[en] A glass-bonded ceramic waste form is being developed to immobilize high-level chloride waste salts generated during the conditioning of spent sodium-bonded nuclear fuel for disposal. The waste salt is loaded into zeolite cavities, mixed with a borosilicate glass, and consolidated at 800--900 C by hot isostatic pressing. During this process, small amounts of halite are generated, whereas the zeolite converts to the mineral sodalite, which retains most of the waste salt. In this work, optical microscopy, scanning electron microscopy, and transmission electron microscopy were used to characterize the halite inclusions in the final waste form. The halite inclusions were detected within micron- to submicron-sized pores that form within the glass phase in the vicinity of the sodalite/glass interface. The chemical nature and distribution of the halite inclusions were determined. The particular microstructure of the halite inclusions has been related to the corrosion of the ceramic waste form