Comparison of organic and inorganic ion exchangers for removal of cesium and strontium from simulated and actual Hanford 241-AW-101 DSSF tank waste

Brown, G.N.; Bray, L.A.; Carlson, C.D.

doi:10.2172/203484

Cited by 25 publications

(25 citation statements)

References 10 publications

(12 reference statements)

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“…, which was designed to selectively separate Cs in the presence of high concentrations of sodium and potassium like those found in high ionic-strength alkaline high-level radioactive tank waste. Previous studies have shown that this organic resin is capable of achieving high decontamination factors for Cs in both simulated and actual Hanford alkaline waste (Brown et al, 1995a;Brown et al, 1996;andBray et al, 1995, King et al, 2000). Furthermore, because hydrogen ions in solution (i.e., H + or H 3 O + ) compete for resin ion exchange sites, Cs sorbed to SuperLig ® 644 resin can be eluted with strong acids and the resin can be used for multiple ion exchange cycles (Brown et al, 1995b).…”

Section: Experimental Approachmentioning

confidence: 98%

Integrated Sr/TRU Precipitation and Cs Ion Exchange Process Validation

Serkiz¹

2003

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Section: Experimental Approachmentioning

confidence: 98%

Integrated Sr/TRU Precipitation and Cs Ion Exchange Process Validation

Serkiz¹

2003

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“…A variety of polymeric organic resins and inorganic materials have been evaluated for removing Cs-137 from alkaline liquid wastes at the Hanford and Savannah River sites (Bray et al 1993(Bray et al , 1995Brown et al 1996;Wester et al 2003). During the initial design of the Hanford Waste Treatment Plant, the contractor chose Cs ion exchange using SuperLig™ 644 as the baseline technology for removing Cs-137 from the LAW stream Bontha 1999, 2000).…”

Section: Ion Exchangementioning

confidence: 99%

The Role of Liquid Waste Pretreatment Technologies in Solving the Doe Clean-Up Mission

Wilmarth¹,

Bush²

2008

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“…It has been shown to be chemically and radiochemcially stable and highly selective for cesium even in the presence of excess sodium or potassium (Bray et al 1995a;Brown et al 1995a;Brown et al 1995b;Brown et al 1995c;Brown et al 1996a;Brown et al 1996b;Brown et al 1996~). …”

Section: 4mentioning

confidence: 99%

Performance evaluation of 24 ion exchange materials for removing cesium and strontium from actual and simulated N-Reactor storage basin water

Brown¹,

Carson²,

DesChane³

et al. 1997

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This report describes the evaluation of 24 organic and inorganic ion exchange materials for removing cesium and strontium from actual and simulated waters from the 100 Area 105 N-Reactor fuel storage basin. The data described in this report can be applied for developing and evaluating ion exchange pretreatment process flowsheets. Cesium and strontium batch distribution ratios (h's), decontamination factors (DF), and material loadings (mmol 8') are compared as a function of ion exchange material and initial cesium concentration.The actual and simulated N-Basin waters contain relatively low levels of aluminum, barium, calcium, potassium, and magnesium (ranging from 8.33E-04 to 6.40E-05 m, with slightly higher levels of boron (6.63E-03 M) and sodium (1.62E-03 M). The I3%s level is 1.74E-06 Ci L-' which corresponds to approximately 4.87E-10 M Cs. The initial Na/Cs ratio was 3.33E+06. The concentration of total strontium is 4.45E-06 M. while the %r radioactive component was measured to be 6.13E-06 Ci L-'.Simulant tests were conducted by contacting 0.067 g or each ion exchange material with approximately 100 mL of either the actual or simulated N-Basin water. The simulants contained variable initial cesium concentrations ranging from 1.00E-04 to 2.57E-10 M Cs while all other components were held constant.For all materials, the average cesium & was independent of cesium concentration below approximately 1 .OK06 M. Above this level, the average cesium I(d values decreased significantly. Cesium I(d values exceeding 1 .OE+07 mL g-' were measured in the simulated N-Basin water. However, when measured in the actual N-Basin water the values were several orders of magnitude lower, with a maximum of 1.24E+05 mL g-' observed. Several materials, including a potassium cobalt hexacyanoferrate (KCoHex), inorganic zeolites, crystalline silicotitanates, biotite micas, pharmacosiderites, and phlogopites exhibited substantial affinity for cesium. The nonspecific cation exchange materials did not show an appreciable affinity for cesium in the basin water.Because of the high levels of nonradioactive strontium and calcium, the strontium I& results were much lower (e.g., between 1 .OE+03 and 1 .OE+05 mL g-') than those for the cesium. The strontium I(d and loading were inversely correlated to the cesium concentration (increasing with decreasing concentration from 1.OE-04 to 1 .Os09 M Cs). The data suggest that either the two ions compete for similar ion exchange sites or the higher cesium loading perturbs the strontium sites such that the strontium exchange process is hindered.... SummaryThis report describes evaluations of the radionuclide uptake capability of several newly produced ion exchange materials under actual waste solution conditions and compares the results obtained with these materials to those obtained with other commercial and experimental exchangers. The ion exchange materials are being evaluated for their performance in treating water from the 105 N-Reactor basin at Hanford. Actual and simulated basin water was us...

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Comparison of organic and inorganic ion exchangers for removal of cesium and strontium from simulated and actual Hanford 241-AW-101 DSSF tank waste

Cited by 25 publications

References 10 publications

Integrated Sr/TRU Precipitation and Cs Ion Exchange Process Validation

Integrated Sr/TRU Precipitation and Cs Ion Exchange Process Validation

The Role of Liquid Waste Pretreatment Technologies in Solving the Doe Clean-Up Mission

Performance evaluation of 24 ion exchange materials for removing cesium and strontium from actual and simulated N-Reactor storage basin water

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