Review and assessment of technologies for the separation of strontium from alkaline and acidic media

Orth, R.J.; Kurath, D.E.

doi:10.2172/10134949

Cited by 14 publications

(6 citation statements)

References 29 publications

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“…The actual waste contains 2.16 g C L-' TOC, while no organics were added to the simulant due to a lack of compositional analysis. The exact nature of these organics is not known but may consist of complexants capable of binding strontium k such a form (chelated anionic metal complex) that is difficult to remove by these cationic ion exchange materials , M&h et al 1995, Orth and Kurath 1993, Samuelson 1953, Samuelson 1963.…”

Section: 17mentioning

confidence: 99%

Comparison of organic and inorganic ion exchangers for removal of cesium and strontium from simulated and actual Hanford 241-AW-101 DSSF tank waste

Brown¹,

Bray²,

Carlson³

1996

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Section: 17mentioning

confidence: 99%

Comparison of organic and inorganic ion exchangers for removal of cesium and strontium from simulated and actual Hanford 241-AW-101 DSSF tank waste

Brown¹,

Bray²,

Carlson³

1996

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“…On the other hand, removal of strontium from high ionic strength solutions dominated by sodium ions has been studied. For example, years of studies on separation and purification of strontium from high-level waste stored in underground tanks at Hanford, WA, produced successful precipitation methods (e.g., lead sulfate, ferric hydroxide, calcium carbonate), solvent extraction (e.g., using di-2-ethylhexyl phosphoric acid or novel heterocyclic compounds such as dicyclohexano-18-crown-6), and ion exchange (e.g., antimonic acid, titanates) (see Schulz and Bray 1987;Orth and Kurath 1994). More recently, Morimoto et al (2011) reported the use of magnesium vermiculite from South Africa that could not retain Sr 2+ in the presence of 3% sodium ion, but upon removal of the sodium via an upstream tetraethylammonium ion exchanger, Sr 2+ could be retained well in column experiments.…”

Section: Resultsmentioning

confidence: 99%

Evaluating Solid Sorbents for Recycling Wash Waters Containing Strontium and Calcium

Oster

Kaminski

Jerden

et al. 2019

J. Hazard. Toxic Radioact. Waste

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A system for rapid reduction of radioactive contamination and recycle of contaminated waters is called the Integrated Wash-Aid, Treatment, and Emergency Reuse System (IWATERS). First developed for cesium contaminations, IWATERS prescribes the use of salt and surfactant additives to decontaminate radionuclides from urban surfaces. The water is collected and recycled after passing through reactive filtration beds containing selective sorbents. To adapt the IWATERS for strontium contaminations, potential additives to enhance its decontamination from urban surfaces are identified. One possible additive is calcium (Ca 2+ ). However, its concentration can have a very strong detrimental effect on the ability of selective sorbents to remove strontium from spent wash water. We recognized that studies on off-the-shelf sorbents that include Ca 2+ concentrations at relevant levels (greater than millimolar) are absent in the literature. To understand better the effect of Ca 2+ , we completed a literature review, batch tests, and surface complexation modeling to reveal few sorbent options. Only silico-titanate sorbents exhibited high K d values in the presence of Ca 2+ , but have significant drawbacks in cost and availability. Given the state of the art, it is imperative that alternatives to alkaline earth ions in the IWATERS be identified to permit in situ recycle of the wash waters.

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“…A number of possible techniquesfor the basic side removal of TRUs and strontiumhave been identified (Orth and Kurath 1993;Kolaric 1991). Precipitationmethods are the most promisingof the processes identified.…”

Section: -29mentioning

confidence: 99%

Annual report of tank waste treatability

Barker

Lane

1993

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This report has been prepared as part of the Hanford Federal Facility Agreement and Consent Order* (Tri-PartyAgreement)and constitutescompletion of Tri-Party Agreement milestone M-O4-OODfor Fiscal year 1993. This report provides a summary of treatmentactivitiesfor newly generatedwaste, existing double-shell tank waste, and existing single-shell tank waste, as well as a summary of grout disposal feasibility, glass disposal feasibility, alternate methods for disposal, and safety issues which may impact the treatment and disposal of existing defense nuclear wastes.

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Review and assessment of technologies for the separation of strontium from alkaline and acidic media

Cited by 14 publications

References 29 publications

Comparison of organic and inorganic ion exchangers for removal of cesium and strontium from simulated and actual Hanford 241-AW-101 DSSF tank waste

Comparison of organic and inorganic ion exchangers for removal of cesium and strontium from simulated and actual Hanford 241-AW-101 DSSF tank waste

Evaluating Solid Sorbents for Recycling Wash Waters Containing Strontium and Calcium

Annual report of tank waste treatability

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