Characterization of Electroactive Cs Ion-Exchange Materials using XAS

1996 ◽  
Vol 465 ◽  
Author(s):  
N. J. Hess ◽  
J. H. Sukamto ◽  
S. D. Rassat ◽  
R. T. Hallen ◽  
R. J. Orth ◽  
...  
Keyword(s):  
Ion Exchange ◽  
High Level Waste ◽  
Cubic Phase ◽  
Loaded State ◽  
Single Use ◽  
Exchange Resins ◽  
High Level ◽  
Initial Results ◽  
Deposition Conditions

ABSTRACTVarious ion exchange materials have been proposed for the removal of Cs from high level waste streams produced during the reprocessing of fuel rods. Cs can be released from loaded traditional exchange resins by elution and then the resin can be reused. However large quantities of secondary wastes are generated. Another class of “single use” exchangers is directly incorporated in the loaded state into a solid waste form (e.g. borosilicate glass logs). A third alternative is electroactive ion-exchange materials, where the uptake and elution of Cs are controlled by an applied potential. This approach has several advantages over traditional reusable ion-exchange resins including much reduced secondary waste, higher Cs selectivity, and higher durability.XAS experiments were conducted at the Fe K-edge and Cs Lm-edge on a series of electrochemically produced nickel ferrocyanide films to determine the effects of deposition conditions and subsequent alkali exchange on structural and chemical aspects of the films. The deposition conditions include methods described in the literature and PNNL proprietary procedures. Although the performance and the durability of the films do vary with processing conditions, Fe K-edge EXAFS results indicate that all deposition conditions result in the. formation of the cubic phase. Initial results from Cs Lm-edge EXAFS analysis suggest that the Cs ion is present as a hydrated species.

Supernatant Treatment Considerations for the Neutralized Waste at West Valley

1982 ◽  
Vol 15 ◽  
Author(s):  
G. B. Gockley ◽  
E. J. Lahoda ◽  
J. M. Pope
Keyword(s):  
New York ◽  
Ion Exchange ◽  
Nuclear Fuel ◽  
Laboratory Data ◽  
High Level Waste ◽  
Inorganic Ion ◽  
Treatment Considerations ◽  
Exchange Resins ◽  
High Level ◽  
Nuclear Fuel Reprocessing Plant

ABSTRACTThe neutralized high-level waste, stored at the Western New York Nuclear Service Center in West Valley, New York, was produced during the operation of the Nuclear Fuel Service, Inc. commercial nuclear fuel reprocessing plant. The supernatant is a highly concentrated salt solution (NaNO3 , NaOH, Na2SO4 and NaCl) containing essentially all of the dissolved cesium as the primary radioactive component. The sludge is primarily iron and aluminum hydroxides and contains strontium and the bulk of the long-lived isotopes. The supernatant will be treated to remove essentially all of the radioactivity and then be concentrated and disposed of as low level nuclear waste. The following supernatant treatment considerations have been evaluated on a laboratory scale using simulated West Valley waste: 1) Organic ion exchange resins; 2) Inorganic ion exchange media; 3) In-tank processing. These processes will be described and preliminary laboratory data will be presented.

THOR® Steam Reforming Technology for the Treatment of Ion Exchange Resins and More Complex Wastes Such as Fuel Reprocessing Wastes

2010 ◽  
Author(s):  
J. Brad Mason ◽  
Corey A. Myers
Keyword(s):  
Ion Exchange ◽  
Steam Reforming ◽  
Waste Treatment ◽  
Full Scale ◽  
Radioactive Wastes ◽  
High Level Waste ◽  
Ion Exchange Resins ◽  
Savannah River ◽  
Exchange Resins ◽  
High Level

The THOR® fluidized bed steam reforming process has been successfully operated for more than 10 years in the United States for the treatment of low- and intermediate-level radioactive wastes generated by commercial nuclear power plants. The principle waste stream that has been treated is ion exchange resins (IER) and Dry Active Waste (DAW), but various liquids, sludges, and solid organic wastes have also been treated. The principle advantages of the THOR® process include: (a) high volume reduction on the order of 5:1 to 10:1 for IER and up to 50:1 for high plastic content DAW streams depending on the waste type and waste characteristics, (b) environmentally compliant off-gas emissions, (c) reliable conversion of wastes into mineralized products that are durable and leach-resistant, and (d) no liquid effluents for treatment of most radioactive wastes. Over the past ten years, the THOR® process has been adapted for the treatment of more complex wastes including historic defense wastes, reprocessing wastes, and other wastes associated with the fuel cycle. As part of the U.S. Department of Energy (DOE) environmental remediation activities, the THOR® dual bed steam reforming process has successfully processed: (a) Idaho National Laboratory (INL) Sodium-Bearing Waste (SBW), (b) Savannah River Tank 48 High Level Waste (HLW), (c) Hanford Low Activity Waste (LAW), and (d) Hanford Waste Treatment Plant Secondary Waste (WTP-SW) liquid slurry simulants. The THOR® process has been shown in pilot plant operations to successfully process various simulated liquid, radioactive, nitrate-containing wastes into environmentally safe, leach-resistant, solid mineralized products. These mineralized products incorporate normally soluble ions (e.g. - Na, K, Cs, Tc), sulfates, chloride salts, and fluoride salts into an alkali alumino-silicate mineral matrix that inhibits the leaching of those ions into the environment. The solid mineralized products produced by the THOR® process exhibit durability and leach resistance characteristics superior to borosilicate waste glasses. As a result of this work, a full-scale THOR® process facility is currently under construction at the DOE’s Idaho site for the treatment of SBW and a full-scale facility is in the final design stage for the DOE’s Savannah River Site for the treatment of Tank 48 high level waste. Recent work has focused on the development of new monolithic waste formulations, the extension of the THOR® process to new waste streams, and the development of modular THOR® processes for niche waste treatment applications. This paper will provide an overview of current THOR® projects and summarize the processes and outcomes of the regulatory and safety reviews that have been necessary for the THOR® process to gain acceptance in the USA.

Tailored ion Exchange Resins for Combined Cesium and Strontium Removal From Soluble Srp High-Level Waste

1981 ◽  
Vol 6 ◽  
Author(s):  
Martha A. Ebra ◽  
Richard M. Wallace ◽  
Darrell D. Walker ◽  
Roice A. Wille
Keyword(s):  
Ion Exchange ◽  
High Level Waste ◽  
Ion Exchange Resins ◽  
Strontium Removal ◽  
Condensation Polymers ◽  
Exchange Resins ◽  
High Level ◽  
Chelating Groups ◽  
Column Performance

ABSTRACTNovel organic resins that achieve high selectivities for both cesium and strontium have been synthesized. They are condensation polymers of resorcinol and formaldehyde withattached chelating groups. Their column performance compares favorably with that of commercially available resins for either cesium or strontium removal. By combining Cs+ and Sr2+ removal in the same bed, these resins can significantly reduce the size and complexity of proposed facilities for processing defense high-level waste.

Preparation and characterization of vitrified glass matrix for high level waste from MOX fuel processing

2007 ◽  
Vol 353 (52-54) ◽  
pp. 4647-4653 ◽  
Author(s):  
V.S. Yalmali ◽  
D.S. Deshingkar ◽  
P.K. Wattal ◽  
S.R. Bharadwaj
Keyword(s):  
Glass Matrix ◽  
High Level Waste ◽  
Fuel Processing ◽  
Mox Fuel ◽  
High Level

Solventless synthesis of solketal with commercially available sulfonic acid based ion exchange resins and their catalytic performance

2017 ◽  
Vol 6 (1) ◽  
Author(s):  
Jesús Esteban ◽  
Félix García-Ochoa ◽  
Miguel Ladero
Keyword(s):  
Ion Exchange ◽  
Sulfonic Acid ◽  
Catalytic Performance ◽  
Maximum Activity ◽  
Ion Exchange Resins ◽  
Active Centers ◽  
Ease Of Access ◽  
Exchange Resins ◽  
Solventless Synthesis

AbstractAs a means to valorize glycerol, the synthesis of solketal through a ketalization reaction with acetone was performed. Mild solventless conditions were applied to test the activity of different commercially available sulfonic ion exchange resins that had already been used for other applications, namely: Amberlyst 35dry, Amberlyst 36dry, Purolite CT275DR, Purolite CT276 and Lewatit GF101. Thorough characterization of the resins is herein provided and discussed, including acidity, elemental analysis, thermogravimetric, 13C-NMR, surface area and pore size distribution measurements. Lewatit GF101 showed the best performance reaching a yield to solketal of 47% after 6 h of operation at 313 K using a molar excess of acetone to glycerol of 4.5 to 1, owing to a greater availability of active centers as well as the ease of access to them than in the rest of the resins. Additionally, reutilization with and without regeneration was performed in up to five cycles, showing that Purolite CT276 had the lowest relative drop of its maximum activity, despite being the least active in each of the cycles.

scholarly journals One-Step Steam Pyrolysis Preparation and Characterization of Spherical Carbon Adsorbents Obtained from Ion-Exchange Resins

2008 ◽  
Vol 26 (6) ◽  
pp. 407-413 ◽  
Author(s):  
Marek Wiśniewski ◽  
Agnieszka Pacholczyk ◽  
Gerhard Rychlicki ◽  
Artur P. Terzyk ◽  
Piotr A. Gauden
Keyword(s):  
Ion Exchange ◽  
Carbon Adsorbents ◽  
Ion Exchange Resins ◽  
Spherical Carbon ◽  
One Step ◽  
Exchange Resins
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