Small Column Ion Exchange Testing of Superlig 644 for Removal of 137Cs from Hanford Tank Waste Envelope C (Tank 241-AN-107)

Kurath, D.E.; Blanchard, DL; Bontha,

doi:10.2172/757282

Cited by 4 publications

(5 citation statements)

References 4 publications

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“…Elution of cesium from SuperLig ® 644 was as expected for cycles [1][2][3][4][5]. Approximately 99% of the cesium was eluted in less than 12 BV, at flow rates that varied from 0.5 (cycle #1) to 1 BV/h (cycles #2 to #6).…”

Section: Results and Performance Against Objectivesmentioning

confidence: 60%

“…Extensive experimental investigations were conducted at Savannah River Technology Center (SRTC) and Battelle, Pacific Northwest National Laboratory (PNNL) with actual waste samples from Tanks 241-AW-101, 241-AN-103, 241-AN-102, 241-AZ-102, 241-AN-107, 241-AP-101, and a mixture of 241-AN-102 and a leachate from C-104 sludge. [1][2][3][4][5][6][7] The experiments focused on the decontamination factors produced by the resins for 137 Cs and 99 Tc removal from each of the waste tanks. The radiation stability of SuperLig ® 644 was studied under static conditions (i.e., batch irradiation tests with resins in contact with air, water, and simulant waste solution) 5,8,9 .…”

Section: Removal Of 137 Cs and 99mentioning

confidence: 99%

“…[1][2][3][4][5][6][7] The experiments focused on the decontamination factors produced by the resins for 137 Cs and 99 Tc removal from each of the waste tanks. The radiation stability of SuperLig ® 644 was studied under static conditions (i.e., batch irradiation tests with resins in contact with air, water, and simulant waste solution) 5,8,9 . The effects of chemical degradation were studied by IBC Advanced Technologies and Battelle, PNNL with simulated Hanford waste samples 10,11 .…”

Section: Removal Of 137 Cs and 99mentioning

confidence: 99%

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Multiple Ion Exchange Column Runs for Cesium and Technetium Removal from AW-101 Waste Sample

Hassan¹

2004

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Section: Results and Performance Against Objectivesmentioning

confidence: 60%

Section: Removal Of 137 Cs and 99mentioning

confidence: 99%

Section: Removal Of 137 Cs and 99mentioning

confidence: 99%

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Multiple Ion Exchange Column Runs for Cesium and Technetium Removal from AW-101 Waste Sample

Hassan¹

2004

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“…The compositions of the cesium ion exchange feeds were obtained from Kurath et al (1999) and Kurath et al (2000). The components that appear to have concentrated on the SL-644 resin relative to the feed concentrations include Cr, Co, and Zr.…”

Section: Icp-aes Resultsmentioning

confidence: 99%

Analysis of spent ion exchange media: Superlig 639 and Superlig 644

Kurath¹,

Wagner²

2000

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“…The Cs ion exchange eluant secondary waste compositions are shown in Table 3.3 and were generated by removal of 137 Cs by ion exchange from the AW-101 LAW supernatant (Kurath et al 2000a) and by removal of 137 Cs by ion exchange from the AN-107 LAW supernatant (Kurath et al 2000b). The various Cs eluants were received in five glass containers.…”

Section: Secondary Waste: Cs Ion Exchange Eluantmentioning

confidence: 99%

Vitrification and Product Testing of C-104 and AZ-102 Pretreated Sludge Mixed with Flowsheet Quantities of Secondary Wastes

Smith¹,

Bates²,

Goles³

et al. 2001

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SummaryThe U.S. Department of Energy (DOE) Office of River Protection (ORP) has acquired Hanford tank waste treatment services at a demonstration scale. The River Protection Project Waste Treatment Plant (RPP-WTP) team is responsible for producing an immobilized (vitrified) high-level waste (IHLW) waste form. Pacific Northwest National Laboratory, hereafter referred to as PNNL, has been contracted to produce and test a vitrified IHLW waste form from two Envelope D high-level waste (HLW) samples previously supplied to the RPP-WTP project by DOE.The primary objective for vitrifying the HLW samples is to generate glass products for subsequent product testing. The scope of the Vitrification and Product Testing has been divided into eight work elements: 1) Glass Fabrication, 2) Chemical Composition, 3) Radiochemical Composition, 4) Crystalline and Non-crystalline Phase Determination, 5) Release Rate (PCT), 6) Toxicity Characteristic Leaching Procedure (TCLP), 7) Total volatile organic and semi-volatile organic analyses (VOA and SVOA), and 8) WAPS, regulatory, and de-listing testing. The work presented in this report is from only the following 5 work elements: 1) Glass Fabrication, 2) Chemical Composition, 3) Radiochemical Composition, 4) Crystalline and Non-crystalline Phase Determination, and 5) Release Rate (PCT). These work elements will help demonstrate the RPP-WTP projects ability to satisfy the product requirements concerning, chemical and radionuclide reporting, waste loading, identification and quantification of crystalline and non-crystalline phases, and waste form leachability. Results from work elements 6 through 8, i.e. VOA, SVOA, dioxins, furans, PCBs, and total cyanide and sulfide analyses are reported in a separate document (Goheen et al., WTP-RPT-010).Two pretreated tank sludge samples, high-level wastes (241-C-104 and 241-AZ-102) hereafter referred to as C-104 and AZ-102 along with a HLW process simulant (know as the HLW Process Blank) were prepared as melter feeds for vitrification. Due to scheduling constraints and small initial sample size of the pretreated tank 241-AZ-102 sludge, this sample was divided into two samples that were vitrified separately (i.e. AZ-102, Melt 1 and AZ-102, Melt 2). The analyzed compositions of the pretreated C-104 and AZ-102 sludge wastes were used by Catholic University of America's (CUA) Vitreous State Laboratory (VSL) to determine the target glass composition.The two tank sludge samples, were processed through pretreatment chemical washing and leaching processes, and the pretreated sludges were converted to high-level waste (HLW) glass after flowsheet quantities of secondary wastes, i.e. Sr/TRU precipitate and Cs and Tc ion exchange eluants, generated from LAW supernatant pretreatment unit operations were added. Both sludge samples were processed through the following unit operations to simulate the RPP-WTP project flowsheet: 1) initial characterization; 2) washing; 3) leaching; and 4) filtration in a crossflow filtration system (Brooks et al., 2000a) (Brooks et al.,...

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Small Column Ion Exchange Testing of Superlig 644 for Removal of 137Cs from Hanford Tank Waste Envelope C (Tank 241-AN-107)

Cited by 4 publications

References 4 publications

Multiple Ion Exchange Column Runs for Cesium and Technetium Removal from AW-101 Waste Sample

Multiple Ion Exchange Column Runs for Cesium and Technetium Removal from AW-101 Waste Sample

Analysis of spent ion exchange media: Superlig 639 and Superlig 644

Vitrification and Product Testing of C-104 and AZ-102 Pretreated Sludge Mixed with Flowsheet Quantities of Secondary Wastes

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