CHLORIDES
AEROSOL WASTES
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
ASHES
BARIUM COMPOUNDS
CALCIUM COMPOUNDS
CALCIUM HALIDES
CHLORINE COMPOUNDS
DISSOLUTION
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
HALIDES
HALOGEN COMPOUNDS
LITHIUM COMPOUNDS
LITHIUM HALIDES
MANAGEMENT
POTASSIUM COMPOUNDS
REACTORS
RESEARCH AND TEST REACTORS
RESIDUES
SEPARATION PROCESSES
SODIUM COMPOUNDS
WASTE MANAGEMENT
WASTES
ZERO POWER REACTORS
220500* - Nuclear Reactor Technology- Environmental Aspects
210500 - Power Reactors
Breeding
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors