Evaluation of Pu Solubility in Glass for Sludge Batch 11
Abstract
Stainless-steel clad Pu from Japan’s Fast Critical Assembly (FCA) reactor is currently being dispositioned at the Savannah River Site. The electrolytic dissolver, operated by Savannah River Nuclear Solutions in H-Canyon, is being utilized to dissolve the material. The resulting solutions are transferred to the Concentration, Storage, and Transfer Facilities, operated by Savannah River Mission Completion (SRMC), for subsequent vitrification at the Defense Waste Processing Facility (DWPF). In support of the FCA mission startup, a preliminary evaluation was conducted by the Savannah River National Laboratory to assess the impact of the FCA discards on the liquid waste system.
Fields of Study & Subjects
Nuclear materials and radiation effects
Radioactive element chemistry and processing
Glass properties and applications
Publication details
- Publication date
- 1 January 2026
- Language
- EN