Column Performance Testing of SuperLig<sup>®</sup> 639 Resin with Simulated Hanford Waste Supernates: Identification of the Primary Sorbing Species and Detailed Characterization of Their Desorption Profiles

King, William D.; Spencer, William A.; Hamm, L.L.; Aleman, S.E.; Duffey, Cheryl; Pettis, Myra A.

doi:10.1081/ss-200042472

Cited by 11 publications

(5 citation statements)

References 14 publications

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“…Another elutable resin, SuperLig 639, − provided by IBC Advanced Technologies (American Forks, UT), has been comprehensively investigated to remove 99 Tc from Hanford tank waste simulants and actual tank waste supernate from laboratory-scale to pilot-scale. This resin is composed of functional crown ether groups grafted onto a polystyrene support (Figure ).…”

Section: Pertechnetate Separation Materialsmentioning

confidence: 99%

Separation and Remediation of ⁹⁹TcO₄^– from Aqueous Solutions

2019

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Technetium-99 (99Tc) is one of the most-problematic radioisotopes in used nuclear fuel owing to its intrinsic features of a high fission yield, long half-life, high environmental mobility, volatile nature during waste vitrification, and its redox interface capability with actinides during used fuel repossessing. The selective separation of pertechnetate (TcO4 –) from legacy nuclear waste and contaminated natural water is therefore highly desirable but still a significant challenge, because the conditions of a strong radiation field, high ionic strength, high acidity/alkalinity, and large amounts of competing anions are often involved in these systems. Until now, there are a handful of functional materials that can efficiently remove TcO4 – from nuclear waste solutions with high uptake capacities, fast kinetics, and good selectivity, but room still remains to further improve our capabilities for controlling the contamination/separation of TcO4 –. In this Perspective, we discuss the current state of the art TcO4 – separation materials including precipitation agents, reducing materials, ion-exchange resins, inorganic cationic frameworks, cationic metal–organic frameworks (MOFs), and cationic polymeric networks (CPNs) materials. The intriguing separation mechanisms of these materials for TcO4 – are also disclosed, which may hopefully shed light on further development in this field.

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Section: Pertechnetate Separation Materialsmentioning

confidence: 99%

Separation and Remediation of ⁹⁹TcO₄^– from Aqueous Solutions

2019

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“…Under oxidizing conditions in groundwater, the most common technetium oxidation states are Tc(IV) and Tc(VII) (8)(9)(10). The anion Tc(VII) is mobile (7,11).…”

Section: Introductionmentioning

confidence: 97%

“…Technetium is a long-lived beta emitter (the most common isotope, 99 Tc, has a 2x10 6 year half-life) that is a waste product from spent uranium fuel (1 kg technetium per ton of uranium enriched to 3% in 235 U) (6)(7)(8). Over 1990 kg of radioactive technetium was created from 1943 through 1987, with 1310±220 kg stored inside the Hanford sites single shell tanks (SSTs) and double shell tanks (DSTs) (7).…”

Section: Introductionmentioning

confidence: 99%

“…Over 1990 kg of radioactive technetium was created from 1943 through 1987, with 1310±220 kg stored inside the Hanford sites single shell tanks (SSTs) and double shell tanks (DSTs) (7). Technetium removal from the Hanford site tanks was stopped as this was considered a monumental task (8).…”

Section: Introductionmentioning

confidence: 99%

“…Technetium, in oxidizing conditions, is environmentally mobile and forms the soluble pertechnetate anion (TcO 4 -) upon atmospheric exposure (7,9). Under oxidizing conditions in groundwater, the most common technetium oxidation states are Tc(IV) and Tc(VII) (8)(9)(10). The anion Tc(VII) is mobile (7,11).…”

Section: Introductionmentioning

confidence: 99%

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Corrosion Behavior of Mild Steel Alloy A537 Used As Canister Material for Nuclear Waste Storage

Grant

Chidambaram

2013

ECS Trans.

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The interaction between mild steel nuclear waste storage containers and technetium ions is not well understood. Technetium is often found as an oxidized pertechnetate (TcO 4 -) anion at nuclear waste storage sites. This study is aimed at identifying whether TcO 4 -anions present a corrosion risk to mild steel nuclear waste storage tanks. The interaction of mild steel alloy A537 class 1 with rhenium, a technetium surrogate, was studied. Potentiodynamic polarization tests evaluated electrochemical behavior and the surface morphology was studied using scanning electron microscopy and optical microscopy. Potentiodynamic polarization experiments were conducted in 1.0M NaNO 3 + 0.1M NaOH and 1.0M NaNO 3 + 0.1M NaOH + 0.02M NaReO 4 . Three different temperatures were used in testing, namely, (i) ambient temperature, (ii) 50 o C and (iii) 80 o C. Sodium perrhenate was observed to inhibit the corrosion of the mild steel A537 samples. However, corrosion rates were found to increase with increasing temperatures both in the presence and absence of perrhenate.

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