Reactivity of Resorcinol Formaldehyde Resin with Nitric Acid

King, William D.; Fondeur, F. F.; Wilmarth, W.R.; Pettis, Myra E.; McCollum, Shirley W.

doi:10.1080/01496390600743151

Cited by 9 publications

(4 citation statements)

References 9 publications

(9 reference statements)

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“…) would occur as they all would exit the CsIX column. We also note that the RF resin is highly susceptible to degradation in strong HNO 3 (King et al 2006). The plutonium concentration available in solution again would be limited to ~0.02 g/L.…”

Section: +mentioning

confidence: 75%

Effects Influencing Plutonium-Absorber Interactions and Distributions in Routine and Upset Waste Treatment Plant Operations

Delegard

Sinkov

Fiskum

2015

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Permanganate Effects -The solubilities of (hydr)oxide compounds of aluminum, cadmium, chromium, iron, and uranium (but not manganese and nickel), and of plutonium itself, increase with alkaline concentration and thus help preserve the plutonium/absorber ratio in solution. However, the ratio may be altered in permanganate oxidative dissolution of discrete plutonium phases such as PuO 2 ,PuO 2 •xH 2 O, or other low-solubility tetravalent plutonium because of oxidation to more soluble pentavalent or hexavalent plutonium. The ratio also may be altered because of oxidative leaching of Cr(III) phases while compounds of other absorber elements (e.g., aluminum, iron, nickel) are largely redox-indifferent. Plutonium dissolution from genuine washed sludge with permanganate is significantly enhanced by an increase in NaOH concentration, increasing by an average factor of 70 when permanganate oxidative leaching is undertaken at 3 M NaOH as compared with 0.1 or 0.25 M NaOH. The increase is likely due to plutonium being more readily oxidized to the more soluble hexavalent state. Dissolved plutonium species in alkaline solution, irrespective of oxidation state, are anionic so they are not expected to sorb onto the cation-sorbing resin used for 137 Cs removal. Indeed, such sorption is observed to be negligible. Excess permanganate does not appear to have an appreciable effect on the distribution of plutonium to solution based on oxidative leaching of REDOX Process sludge simulants and genuine Cr(III)-bearing Hanford tank sludges. In lab testing, intentional over-dosage of permanganate did not lead to enhanced plutonium leaching at lower alkalinity (0.09 to 0.25 M NaOH), while at higher alkalinity (3 M NaOH), the plutonium concentration increase to ~0.00036 g Pu/L was relatively low and could be mitigated by adding Cr(III) nitrate to the permanganate/manganate-bearing slurry to eliminate excess oxidant, form MnO 2 , and remove ~95% of the solubilized plutonium by coprecipitation. Separate testing showed that plutonium dissolution in the presence of excess permanganate at 2 to 4 M NaOH also can be mitigated by addition of hydrogen peroxide, removing ~75% of the solubilized plutonium. In treatment with Sr/Mn(VII) for 90 Sr and transuranic element removal from Envelope C supernates, both coprecipitated plutonium that remains undissolved and the residual soluble plutonium, should be protected with 100 to 1000 times higher neutron absorber concentrations based on AN-102 supernate studies. Although experimental data on 239 Pu decontamination from AN-107 supernates are lacking, it is likely that plutonium decontamination by Sr/Mn(VII) treatment was similar to that of AN-102 supernates based on solution composition and total alpha analyses. Decontamination of tank SY-101 from dissolved plutonium by permanganate treatment also is found. Overall, treatment of Envelope C wastes by Sr/Mn(VII) should improve criticality safety by carrying plutonium into the solid phase in the presence of co-precipitated iron and especially manganese.Cerium an...

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Section: +mentioning

confidence: 75%

Effects Influencing Plutonium-Absorber Interactions and Distributions in Routine and Upset Waste Treatment Plant Operations

Delegard

Sinkov

Fiskum

2015

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“…Solutions of HNO 3 were used for the desorption of Cs-137. One should mention that, at room temperature, 2.0-3.0 M solutions of HNO 3 lead to changes in RFR after 24 h due to its nitration [38]. Nitration of RFRs with 0.5-1.0 M HNO 3 solutions occurs when heated to 55 • C or after prolonged exposure for 70 days [38,39].…”

Section: Resultsmentioning

confidence: 99%

“…One should mention that, at room temperature, 2.0-3.0 M solutions of HNO 3 lead to changes in RFR after 24 h due to its nitration [38]. Nitration of RFRs with 0.5-1.0 M HNO 3 solutions occurs when heated to 55 • C or after prolonged exposure for 70 days [38,39]. Nitration of RFRs is accompanied by the destruction of the polymer matrix as well as a decrease in the sorption capacity [40].…”

Section: Resultsmentioning

confidence: 99%

Removal of Cs-137 from Liquid Alkaline High-Level Radwaste Simulated Solution by Sorbents of Various Classes

Milyutin,

Nekrasova,

Kozlov

et al. 2023

Sustainability

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The present work describes the results of the removal of cesium by sorbents of various classes from highly mineralized alkaline solutions simulating the clarified phase of storage tanks with high-level radioactive waste (HLW) of the Mayak Production Association. Within the scope of the performed works, inorganic sorbents of the Clevasol® and Fersal brands, as well as resorcinol-formaldehyde ion-exchange resins (RFRs: RFR-i, RFR-Ca, and Axionit RCs), were used. The sorbents’ characteristics under both static and dynamic conditions are presented. The Fersal sorbent has demonstrated the best sorption characteristics in the series of sorbents under study. The disadvantage of inorganic sorbents is the loss of mechanical strength upon cesium desorption, which complicates their repeated use. It has been demonstrated that RFRs, despite their lower selectivity towards cesium and adsorption capacity, can be used many times in repeated sorption-desorption cycles. The latter makes RFRs more technologically attractive in terms of the total volume of decontaminated HLW. However, RFRs tend to be oxidized during storage, which results in the formation of carboxyl groups and a decrease in sorption characteristics—this must be further taken into account in the real processes of liquid radioactive waste (LRW) management.

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“…The significant difference between the resins was their matrices. Only Duolite A7 resin had a phenol formaldehyde matrix or Bakelite matrix known to be susceptible to oxidative degradation . As can be seen in Figure S1, Duolite A7 consists of −OH and −NH 2 functional groups, both of which are known to be significant electron donors. − Thus, the phenol formaldehyde polymer matrix of Duolite A7 was most probably the electron donor for eq reduction reaction.…”

Section: Results and Discussionmentioning

confidence: 99%

Trace Cr(VI) Removal: Evidence of Redox-Active Ion Exchange by a Weak-Base Anion Exchanger

Verma

Sarkar

2020

Ind. Eng. Chem. Res.

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The presence of Cr(VI) in water, even in trace concentrations, is toxic to numerous animals, plants, and microorganisms. Remediation efforts require selective removal of trace concentrations of Cr(VI) anions from the background of other competing ions present in concentrations at least 2 orders of magnitude greater than Cr(VI). The objective of this study was to evaluate the trace Cr(VI) removal capacities of commonly available anion exchangers. Batch and column studies revealed that Duolite A7 showed extraordinarily high Cr(VI) removal capacity compared to other anion exchangers. For a synthetic influent solution containing trace Cr(VI) at pH 5, Duolite A7 removed Cr(VI) for 30 000 bed volumes (BVs), while the columns having other anion exchangers reached breakthrough almost instantaneously less than 1000 BVs. Equilibrium and kinetic studies were performed on Duolite A7 at varying pH and contact time, coupled with characterization studies on the raw and exhausted ion exchanger to elucidate the mechanism behind such a significantly higher Cr(VI) removal. Based on the results, it was concluded that there was an occurrence of redox reaction within the resin in addition to ion exchange because of the unique resin composition. Duolite A7 is a weak-base anion exchange resin with a phenol formaldehyde matrix, and both secondary and tertiary amine functional groups. The redox reactions resulted in the perpetual regeneration of ion exchange sites and 30× greater Cr(VI) removal capacity of Duolite A7. This finding may pave the way to design a new class of redoxactive ion exchangers for various water and wastewater treatment applications.

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Reactivity of Resorcinol Formaldehyde Resin with Nitric Acid

Cited by 9 publications

References 9 publications

Effects Influencing Plutonium-Absorber Interactions and Distributions in Routine and Upset Waste Treatment Plant Operations

Effects Influencing Plutonium-Absorber Interactions and Distributions in Routine and Upset Waste Treatment Plant Operations

Removal of Cs-137 from Liquid Alkaline High-Level Radwaste Simulated Solution by Sorbents of Various Classes

Trace Cr(VI) Removal: Evidence of Redox-Active Ion Exchange by a Weak-Base Anion Exchanger

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