A method is described for immobilizing waste chloride salts containing radionuclides and hazardous nuclear material for permanent disposal starting with a substantially dry zeolite and sufficient glass to form leach resistance sodalite with occluded radionuclides and hazardous nuclear material. The zeolite and glass are heated to a temperature up to about 1,000 K to convert the zeolite to sodalite and thereafter maintained at a pressure and temperature sufficient to form a sodalite product near theoretical density. Pressure is used on the formed sodalite to produce the required density
Argonne is developing a method to treat spent nuclear fuel in a molten salt electrorefiner. Wastes f...
Neutron diffraction studies of salt-occluded zeolite and zeolite/glass composite samples, simulating...
Pellets made of pure sodalite blended with commercial glass frit and pellets made of sodalite, glass...
The pyrometallurgical processing of spent nuclear fuel generates a chloride salt waste containing al...
Spent nuclear fuel can be treated in a molten salt electrorefiner for conversion into metal and mine...
A method is described for immobilizing waste chlorides salts containing radionuclides and hazardous ...
The electrometallurgical treatment of spent nuclear fuel generates a waste stream of fission product...
Two different glass powders (a commercially available glass frit and a borosilicate glass) have been...
Abstract: A waste LiCl salt generated from an electrolytic reduction process of a spent oxide fuel c...
A ceramic waste form (CWF) of glass bonded sodalite is being developed as a waste form for the long-...
Sodalite has been taken into account as a matrix for conditioning chloride salt wastes coming from p...
The electrometallurgical treatment of spent nuclear fuels result in a chloride waste salt requiring ...
Electrometallurgical treatment of spent nuclear fuel results in a secondary waste stream of radioact...
An electrometallurgical process is being developed at Argonne National Laboratory to treat spent met...
Sodalite/glass bodies prepared by hot isostatic pressing (HIPing) at ∼850 °C/100 MPa are c...
Argonne is developing a method to treat spent nuclear fuel in a molten salt electrorefiner. Wastes f...
Neutron diffraction studies of salt-occluded zeolite and zeolite/glass composite samples, simulating...
Pellets made of pure sodalite blended with commercial glass frit and pellets made of sodalite, glass...
The pyrometallurgical processing of spent nuclear fuel generates a chloride salt waste containing al...
Spent nuclear fuel can be treated in a molten salt electrorefiner for conversion into metal and mine...
A method is described for immobilizing waste chlorides salts containing radionuclides and hazardous ...
The electrometallurgical treatment of spent nuclear fuel generates a waste stream of fission product...
Two different glass powders (a commercially available glass frit and a borosilicate glass) have been...
Abstract: A waste LiCl salt generated from an electrolytic reduction process of a spent oxide fuel c...
A ceramic waste form (CWF) of glass bonded sodalite is being developed as a waste form for the long-...
Sodalite has been taken into account as a matrix for conditioning chloride salt wastes coming from p...
The electrometallurgical treatment of spent nuclear fuels result in a chloride waste salt requiring ...
Electrometallurgical treatment of spent nuclear fuel results in a secondary waste stream of radioact...
An electrometallurgical process is being developed at Argonne National Laboratory to treat spent met...
Sodalite/glass bodies prepared by hot isostatic pressing (HIPing) at ∼850 °C/100 MPa are c...
Argonne is developing a method to treat spent nuclear fuel in a molten salt electrorefiner. Wastes f...
Neutron diffraction studies of salt-occluded zeolite and zeolite/glass composite samples, simulating...
Pellets made of pure sodalite blended with commercial glass frit and pellets made of sodalite, glass...