Evaluation of Iron‐Phosphate Glass–Ceramic Waste Form for Electrorefiner Salt Waste Simulant Dechlorinated With Phosphoric Acid

ABSTRACT The importance of glass and glass–ceramic nuclear waste forms has been reaffirmed in recent years by the growing interest in nuclear power as a reliable energy source. Determination of processing methods for the disposal of halide‐containing wastes will be essential for the advancement of nuclear technologies such as non‐aqueous fuel reprocessing. Phosphate‐based dechlorination and subsequent vitrification of radioactive salt waste into an iron‐phosphate waste form have been identified as a potential processing scheme for electrochemical processing waste. The impact of H 3 PO 4 ‐based dechlorination of complex salt mixtures on the vitrification process and structure of the final iron‐phosphate waste form has not yet been investigated. In this work, iron‐phosphate glass–ceramics were made from simulant salt waste (48LiCl–33KCl–19NaCl mol%) dechlorinated with the H 3 PO 4 ‐based method. The glass‐forming region was compared to that of traditionally prepared Na 2 O–Fe 2 O 3 –P 2 O 5 systems. For a candidate glass‐forming composition, the processing scheme presented here was determined to favor Fe 3+ species. The O/P molar ratio was consistent for the candidate composition when dechlorinated at 400°C and 600°C in air and argon environments, indicating glass network connectivity was maintained despite variations in processing parameters. The results presented here validate processing schemes requiring iron‐phosphate waste form synthesis following H 3 PO 4 ‐based dechlorination.