Investigations Into the Reusability of Amidoxime-Based Polymeric Uranium Adsorbents [electronic resource]
Amidoxime; Marine Sciences Laboratory.
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| Online Access: |
Online Access (via OSTI) |
|---|---|
| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
2016.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Investigations Into the Reusability of Amidoxime-Based Polymeric Uranium Adsorbents |h [electronic resource] |
| 260 | |a Washington, D.C. : |b United States. Department of Energy. ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 2016. | ||
| 300 | |a 39 p. : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through SciTech Connect. | ||
| 500 | |a 09/28/2016. | ||
| 500 | |a "pnnl--25874" | ||
| 500 | |a "AF5855000" | ||
| 500 | |a Li-Jung Kuo; Gary A. Gill; Jonathan E. Strivens; Jordana R. Wood; Nicholas J. Schlafer; Chien M. Wai; H. B. Pan. | ||
| 520 | 3 | |a Significant advancements in amidoxime-based polymeric adsorbents to extract uranium from seawater are achieved in recent years. The success of uranium adsorbent development can help provide a sustainable supply of fuel for nuclear reactors. To bring down the production cost of this new technology, in addition to the development of novel adsorbents with high uranium capacity and manufacture cost, the development of adsorbent re-using technique is critical because it can further reduce the cost of the adsorbent manufacture. In our last report, the use of high concentrations of bicarbonate solution (3M KHCO3) was identified as a cost-effective, environmental friendly method to strip uranium from amidoxime-based polymeric adsorbents. This study aims to further improve the method for high recovery of uranium capacity in re-uses and to evaluate the performance of adsorbents after multiple re-use cycles. Adsorption of dissolved organic matter (DOM) on the uranium adsorbents during seawater exposure can hinder the uranium adsorption and slow down the adsorption rate. An additional NaOH rinse (0.5 M NaOH, room temperature) was applied after the 3 M KHCO3 elution to remove natural organic matter from adsorbents. The combination of 3 M KHCO3 elution and 0.5 M NaOH rinse significantly improves the recovery of uranium adsorption capacity in the re-used adsorbents. In the first re-use, most ORNL adsorbents tested achieve ̃100% recovery by using 3 M KHCO3 elution + 0.5 M NaOH rinse approach, in comparison to 54% recovery when only 3 M KHCO3 elution was applied. A significant drop in capacity was observed when the adsorbents went through more than one re-use. FTIR spectra revealed that degradation of amidoxime ligands occurs during seawater exposure, and is more significant the longer the exposure time. Significantly elevated ratios of Ca/U and Mg/U in re-used adsorbents support the decrease in abundance of amidoxime ligands and increase carboxylate group from FT-IR analysis. The impact of the length of seawater exposure cycle in adsorbent re-use was evaluated by comparing the adsorption capacity for a common adsorbent formulation (ORNL AI8 formulation) under different exposure cycle (28 days and 42 days). Adsorbents with a 28 days seawater exposure cycle had higher recovery of uranium capacity than adsorbent with 42 days of seawater exposure. Under different cumulative seawater exposure time, the adsorbent with 28 days seawater exposure cycle also had less amidoxime ligands degradation than the adsorbent with 42 days seawater exposure cycle. These observations support the negative impact of prolonged seawater exposure on amidoxime ligands stability. Recovery of uranium capacity in re-uses also varies across different adsorbent formulations. Among three different ORNL adsorbents tested (AI8, AF8, AF1-DMSO), AI8 had the best recovery in each re-use, followed by AF8 and then AF1-DMSO. This demonstrates that continuing efforts on developing new adsorbents with high capacity and stability is critical. The overall performance of adsorbents in multiple re-use cycles can be evaluated by calculation total harvestable uranium, the summation of adsorbed uranium from each seawater exposure cycle. In this assessment, the ORNL AI8 braid with 28 days seawater exposure cycle can reach total harvestable uranium 10g Uranium/kg adsorbent in ̃140 days; while the same type of braid but with 42 days seawater exposure cycle reach the same level in ̃170 days. Notably, the performance of total harvestable uranium also varies among different adsorbent formulations (AI8 > AF1-DMSO > AF8). Short seawater exposure cycle is associated with high re-use frequency. The development of low-cost offshore adsorbent deployment/extraction is essential for high frequency reuse operation. This study also highlights the importance to examine the re-use performance of newly developed uranium adsorbents for selection of optimal adsorbents for ocean deployment. | |
| 520 | 0 | |a Amidoxime; Marine Sciences Laboratory. | |
| 536 | |b AC05-76RL01830. | ||
| 650 | 7 | |a Uranium. |2 local. | |
| 650 | 7 | |a Materials Recovery. |2 local. | |
| 650 | 7 | |a Extraction. |2 local. | |
| 650 | 7 | |a Amides. |2 local. | |
| 650 | 7 | |a Oximes. |2 local. | |
| 650 | 7 | |a Organic Polymers. |2 local. | |
| 650 | 7 | |a Seawater. |2 local. | |
| 650 | 7 | |a Sodium Hydroxides. |2 local. | |
| 650 | 7 | |a Adsorbents. |2 local. | |
| 650 | 7 | |a Adsorption. |2 local. | |
| 650 | 7 | |a Capacity. |2 local. | |
| 650 | 7 | |a Comparative Evaluations. |2 local. | |
| 650 | 7 | |a Elutriation. |2 local. | |
| 650 | 7 | |a Rinsing. |2 local. | |
| 650 | 7 | |a Decomposition. |2 local. | |
| 650 | 7 | |a Time Dependence. |2 local. | |
| 650 | 7 | |a Organic Matter. |2 local. | |
| 650 | 7 | |a Ligands. |2 local. | |
| 650 | 7 | |a Performance. |2 local. | |
| 650 | 7 | |a Temperature Range 0273-0400 K. |2 local. | |
| 650 | 7 | |a Concentration Ratio. |2 local. | |
| 650 | 7 | |a Stability. |2 local. | |
| 650 | 7 | |a Potassium Compounds. |2 local. | |
| 650 | 7 | |a Acid Carbonates. |2 local. | |
| 650 | 7 | |a Radiation Chemistry, Radiochemistry, And Nuclear Chemistry. |2 edbsc. | |
| 650 | 7 | |a Nuclear Fuel Cycle And Fuel Materials. |2 edbsc. | |
| 710 | 2 | |a Pacific Northwest National Laboratory (U.S.). |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
| 856 | 4 | 0 | |u http://www.osti.gov/scitech/biblio/1330925 |z Online Access (via OSTI) |
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| 952 | f | f | |p Can circulate |a University of Colorado Boulder |b Online |c Online |d Online |e E 1.99:pnnl--25874 |h Superintendent of Documents classification |i web |n 1 |