The treatment of spent nuclear fuel for disposition using an electrometallurgical technique results in two high-level waste forms: a ceramic waste form (CWF) and a metal waste form. Reactive metal fuel constituents, including all the transuranic metals and the majority of the fission products remain in the salt as chlorides and are processed into the CWF. The solidified salt is containerized and transferred to the CWF process where it is ground in an argon atmosphere. Zeolite 4A is ground and then dried in a mechanically-fluidized dryer. The salt and zeolite are mixed in a V-mixer and heated to 500°C to occlude the salt into the structure of the zeolite. The salt-loaded zeolite is cooled, mixed with borosilicate glass frit, and transferred ...
The results of laboratory testing and modeling activities conducted to support the development of wa...
Not all the nuclear waste destined for Yucca Mountain is in the form of spent fuel. Some of it will ...
A pyrochemical treatment process of spent nuclear fuel, mainly composed of an electrolytic reduction...
The treatment of spent nuclear fuel for disposition using an electrometallurgical technique results ...
An electrometallurgical process is being developed at Argonne National Laboratory to treat spent met...
ABSTRACT Argonne National Laboratory has developed a process to immobilize waste salt containing fis...
The pyroprocessing of spent nuclear fuel results in two high-level waste streams--ceramic and metal ...
ABSTRACT SCALE UP OF CERAMIC WASTE FORMS FOR THE EBR-II SPENT FUEL TREATMENT PROCESS Matthew C. Morr...
Argonne is developing a method to treat spent nuclear fuel in a molten salt electrorefiner. Wastes f...
A ceramic waste form is being developed by Argonne National Laboratory (ANL) as part of the demonstr...
Over the last 10 years, pyrochemical treatment of spent nuclear fuel has progressed from demonstrati...
High-level radioactive waste salts generated during the electrometallurgical treatment of spent sodi...
Electrochemical processing of used nuclear fuel involves operation of one or more cells containing m...
Argonne National Laboratory has developed a composite ceramic waste form for the disposition of high...
A multiphase waste form referred to as the ceramic waste form (CWF) will be used to immobilize radio...
The results of laboratory testing and modeling activities conducted to support the development of wa...
Not all the nuclear waste destined for Yucca Mountain is in the form of spent fuel. Some of it will ...
A pyrochemical treatment process of spent nuclear fuel, mainly composed of an electrolytic reduction...
The treatment of spent nuclear fuel for disposition using an electrometallurgical technique results ...
An electrometallurgical process is being developed at Argonne National Laboratory to treat spent met...
ABSTRACT Argonne National Laboratory has developed a process to immobilize waste salt containing fis...
The pyroprocessing of spent nuclear fuel results in two high-level waste streams--ceramic and metal ...
ABSTRACT SCALE UP OF CERAMIC WASTE FORMS FOR THE EBR-II SPENT FUEL TREATMENT PROCESS Matthew C. Morr...
Argonne is developing a method to treat spent nuclear fuel in a molten salt electrorefiner. Wastes f...
A ceramic waste form is being developed by Argonne National Laboratory (ANL) as part of the demonstr...
Over the last 10 years, pyrochemical treatment of spent nuclear fuel has progressed from demonstrati...
High-level radioactive waste salts generated during the electrometallurgical treatment of spent sodi...
Electrochemical processing of used nuclear fuel involves operation of one or more cells containing m...
Argonne National Laboratory has developed a composite ceramic waste form for the disposition of high...
A multiphase waste form referred to as the ceramic waste form (CWF) will be used to immobilize radio...
The results of laboratory testing and modeling activities conducted to support the development of wa...
Not all the nuclear waste destined for Yucca Mountain is in the form of spent fuel. Some of it will ...
A pyrochemical treatment process of spent nuclear fuel, mainly composed of an electrolytic reduction...