Decontamination of Dissolved Salt Solution from Tank 19F Using Duolite CS-100 and Amberlite IRC-718 Resins

Lee, L.M.

Savannah River Site (S.C.)

关键词: Sample Preparation;    Radioactive Waste Processing;    12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities;    Liquid Wastes;    Organic Ion Exchangers;   

DOI  :  10.2172/787807
RP-ID  :  DPST-81-329
RP-ID  :  AC09-76SR00001
RP-ID  :  787807

美国|英语

来源: UNT Digital Library

【 摘 要 】

In this study actual Savannah River Plant liquid supernate solutions were processed to refine and verify these synthetic solution studies. The main objectives were: (1) confirm high decontamination factors (DFs) for cesium-137 and strontium-90 using Duolite CS-100 and Amberlite IRC-718 ion exchange resins, (2) obtain DFs for other minor radioactive isotopes such as plutonium, technetium and ruthenium, (3) provide ion exchange elutriant containing cesium-137, strontium-90 and other radioactive isotopes for ''hot'' melter studies, (4) determine the quality of the decontaminated salt solution, and (5) provide actual decontaminated salt solution for saltcrete development programs.