Small-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102

Hassan, Neguib M.

doi:10.2172/759139

Cited by 18 publications

(29 citation statements)

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“…The lead and guard column breakthrough data indicate that the lead column removed virtually all of the pertechnetate, such that little pertechnetate actually reached the guard column. This is consistent with the lambda value predicted from the batch contact data, which indicated that the TcO 4 -breakthrough would not be observed until >196 BV of solution had been processed. ~70% Tc breakthrough was also observed for the small portion of the Envelope C sample using a 5.…”

Section: Superlig ® 639 Column Experimentssupporting

confidence: 88%

“…4 This report describes ion exchange testing conducted on the remaining larger portion (~18 L) of the Tank 241-AN-102 sample. The objectives of this study were as follows: Duration of the contact must be sufficient to achieve equilibrium or a constant comparative value must be used.…”

Section: Discussionmentioning

confidence: 99%

“…The concentration of nonpertechnetate forms of Tc was calculated for each sample based on the amount of extractable Tc in subsequent recontact tests. These calculations indicate that 37% of the Tc is TcO 4 -in the large Envelope C sample, while only 22% of the technetium in the small sample was in the extractable TcO 4 -form. This observation was surprising since the small and large portions of the Tank 241-AN-102 sample were treated similarly.…”

Section: Superlig ® 639 Batch Contact Experimentsmentioning

confidence: 93%

“…Relatively high concentrations of Ca, Cu, Cr, Ni, Pb and P were present in the cesium eluate. The P and Pb concentrations 4 Apparently, these species either absorb to specific resin sites or precipitate from the solution during ion exchange processing of Envelope C solution.…”

Section: Superlig ® 644 Column Experimentsmentioning

confidence: 99%

“…The theoretical 50% TcO 4 -breakthrough point (λ) for the large portion of the Env. C sample can be predicted from K d data and the swollen bulk resin density using Eqn.…”

Section: Superlig ® 639 Batch Contact Experimentsmentioning

confidence: 99%

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Intermediate-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102

King¹

2001

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Section: Superlig ® 639 Column Experimentssupporting

confidence: 88%

Section: Discussionmentioning

confidence: 99%

Section: Superlig ® 639 Batch Contact Experimentsmentioning

confidence: 93%

Section: Superlig ® 644 Column Experimentsmentioning

confidence: 99%

“…The theoretical 50% TcO 4 -breakthrough point (λ) for the large portion of the Env. C sample can be predicted from K d data and the swollen bulk resin density using Eqn.…”

Section: Superlig ® 639 Batch Contact Experimentsmentioning

confidence: 99%

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Intermediate-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102

King¹

2001

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Identification and Quantification of Technetium Species in Hanford Waste Tank AN-102

et al. 2020

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Technetium-99 (Tc), a high yield fission product generated in nuclear reactors, is one of the most difficult contaminants to address at the U.S. Department of Energy Hanford, Savannah River, and other sites. In strongly alkaline solutions typifying Hanford tank waste, Tc exists as pertechnetate (TcO 4 − ) (oxidation state VII) as well as in reduced forms (oxidation state < VII), collectively known as nonpertechnetate (non-TcO 4 − ) species. Designing strategies for effective Tc management, including separation and immobilization, necessitates understanding the molecular structure of the non-TcO 4 − species and their identification in actual tank waste samples. Identification of non-TcO 4 − species would facilitate the development of new treatment technologies effective for dissimilar Tc species. Toward this objective, a spectroscopic library of the Tc(I) [fac-Tc(CO) 3 ] + and Tc(II, IV, V, VII) compounds was generated and applied to the characterization of the actual Hanford AN-102 tank waste supernatant, which was processed to adjust Na concentration to ∼5.6 M and remove 137 Cs by spherical resorcinol-formaldehyde (sRF) ion-exchange resin. Post 137 Cs removal, the cesium-loaded sRF column was eluted with 0.45 M HNO 3 . As-received AN-102, Cs-depleted effluent, and sRF eluate fractions were comprehensively characterized for chemical composition and speciation of Tc using 99 Tc nuclear magnetic resonance spectroscopy and X-ray absorption spectroscopy. It was demonstrated for the first time that non-TcO 4 − Tc present in the AN-102 tank waste is composed of several low-valent Tc species, including the Tc(I) [fac-Tc(CO) 3 ] + and Tc(IV) compounds. This is the first demonstration of multiple non-TcO 4 − species co-existing in the Hanford tank waste, highlighting their importance for the waste processing.

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Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

Wilmarth

Lumetta

Johnson³

et al. 2011

Solvent Extraction and Ion Exchange

127

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Small-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102

Cited by 18 publications

References 0 publications

Intermediate-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102

Intermediate-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102

Identification and Quantification of Technetium Species in Hanford Waste Tank AN-102

Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

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