Cesium Ion Exchange Testing Using Crystalline Silicotitanate with Hanford Tank Waste 241-AP-107

Rovira, Amy M.; Fiskum, Sandra K.; Colburn, Heather A.; Allred, Jarrod R.; Smoot, Margaret R.; Peterson, Reid A.

doi:10.2172/1466215

Cited by 9 publications

(18 citation statements)

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“…Measurements were conducted by PNNL's ASO organization in RPL according to the Analytical Service Requests (ASR) 0543 (gamma) and 0552 (total activity). The activity for each sample was measured and compared to the parent AP-107 feed analysis completed and reported by Rovira et al (2018) as part of PNNL's Radioactive Test Platform 1 work.…”

Section: Resultsmentioning

confidence: 99%

“…6.2 (a) 241-AP-107 sample 7AP-17-11 GEA results reported by Rovira et al (2018) The actual samples of interest for the purpose of Hg species quantification using CVAFS are the Carbotrap ® and gold-coated sand substrate materials. These traps will eventually be heated and purged with an inert gas to desorb, volatilize, and deliver the mercury to the fluorescence detector.…”

Section: Resultsmentioning

confidence: 99%

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Separation and Speciation of Mercury from Hanford 241-AP-107 Tank Waste Supernatant

Fountain

Branch

Gill

2018

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Separation and Speciation of Mercury from Hanford 241-AP-107 Tank Waste Supernatant

Fountain

Branch

Gill

2018

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“…The AP-107 waste was delivered in two portions, one of approximately 4.8 L and a second of approximately 3.8 L. The composition of the AP-107 waste after solids and cesium removal was analyzed by Rovira et al (2018). The mass of each GFC to be added to the separate portions of the AP-107 waste was calculated by the glass models documented in Kim et al (2012) to satisfy the WTP baseline requirements and the GFCs masses are given in Table 2.2.…”

Section: Melter Feed Preparationmentioning

confidence: 99%

“…A second waste portion was received at the RPL, the supernatant from Hanford tank 241-AP-107 (hereafter called AP-107). This AP-107 waste went through solids removal by filtration (Geeting et al 2018b) and cesium removal by ion exchange (Rovira et al 2018); this test report describes the results 1.2 from the vitrification of the treated AP-107 waste in the CLSM in RPL. The vitrification test was performed in August 2018, during which glass product and off-gas effluents, both gaseous and liquid, were collected for elemental analysis.…”

Section: Introductionmentioning

confidence: 99%

Vitrification of Hanford Tank Waste 241-AP-107 in a Continuous Laboratory-Scale Melter

Dixon

Stewart

Venarsky

et al. 2019

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Low-activity waste (LAW) stored in underground tanks on the Hanford Site in Washington State is planned to be filtered for solids removal and processed through ion exchange columns for cesium removal. These pretreatment steps will allow the waste to be transferred to the Hanford Tank Waste Treatment and Immobilization Plant's LAW Facility for immobilization into glass. The liquid waste will be combined with glass-forming chemicals (GFCs) to form a waste feed slurry that can be fed to electric melters for vitrification. The process of continuously converting the aqueous feed slurry into a melt is dynamic and includes multiple reactions, degassing, and dissolution processes that depend on heat from the melt below. In this conversion process, waste components are partitioned into one of two streams: glass and off-gas. Washington River Protection Solutions has requested processing information and chemical information associated with these waste products for actual waste from Hanford tank 241-AP-107 (referred to herein as AP-107). To acquire this type of information, a small-scale melter system was designed that would not require high volumes of input waste or the large resource commitment of a full-scale melter system, while also providing dynamic information that would be difficult to determine from batch reactions in a crucible system. A continuous laboratory-scale melter (CLSM) has been designed to operate with a continuous feeding process while periodically pouring glass product and collecting off-gas. The CLSM vessel has been sized to collect the relevant process and chemical information from obtainable volumes of AP-107 waste samples. A total 8.6 L of actual AP-107 tank waste were received after filtering for solids removal and ion exchange for cesium removal. This volume of AP-107 waste was mixed with GFCs to form an estimated 11.8 L of melter feed slurry. A mass of 7.01 kg of glass product were poured from the CLSM vessel during 10.07 hours of charging the AP-107 melter feed, indicating that about 15.0 kg of melter feed was vitrified into glass. These production values and other processing results from the AP-107 waste vitrification in the CLSM system are shown in Table ES.1. The CLSM system was also designed with the capability to fully divert the flow of off-gas produced in the CLSM vessel to a sampling line that could capture the volatile species of interest, such as technetium-99 (99 Tc). This novel sampling system avoided the difficulties of slipstream sampling and could be activated once the feeding reached a steady state within the CLSM vessel. Off-gas product samples captured via high-efficiency particulate air (HEPA) filters using this method, as well as selected glass product samples were sent to an analytical lab for chemical analysis. The calculated average retention of 99 Tc (mass of 99 Tc output in the glass per mass of 99 Tc input in the melter feed) during the off-gas sampling is shown in Table ES.1. The measured composition of the AP-107 glass product, compared to the target composition, is s...

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“…The above two parameters were revised, based on recent Pacific Northwest National Laboratory (PNNL) data where a recently manufactured batch of UOP CST media (IONSIV TM R9140-B received in 2018) was used for testing. The new CST batch specific information employed was the batch contact tests and column breakthrough tests performed by Fiskum et al (2018) for a simple simulant and by Rovira et al (2018) for actual AP-107 tank waste. There are some results from this testing that are not consistent with historical observations (discussed later in this report), but, given the urgency in arriving at an acceptable column size best estimate, we employed these test results to establish more batch-specific parameter values: To accomplish the column sizing and sensitivity studies mentioned above, several computational tasks were performed and are discussed in subsequent sections of this report.…”

Section: Introductionmentioning

confidence: 99%

Crystalline Silicotitanate Ion Exchange Column Sizing and Sensitivity Study in Support of the Hanford Test Bed Initiative

McCabe

Hamm

2018

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The Environmental Management Office of the Department of Energy (DOE) is spearheading a Test Bed Initiative a (TBI) to treat and dispose 2,000 gallons of tank waste from Hanford. One step in the process is to remove radioactive 137 Cs from the waste using Crystalline Silicotitanate b (CST) ion exchange media. This report describes the modeling performed to provide an estimate of the volume of a bed of CST required to meet the design requirements. Sensitivity studies were also performed to help provide project guidance. This modeling effort assumed 2100 gallons of waste to be processed (i.e., entire 2000 gallon campaign plus a 100 gallon margin).The Savannah River National Laboratory (SRNL) has extensive experience in the testing and modeling of ion exchange columns using CST for the explicit removal of 137 Cs from highly caustic feed solutions. This analysis effort uses SRNL's modeling methodology for CST based on extensive testing for Savannah River Site (SRS), Hanford Site, and other DOE Complex-wide applications. This methodology has been used to assess primarily waste streams with typically lower potassium concentrations than that expected for the TBI waste stream and with CST manufactured into a smaller bead size than planned for use in TBI. However, while applying the existing model methodology to recent CST testing of Hanford simulant and actual tank waste, it was found capable of adequately predicting measured Cs breakthrough performance at high potassium and with larger bead size media. As the results provided in this report indicate, a reliable calculational scheme has been achieved that can provide design guidance on the sizing and expected performance for the upcoming TBI ion exchange column.

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Cesium Ion Exchange Testing Using Crystalline Silicotitanate with Hanford Tank Waste 241-AP-107

Cited by 9 publications

References 0 publications

Separation and Speciation of Mercury from Hanford 241-AP-107 Tank Waste Supernatant

Separation and Speciation of Mercury from Hanford 241-AP-107 Tank Waste Supernatant

Vitrification of Hanford Tank Waste 241-AP-107 in a Continuous Laboratory-Scale Melter

Crystalline Silicotitanate Ion Exchange Column Sizing and Sensitivity Study in Support of the Hanford Test Bed Initiative

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