Immobilisation of Molten Licl Waste Using Zeolite A
نویسندگان
چکیده
The oxide fuel reduction process, based on an electrochemical method as well as the long-lived radioactive nuclides partitioning process based on pyroprocessing, which are being developed at the Korea Atomic Energy Research Institute (KAERI), are to generate molten salt wastes such as a LiCl salt and a LiCl-KCl eutectic salt, respectively. The treatment process of waste LiCl salt, consisting of an incorporation of the salts into zeolite 4A and then a hot pressing with a glass frit to form a saltloaded waste form, is being studied now. Free chloride content, chemical durability by a 7-day PCT, equivalents of the elements loaded within the salt-zeolite have been compared for the SLZ samples with different mixing ratios of the LiCl salt to zeolite 4A, resulting in an optimum mixing ratio of LiCl to zeolite, r = 1.0, which must be confirmed by the long-term behavior of a vitrified waste form.
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