An advanced spent fuel management process that is based on Li reduction of the spent oxide fuel to metallic form generates waste LiCl salt containing the alkali, alkaline-earth and some of the rare-earth fission products. The recycling of the LiCl waste salt to the process stream needs periodic removal of the Cs and Sr, which generate high radioactive decay heat. In this study, zeolite 4A was selected as an absorbent for removal of Cs and Sr element in LiCl molten salt phase, and the ion-exchange characteristics were investigated. Batch tests have shown that zeolite 4A has the desirable properties for selective removal of Cs and Sr elements by the ion-exchange process. Uptake of Cs and Sr elements in LiCl molten salt reaches nearly a constant value after 2 to 4 h of contact. We have formed salt occluded zeolite from LiCl molten salt, and studied its ion exchange and salt occlusion properties experimentally. The results indicate that zeolite 4A occluded between 10 and 11.5 salt molecules, and the salt occluded zeolite was found to be the most effective molecular sieve for sorbing Cs and Sr in LiCl waste salt.