Abstract The pyrochemical process for the recycling of used nuclear fuels generates LiCl and LiCl–KCl waste salt during a series of processes. In particular, for the reduction of LiCl–KCl waste volume, radioactive rare earth nuclides in the LiCl–KCl waste salt are separated by a phosphorylation precipitation reaction, generating rare earth phosphate waste in a powder form. In this study, for the immobilization of rare earth phosphate wastes, rare earth calcium phosphate (RCP) glass waste forms have been fabricated using a CaO–P 2 O 5 glass system under a moderate vitrification temperature of below 1200 °C. Vitrification properties of NdPO 4 , which is a representative rare earth phosphate material have been investigated through XRD, SEM, EDX, DSC, IR, and density measurements. The RCP glass waste form fabricated from the 4CaO–6P 2 O 5 system showed an immobilization capacity of about 32 wt.% NdPO 4 waste loading. Also, chemical durabilities of RCP glass waste forms are investigated by PCT-A test.