Mixtures of Linde Ionsiv IE-96 and Linde Ionsiv A-51 were evaluated for use in the Submerged Demineralizer System (SDS) that was installed at the Three Mile Island Nuclear Power Station, Unit 2 (TMI-2) for decontaminating approx. 2650 m3 of high-activity-level water (HALW) in the Containment Building (CB) sump.

Mixtures of Linde Ionsiv IE-96 and Ionsiv A-51 were evaluated for use in the Submerged Demineralizer System (SDS) that was installed at the Three Mile Island Unit 2 Nuclear Power Station to decontaminate approx. 2780 m3 of high-activity-level water. The original SDS flowsheet was conservatively designed for removal of cesium and strontium and would have required the use of approx. 60 SDS columns. Mixed zeolite tests were made on a 10−5 scale and indicated that the appropriate ratio of IE-96/A-51 was 3/2. A mathematical model was used to predict the performance of the mixed zeolite columns in the SDS configuration and with the intended method of operation. Actual loading results were similar to those predicted for strontium and better than those predicted for cesium. The number of SDS columns needed to process the HALW was reduced to approx. 10. 6 references, 4 figures, 2 tables.

Proceedings of the NATO Advanced Study Institute on Zeolites: Science and Technology, Alcabideche, Portugal, May 1-12, 1983

Tests were made to investigate flowsheet modifications which might improve the expected performance of the reference Submerged Demineralizer System (SDS) flowsheet for decontaminating the high-activity-level water at the Three Mile Island Nuclear Power Station, Unit 2. The tests included one series designed to show the effects of aging time, temperature, and pH on reduction of the concentrations of residual /sup 137/Cs and /sup 90/Sr, and a second series designed to evaluate the physical sorption of /sup 125/Sb on silica gel or other inorganic sorbents. Results of the tests indicated that the most promising method for reducing /sup 137/Cs and /sup 90/Sr concentrations below 10/sup -4/ .mu. Ci/mL is to age the effluent water from the zeolite columns for at least 2 h at 75/sup 0/C prior to its passage through another zeolite column. Sorption of the /sup 125/Sb on silica gel or other inorganic sorbents did not show sufficient promise to be considered for practical use. A previously identified method for removal of /sup 125/Sb requires deionization of the water by removal of the sodium on a cation exchange resin prior to sorption of /sup 125/Sb on anion exchange resin; however, this method would generate a relatively large amount of low-activity-level solid waste (ion exchange resin).