Extraction of heptavalent technetium from nuclear waste streams with 2-nitrophenyl octyl ether

2001 ◽  
Vol 89 (6) ◽  
Author(s):  
J. Chen ◽  
H. Boerrigter ◽  
A.C. Veltkamp
Keyword(s):  
Solvent Extraction ◽  
Nuclear Waste ◽  
Half Life ◽  
Separation Technique ◽  
Waste Streams ◽  
Octyl Ether ◽  
Nitrophenyl Octyl Ether

Technetium-99, in the form of Tc(VII), is one of major problems in the management and disposal of nuclear waste in view of its long half-life in combination with high geochemical mobility. Solvent extraction is an important separation technique to remove

Technetium(VII) transport across supported liquid membranes (SLMs) containing 2-nitrophenyl octyl ether (NPOE)

2001 ◽  
Vol 89 (8) ◽  
Author(s):  
J. Chen ◽  
H. Boerrigter ◽  
A.C. Veltkamp
Keyword(s):  
Half Life ◽  
Liquid Waste ◽  
Alkaline Solutions ◽  
Liquid Membranes ◽  
Fission Yield ◽  
Radioactive Liquid Waste ◽  
Supported Liquid Membranes ◽  
Octyl Ether ◽  
Nitrophenyl Octyl Ether ◽  
Key Issues

Technetium is one of key issues in the treatment of radioactive liquid waste because of its long half-life in combination with high fission yield and its geochemical mobility. For the removal of Tc(VII) from water and concentrated alkaline solutions, 2-nitrophenyl octyl ether (NPOE) is a very effective extractant. In this paper we describe the application of supported liquid membranes (SLMs) impregnated with NPOE for the removal of Tc(VII) from these solutions by using 1.5 M HNO

SREX: A NEWPROCESS FOR THE EXTRACTION AND RECOVERY OF STRONTIUM FROM ACIDIC NUCLEAR WASTE STREAMS

1991 ◽  
Vol 9 (1) ◽  
pp. 1-25 ◽  
Author(s):  
E. Philip Horwitz ◽  
Mark L. Dietz ◽  
Dan E. Fisher
Keyword(s):  
Nuclear Waste ◽  
Waste Streams

Coated Magnetic Nanoparticles for Acidic Nuclear Waste Separation

2010 ◽  
Vol 1265 ◽  
Author(s):  
Maninder Kaur ◽  
Hongmei Han ◽  
Andrew Johnson ◽  
Jesof Kaczor ◽  
Andrzej Paszczynski ◽  
...  
Keyword(s):  
Magnetic Nanoparticles ◽  
Solvent Extraction ◽  
Ion Exchange ◽  
Nuclear Waste ◽  
Cost Effective ◽  
Silica Coating ◽  
Coating Process ◽  
Acidic Conditions ◽  
Allylamine Hydrochloride ◽  
Waste Separation

AbstractActinide specific chelator (che) conjugated with magnetic nanoparticles (MNPs) have been developed to separate nuclear waste in acidic conditions. Compared to the traditional nuclear waste treatments, such as solvent extraction and ion exchange, this method is a simple, compact and cost-effective process that generates minimum secondary waste. In this paper, we focus on the coating process of MNPs to achieve a combination of good acidic resistance, high chelator loading density and efficient magnetic separation. An optimized silica coating process before conjugates chelator directly onto MNPs significantly improves the acidic resistance of the MNP-che complex. Chelator loading density is significantly increased by attaching a linear polyamine polymer poly(allylamine hydrochloride) (PAH) to the surface of the MNPs using chemical and physical approaches.

scholarly journals Facile incorporation of technetium into magnetite, magnesioferrite, and hematite by formation of ferrous nitrate in situ: precursors to iron oxide nuclear waste forms

2018 ◽  
Vol 47 (30) ◽  
pp. 10229-10239 ◽  
Author(s):  
Wayne W. Lukens ◽  
Sarah A. Saslow
Keyword(s):  
Iron Oxide ◽  
Fission Product ◽  
Nuclear Waste ◽  
Half Life ◽  
Fission Yield ◽  
Waste Forms ◽  
Nuclear Waste Forms

The fission product, 99Tc, presents significant challenges to the long-term disposal of nuclear waste due to its long half-life, high fission yield, and to the environmental mobility of pertechnetate (TcO4−), the stable Tc species in aerobic environments.

scholarly journals Removal of TcO4– from Representative Nuclear Waste Streams with Layered Potassium Metal Sulfide Materials

2016 ◽  
Vol 28 (11) ◽  
pp. 3976-3983 ◽  
Author(s):  
James J. Neeway ◽  
R. Matthew Asmussen ◽  
Amanda R. Lawter ◽  
Mark E. Bowden ◽  
Wayne W. Lukens ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Metal Sulfide ◽  
Waste Streams

Preparation of a Uranium Conversion Plant’s Nuclear Waste for Final Disposal by Means of Magnetically Assisted Chemical Separation

2013 ◽  
Vol 3 (1) ◽  
pp. 8-18
Author(s):  
Ahad Ghaemi ◽  
Mehdi Maghsudi ◽  
Fatemeh Hanifpour ◽  
Mohammad Samadfam
Keyword(s):  
Nitric Acid ◽  
Solvent Extraction ◽  
Nuclear Waste ◽  
Chemical Separation ◽  
Extraction Process ◽  
Uranium Content ◽  
Extraction Yield ◽  
Solvent Extraction Plant ◽  
Ft Ir ◽  
Co Precipitation

Uranium is separated from the raffinate of Isfahan’s uranium conversion solvent extraction process by means of solvent coated magnetic nanoparticles. These particles were synthesized via chemical co-precipitation and were analyzed by XRD, TEM and TGA methods. The particles’ surface were modified with D2EHPA and analyzed with FT-IR method. The results revealed that 0.5 M nitric acid and 25% w/w D2EHPA on nanoparticles gives the maximum uranium extraction yield. The raffinate of the solvent extraction plant can be disposed safely after its uranium content reduces to the allowable values.

scholarly journals A Recovery Process of Strontium from Acidic Nuclear Waste Streams

1997 ◽  
Vol 32 (10) ◽  
pp. 1725-1737 ◽  
Author(s):  
M. Draye ◽  
G. Le Buzit ◽  
J. Foos ◽  
A. Guy ◽  
B. Leclere ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Recovery Process ◽  
Waste Streams

scholarly journals Apatite- and Monazite-Bearing Glass-Crystal Composites for the Immobilization of Low-Level Nuclear and Hazardous Wastes

1995 ◽  
Vol 412 ◽  
Author(s):  
D. J. Wronkiewicz ◽  
S. F. Wolf ◽  
T. S. DiSanto
Keyword(s):  
Transition Metals ◽  
Nuclear Waste ◽  
Toxic Metals ◽  
Hazardous Wastes ◽  
Waste Streams ◽  
Waste Forms ◽  
Glass Crystal ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Crystal Composite

AbstractThis study demonstrates that glass-crystal composite waste forms can be produced from waste streams containing high proportions of phosphorus, transition metals, and/or halides. The crystalline phases produced in crucible-scale melts include apatite, monazite, spinels, and a Zr-Si-Fe-Ti phase. These phases readily incorporated radionuclide and toxic metals into their crystal structures, while corrosion tests have demonstrated that glass-crystal composites can be up to 300-fold more durable than simulated high-level nuclear waste glasses, such as SRL 202U.

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