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Recovery of Enriched Mo-100 from Low Specific Activity Mo-99/Tc-99m Generator Waste Streams

Technical Report ·
DOI:https://doi.org/10.2172/2425861· OSTI ID:2425861
 [1];  [1];  [1]
  1. Argonne National Laboratory (ANL), Argonne, IL (United States)
This study assessed two potential techniques for the extraction of pure Mo-100 target material from Mo-99/Tc-99m waste streams: 1) an established solvent-extraction method tailored for Mo-99 spent solution recycling, and 2) a low-temperature molten salt electrochemical process. By making minor modifications to the conventional solvent extraction method, particularly to accommodate the altered solubility limits arising from elevated Na+ concentrations in the waste, we achieved quantitative Mo recoveries. Although the electrochemical technique offers advantages in scalability and processing simplicity, it proved ineffective in recovering Mo from a NaOH-KOH salt melt.
Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
DOE Contract Number:
AC02-06CH11357
OSTI ID:
2425861
Report Number(s):
ANL--23/48; 185563
Country of Publication:
United States
Language:
English

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