Small Column Ion Exchange Testing of Superlig 644 for Removal of 137Cs from Hanford Tank Waste Envelope A (Tank 241-AW-101)

Multiple Ion Exchange Column Runs for Cesium and Technetium Removal from AW-101 Waste Sample

“…Elution of cesium from SuperLig ® 644 was as expected for cycles [1][2][3][4][5]. Approximately 99% of the cesium was eluted in less than 12 BV, at flow rates that varied from 0.5 (cycle #1) to 1 BV/h (cycles #2 to #6).…”

“…Extensive experimental investigations were conducted at Savannah River Technology Center (SRTC) and Battelle, Pacific Northwest National Laboratory (PNNL) with actual waste samples from Tanks 241-AW-101, 241-AN-103, 241-AN-102, 241-AZ-102, 241-AN-107, 241-AP-101, and a mixture of 241-AN-102 and a leachate from C-104 sludge. [1][2][3][4][5][6][7] The experiments focused on the decontamination factors produced by the resins for 137 Cs and 99 Tc removal from each of the waste tanks. The radiation stability of SuperLig ® 644 was studied under static conditions (i.e., batch irradiation tests with resins in contact with air, water, and simulant waste solution) 5,8,9 .…”

Removal of cesium from alkaline waste solution: Part I – Batch ion exchange study

“…The steps below essentially reduced the 137 Cs on the resin to permit its removal from the radioactive cell (hot cell) for analysis. Note that the steps are those used in the SuperLig ® 644 resin column ion exchange operation [2,[5][6][7][8][9][10][11][12].…”

“…This work is part of a larger effort to evaluate the effectiveness of the selected baseline ion exchange resin i.e., SuperLig ® 644 resin to remove 137 Cs from various Hanford site tank wastes [1][2][3][4][5][6][7][8][9][10][11]. The study focused on tank AN-104 waste solution.…”

Vitrification and Product Testing of AW-101 and AN-107 Pretreated Waste

“…Most of the radioactivity was removed from the two supemate samples through pretreatment chemical separation processes, and the decontaminated supemates were processed into low-activity waste (LAW) glass. The AW-101 supemate sample was processed through the following unit operations to simulate the RPP-WTP project flowsheeti 1) dilution of the feed (Uric et al 1999); 2) ultrailltration to remove entrained solids (Brooks et al 1999); 3) removal of *37CS by ion exchange (Kurath et al 2000a); and 4) removal of WC by ion exchange (Bhmchard et al 1999). The AN-107 supemate sample was processed through the following unit operations to simulate the RPP-WT.P project flowsheeti 1) dilution of the feed (Uric et al 1999); 2) removal of Sr/TRU by precipitation (Hallen et al 2000); 3) ultrafiltration to remove entrained solids and Sr/TRU precipitate (Hallen et al 2000); 4) removal of 137CS by ion exchange (Kurath et al 2000b); 5) removal of 'Tc by ion exchange (Blanchard et al 2000); and 5) removal of sulfate (S04) by a precipitation process (Fiskum et al 2000).…”