Tank 241-AZ-102 SuperLig 639 Technetium Ion Exchange Eluate Evaporation Study
As part of the Hanford River Protection Project (RPP), the Savannah River Technology Center (SRTC) has conducted tests on the pretreatment and vitrification of a radioactive waste sample from Hanford Tank 241-AZ-102. The original, AZ-102 sample which was received at SRTC was characterized and filtered to remove entrained solids.1 The sample was then passed sequentially through ion exchange columns containing SuperLig{reg_sign} 644 and 639 resins for the removal of cesium and technetium ions (Tc removed as pertechnetate, TcO{sub 4}{sup {minus}}), respectively.2 The cesium and technetium absorbed to the resins was then eluted to give separate eluate solutions containing relatively high concentrations of Cs{sup +} and TcO{sub 4}{sup {minus}}. According to the current plant design, the decontaminated Tank 241-AZ-102 sample and the eluate solutions will be subjected to separate evaporation and vitrification processes to give low- and high-activity waste glasses, respectively. This report describes evaporation testing of the Tc eluate solution derived from ion exchange processing of the Tank 241-AZ-102 sample with SuperLig 639 resin.
- Research Organization:
- Savannah River Site (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC09-96SR18500
- OSTI ID:
- 774861
- Report Number(s):
- WSRC-TR-2000-00424 SRT-RPP-2000-00024 Rev. 0
- Country of Publication:
- United States
- Language:
- English
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