Removal of 137Cs from Dissolved Hanford Tank Saltcake by Treatment with IE-911

Rapko, Brian M. (BATTELLE (PACIFIC NW LAB)) ; Sinkov, Serguei I. (BATTELLE (PACIFIC NW LAB)) ; Levitskaia, Tatiana G. (BATTELLE (PACIFIC NW LAB))

Pacific Northwest National Laboratory (U.S.)

关键词: Removal;    12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities;    Ion Exchange;    Radioactive Waste Processing;    Cesium 137;   

DOI  :  10.2172/15003809
RP-ID  :  PNNL-14250
RP-ID  :  AC06-76RL01830
RP-ID  :  15003809

美国|英语

来源: UNT Digital Library

【 摘 要 】

The U.S. Department of Energy's Richland Operations Office plans to accelerate the cleanup of the Hanford Site. Testing new technology for the accelerated cleanup will require dissolved saltcake from single-shell tanks. However, the 137Cs will need to be removed from the saltcake to alleviate radiation hazards. A saltcake composite constructed from archived samples from Hanford Single Shell Tanks 241-S-101, 241-S-109, 241-S-110, 241-S-111, 241-U-106, and 241-U-109 was dissolved in water, adjusted to 5 M Na, and transferred from the 222-S building to the Radiochemical Processing Laboratory (RPL). At the RPL, the approximately 5.5 liters of solution was passed through a 0.2-micron polyethersulfone filter, collected, and homogenized. The filtered solution then was passed through an ion exchange column containing approximately 150 mL IONSIV IE-911, an engineered form of crystalline silicotitanate available from UOP, at approximately 200 mL/hour in a continuous operation until all of the feed solution had been run through the column. An analysis of the 137Cs concentrations in the initial feed solution and combined column effluent indicates that> 99.999 percent of the Cs in the feed solution was removed by this operation. This report describes the Cs-depletion operations together with a partial analysis of the as-received solution and a more extensive characterization of the Cs-depleted solution.