Small Column Testing of Superlig 639 for Removal of 99Tc from Hanford Tank Waste Envelope C (Tank 241-AN-107)

Blanchard, DL; Kurath, D.E.; Rapko, BM

doi:10.2172/757286

Cited by 12 publications

(16 citation statements)

References 3 publications

(6 reference statements)

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“…Described sample treatments were noted not to significantly affect total 99 Tc concentration and speciation. 26 Resulting sample solutions were filtered using 0.45-µm filters prior to experimentation. To determine the content of non-pertechnetate species, the nuclear waste samples were batch contacted with excess Superlig 639 solid-phase extraction material (IBC Technologies, Inc., American Fork, UT).…”

Section: Methodsmentioning

confidence: 99%

See 1 more Smart Citation

Microwave-Assisted Sample Treatment in a Fully Automated Flow-Based Instrument: Oxidation of Reduced Technetium Species in the Analysis of Total Technetium-99 in Caustic Aged Nuclear Waste Samples

2004

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An automated flow-based instrument for microwave-assisted treatment of liquid samples has been developed and characterized. The instrument utilizes a flow-through reaction vessel design that facilitates the addition of multiple reagents during sample treatment and removal of the gaseous reaction products and enables quantitative removal of liquids from the reaction vessel for carryover-free operations. Matrix modification and speciation control chemistries that are required for the radiochemical determination of total (99)Tc in caustic aged nuclear waste samples have been investigated. A rapid and quantitative oxidation procedure using peroxydisulfate in acidic solution was developed to convert reduced technetium species to pertechnetate in samples with high content of reducing organics. The effectiveness of the automated sample treatment procedures has been validated in the radiochemical analysis of total (99)Tc in caustic aged nuclear waste matrixes from the Hanford site.

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Section: Methodsmentioning

confidence: 99%

“…This sorbent material selectively removes pertechnetate from caustic samples but does not exhibit affinity toward non-pertechnetate species. 26 The content of non-pertechnetate was determined by subtracting the total 99 Tc concentration in the samples with removed pertechnetate from the total 99 Tc concentration of the untreated samples.…”

Section: Methodsmentioning

confidence: 99%

Microwave-Assisted Sample Treatment in a Fully Automated Flow-Based Instrument: Oxidation of Reduced Technetium Species in the Analysis of Total Technetium-99 in Caustic Aged Nuclear Waste Samples

2004

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“…Note that unlike its corresponding equation 6for the 35.37-70 o C range, this equation includes density terms. The measured density of the sample should be used as opposed to that calculated by equation (11).…”

Section: Expressions Valid For 20-3537 O Cmentioning

confidence: 99%

“…For the two AN-102 samples ("small" and "large" C eluate samples) [9,10] the anion concentrations determined by ion chromatography (NO 2 , NO 3 , Cl, PO 4 , etc…) were below the detection limits making the data unsuitable for this purpose. The columns used in the AN-107 experiment [11] had been used previously in the AW-101 [8] experiment mentioned above. Analytical results of the AN-107 eluate indicate that the columns may have been contaminated with AW-101 waste at the onset of the experiment.…”

Section: Determination Of Significant Eluate Speciesmentioning

confidence: 99%

Preliminary Modeling Results of Evaporated Tc-Eluate Physical Properties

Choi¹

2003

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“…The Tc ion exchange eluants were generated by removal of 99 Tc by ion exchange from the AW-101 LAW supernatant (Blanchard et al 1999) and by removal of 99 Tc by ion exchange from the AN-107 LAW supernatant (Blanchard et al 2000). The Sr/TRU precipitate solids were generated by removal of Sr/TRU by precipitation and ultrafiltration to remove entrained solids and the Sr/TRU precipitate from the AN-107 LAW supernatant (Hallen et al 2000).…”

Section: Secondary Waste: Tc Ion Exchange Eluant and Sr/tru Precipitamentioning

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 Testing of Superlig 639 for Removal of 99Tc from Hanford Tank Waste Envelope C (Tank 241-AN-107)

Cited by 12 publications

References 3 publications

Microwave-Assisted Sample Treatment in a Fully Automated Flow-Based Instrument: Oxidation of Reduced Technetium Species in the Analysis of Total Technetium-99 in Caustic Aged Nuclear Waste Samples

Microwave-Assisted Sample Treatment in a Fully Automated Flow-Based Instrument: Oxidation of Reduced Technetium Species in the Analysis of Total Technetium-99 in Caustic Aged Nuclear Waste Samples

Preliminary Modeling Results of Evaporated Tc-Eluate Physical Properties

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

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