Tank 241-AZ-102 SuperLig 639 Technetium Ion Exchange Eluate Evaporation Study

King, W. D.

Savannah River Site (S.C.)

关键词: Technetium Ions;    Evaporation;    Radioactive Wastes;    Wastes;    Technetium;   

DOI  :  10.2172/774861
RP-ID  :  WSRC-TR-2000-00424 SRT-RPP-2000-00024 Rev. 0
RP-ID  :  AC09-96SR18500
RP-ID  :  774861

美国|英语

来源: UNT Digital Library

【 摘 要 】

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.