RECOVERY OF NEPTUNIUM-237 BY ION EXCHANGE
Technical Report
·
OSTI ID:4006940
Adsorption and concentration of neptunium-237 occurring in trace level quantities in uranyl nitrate solutions were accomplished by cation exchange. Subsequent purification by anion exchange for removal of fission products was demonstrated to be feasible. Gamma scintillation spectrometry was found to be a valuable aid in quantitatively assessing radionuclide concentrations in the system's streams. (auth)
- Research Organization:
- Union Carbide Nuclear Co. Y-12 Plant, Oak Ridge, Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-15-026116
- OSTI ID:
- 4006940
- Report Number(s):
- Y-1346
- Country of Publication:
- United States
- Language:
- English
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