Modeling of Ion-Exchange for Cesium Removal From Dissolved Saltcake in SRS Tanks 1-3, 37 and 41

Smith, Frank

doi:10.2172/919040

Cited by 23 publications

(52 citation statements)

References 13 publications

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“…SRNL-STI-2009-00367, Rev. 0 columns, the models [2] studied the effect of temperatures (i.e., 25°C, 35°C, 45°C) and found that as temperature increased, cesium loading decreased; therefore, the lower temperature was selected. The models further evaluated waste treatment at flowrates (in terms of resin bed volume [BV]) of 0.7 BV/hr, 1.4 BV/hr, and 2.8 BV/hr.…”

Section: Figure 1 Spherical Resorcinol Formaldehyde Resin Beads In Hmentioning

confidence: 99%

“…For this study the middle flowrate of 1.4 BV/hr was chosen. Table 4] (2) Values were calculated with software by OLI Systems, Inc. [2] The other important feature selected for the column tests was the intended lead-lag design where the lead IX column does most of the cesium separation with the lag column, connected in series, capturing cesium that leaves the lead column once the lead column approaches saturation. At some design level of saturation the waste treatment will be stopped, ending one cycle of operation.…”

Section: Figure 1 Spherical Resorcinol Formaldehyde Resin Beads In Hmentioning

confidence: 99%

“…A simulant of the waste targeted for testing, Tank 2F, was made to the composition in Table 1 [2] . Table 2 shows that the simulant compared well to the actual waste, especially for the important species; e.g., Na, Cs, K, and OH, which affect loading of the RF resin and test its effectiveness.…”

Section: Simulant Solutionmentioning

confidence: 99%

“…The operation of one cycle was previously summarized as the six-step process after Table 4. For the current study, the baseline parameters used; e.g., number of BVs before cesium breakthrough, BV/hr, came from computational results of SCIX operation [2] with SRS waste. Prototypic aspects were: the chemical makeup of the waste, the flowrate in BV/hr, and the resin media itself; i.e., sRF.…”

Section: Test Equipmentmentioning

confidence: 99%

“…This resin has a strong preference for H + and can be eluted by using acid to remove Cs + and its competitors. Its relative affinities has been estimated [2] to be H + > Cs + > Rb + > K + > Na + . RF resin can withstand multiple cycles of loading and eluting before its usefulness is exhausted.…”

Section: Introductionmentioning

confidence: 99%

See 4 more Smart Citations

Removal of Cesium from Savannah River Site Waste with Spherical Resorcinol Formaldehyde Ion Exchange Resin: Experimental Tests

Duignan¹,

Nash²

2010

Separation Science and Technology

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Abstract:A principal goal at the Savannah River Site (SRS) is to safely dispose of the large volume of liquid nuclear waste held in many storage tanks. In-tank ion exchange (IX) columns are being considered for cesium removal. The spherical form of resorcinol formaldehyde ion exchange resin (sRF) is being evaluated for decontamination of dissolved saltcake waste at SRS, which is generally lower in potassium and organic components than Hanford waste. The sRF performance with SRS waste was evaluated in two phases: resin batch contacts and IX column testing with both simulated and actual dissolved salt waste. The tests, equipment, and results are discussed.

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Section: Figure 1 Spherical Resorcinol Formaldehyde Resin Beads In Hmentioning

confidence: 99%

Section: Figure 1 Spherical Resorcinol Formaldehyde Resin Beads In Hmentioning

confidence: 99%

Section: Simulant Solutionmentioning

confidence: 99%

Section: Test Equipmentmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Removal of Cesium from Savannah River Site Waste with Spherical Resorcinol Formaldehyde Ion Exchange Resin: Experimental Tests

Duignan¹,

Nash²

2010

Separation Science and Technology

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Early construction and operation of the highly contaminated water treatment system in Fukushima Daiichi Nuclear Power Station (III) – a unique simulation code to evaluate time-dependent Cs adsorption/desorption behavior in column system

Inagaki

Hijikata

Tsukada

et al. 2014

Journal of Nuclear Science and Technology

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A simulation code was developed to evaluate the performance of the cesium adsorption instrument operating in Fukushima Daiichi Nuclear Power Station. Since contaminated water contains seawater whose salinity is not constant, a new model was introduced to the conventional zeolite column simulation code to deal with the variable salinity of the seawater. Another feature of the cesium adsorption instrument is that it consists of several columns arranged in both series and parallel. The spent columns are replaced in a unique manner using a merry-go-round system. The code is designed by taking those factors into account. Consequently, it enables the evaluation of the performance characteristics of the cesium adsorption instrument, such as the time history of the decontamination factor, the cesium adsorption amount in each column, and the axial distribution of the adsorbed cesium in the spent columns. The simulation is conducted for different operation patterns and its results are given to Tokyo Electric Power Company (TEPCO) to support the optimization of the operation schedule. The code is also used to investigate the cause of some events that actually occurred in the operation of the cesium adsorption instrument.

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Characterization of the Binding Interaction between Poly(Epicholorohydrin‐Diamine) and Reactive Dyes using a Multiple Linear Regression and Quartz Crystal Microbalance Methods

Smith

Lee

King

et al. 2007

Separation Science and Technology

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Chemical and thermal performance of crystalline silicotitanate (CST) and resorcinolformaldehyde (RF) ion exchange media were predicted for column configurations designed for installation in high level waste tanks and intended for cesium removal from radioactive waste supernates. Modeling predictions for the processing of a known Savannah River Site tank waste composition were generated. In a two column configuration under presumed nominal operating conditions (432 gallon packed bed, 10 gpm liquid flow, 25 ºC, 45 nCi/g average breakthrough limit) with lead/lag column rotation between processing cycles, approximately two cycles were predicted to treat 1,000,000 gallons of radioactive waste with CST as compared to three cycles predicted for RF. However, this processing mode was shown to be highly unfavorable for RF due to the fact that the lead column is unnecessarily exposed to large radiation doses during movement of the cesium mass transfer zone into the lag column. Thermal modeling calculations indicated that maximum temperatures within stagnant, packed CST and RF columns containing the highest anticipated cesium loading and no active cooling will reach 128 and 78 ºC, respectively, within 6 days. Active cooling maintains the cesiumsaturated CST and RF columns below 88 and 41 ºC, respectively, under stagnant flow conditions.

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Modeling of Ion-Exchange for Cesium Removal From Dissolved Saltcake in SRS Tanks 1-3, 37 and 41

Cited by 23 publications

References 13 publications

Removal of Cesium from Savannah River Site Waste with Spherical Resorcinol Formaldehyde Ion Exchange Resin: Experimental Tests

Removal of Cesium from Savannah River Site Waste with Spherical Resorcinol Formaldehyde Ion Exchange Resin: Experimental Tests

Early construction and operation of the highly contaminated water treatment system in Fukushima Daiichi Nuclear Power Station (III) – a unique simulation code to evaluate time-dependent Cs adsorption/desorption behavior in column system

Characterization of the Binding Interaction between Poly(Epicholorohydrin‐Diamine) and Reactive Dyes using a Multiple Linear Regression and Quartz Crystal Microbalance Methods

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