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Journal articles on the topic 'Dmdohema'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 February 2022

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1

Weßling, Patrik, Michael Trumm, Andreas Geist, and Petra J. Panak. "Stoichiometry of An(iii)–DMDOHEMA complexes formed during solvent extraction." Dalton Transactions 47, no. 32 (2018): 10906–14. http://dx.doi.org/10.1039/c8dt02504e.

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2

Ebert, Elena L., Andrey Bukaemskiy, Fabian Sadowski, Steve Lange, Andreas Wilden, and Giuseppe Modolo. "Reprocessability of molybdenum and magnesia based inert matrix fuels." Nukleonika 60, no. 4 (December 1, 2015): 871–78. http://dx.doi.org/10.1515/nuka-2015-0124.

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Abstract This work focuses on the reprocessability of metallic 92Mo and ceramic MgO, which is under investigation for (Pu,MA)-oxide (MA = minor actinide) fuel within a metallic 92Mo matrix (CERMET) and a ceramic MgO matrix (CERCER). Magnesium oxide and molybdenum reference samples have been fabricated by powder metallurgy. The dissolution of the matrices was studied as a function of HNO3 concentration (1-7 mol/L) and temperature (25-90°C). The rate of dissolution of magnesium oxide and metallic molybdenum increased with temperature. While the MgO rate was independent of the acid concentration (1-7 mol/L), the rate of dissolution of Mo increased with acid concentration. However, the dissolution of Mo at high temperatures and nitric acid concentrations was accompanied by precipitation of MoO3. The extraction of uranium, americium, and europium in the presence of macro amounts of Mo and Mg was studied by three different extraction agents: tri-n-butylphosphate (TBP), N,Nʹ-dimethyl-N,Nʹ-dioctylhexylethoxymalonamide (DMDOHEMA), and N,N,N’,N’- -tetraoctyldiglycolamide (TODGA). With TBP no extraction of Mo and Mg occurred. Both matrix materials are partly extracted by DMDOHEMA. Magnesium is not extracted by TODGA (D < 0.1), but a weak extraction of Mo is observed at low Mo concentration.

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3

Petit, S., L. Bertolo, F. Petitjean, C. Marie, O. Conocar, and V. Thiebaut. "TEHDGA, DMDOHEMA and Mixed Sorbents: Characterization and Am(III) Uptake Properties." Procedia Chemistry 21 (2016): 9–16. http://dx.doi.org/10.1016/j.proche.2016.10.002.

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4

Pacary, Vincent, Fabien Burdet, and Marie-Thérèse Duchesne. "Experimental and Modeling of Extraction of Lanthanides in System HNO3-TEDGA-{DMDOHEMA-HDEHP}." Procedia Chemistry 7 (2012): 328–33. http://dx.doi.org/10.1016/j.proche.2012.10.052.

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5

Marie, Cécile, Vincent Vanel, Sou Watanabe, Marie-Thérèse Duchesne, Nicole Zorz, and Laurence Berthon. "Behavior of Molybdenum (VI) in {DMDOHEMA–HDEHP/nitric acid} Liquid–Liquid Extraction Systems." Solvent Extraction and Ion Exchange 34, no. 5 (July 2016): 407–21. http://dx.doi.org/10.1080/07366299.2016.1208029.

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6

Carrot, M. J., C. R. Gregson, and R. J. Taylor. "Neptunium Extraction and Stability in the GANEX Solvent: 0.2 M TODGA/0.5 M DMDOHEMA/Kerosene." Solvent Extraction and Ion Exchange 31, no. 5 (October 11, 2012): 463–82. http://dx.doi.org/10.1080/07366299.2012.735559.

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7

Patil, Ajay B., Pankaj Kandwal, V. S. Shinde, P. N. Pathak, and P. K. Mohapatra. "Evaluation of DMDOHEMA based supported liquid membrane system for high level waste remediation under simulated conditions." Journal of Membrane Science 442 (September 2013): 48–56. http://dx.doi.org/10.1016/j.memsci.2013.04.019.

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8

Poirot, Rémi, Damien Bourgeois, and Daniel Meyer. "Palladium Extraction by a Malonamide Derivative (DMDOHEMA) from Nitrate Media: Extraction Behavior and Third Phase Characterization." Solvent Extraction and Ion Exchange 32, no. 5 (June 6, 2014): 529–42. http://dx.doi.org/10.1080/07366299.2014.908587.

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9

Geist, Andreas, Laurence Berthon, Marie-Christine Charbonnel, and Udo Müllich. "Extraction of Nitric Acid, Americium(III), Curium(III), and Lanthanides(III) into DMDOHEMA Dissolved in Kerosene." Solvent Extraction and Ion Exchange 38, no. 7 (July 21, 2020): 681–702. http://dx.doi.org/10.1080/07366299.2020.1794523.

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10

Usma, Cesar L., S. Dourdain, G. Arrachart, and S. Pellet-Rostaing. "Solvent extraction of rare earths elements from nitrate media in DMDOHEMA/ionic liquid systems: performance and mechanism studies." RSC Advances 11, no. 50 (2021): 31197–207. http://dx.doi.org/10.1039/d1ra05359k.

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Extraction of La(iii), Eu(iii) and Fe(iii) was compared in n-dodecane and in two ionic liquids (ILs) [EBPip+] [NTf2−] and [EOPip+] [NTf2−]. Extraction mechanisms have been investigated as a function of pH.

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11

Van Hecke, K., and G. Modolo. "Separation of actinides from Low Level Liquid Wastes (LLLW) by extraction chromatography using novel DMDOHEMA and TODGA impregnated resins." Journal of Radioanalytical and Nuclear Chemistry 261, no. 2 (2004): 269–75. http://dx.doi.org/10.1023/b:jrnc.0000034858.26483.ae.

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12

Patil, Ajay B., Vaishali S. Shinde, P. N. Pathak, P. K. Mohapatra, and V. K. Manchanda. "Modified synthesis scheme forN,N´-dimethyl-N,N´-dioctyl-2,(2´-hexyloxyethyl) malonamide (DMDOHEMA) and its comparison with proposed solvents for actinide partitioning." Radiochimica Acta 101, no. 2 (February 2013): 93–100. http://dx.doi.org/10.1524/ract.2013.1998.

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13

Malmbeck, Rikard, Daniel Magnusson, Stéphane Bourg, Michael Carrott, Andreas Geist, Xavier Hérès, Manuel Miguirditchian, et al. "Homogenous recycling of transuranium elements from irradiated fast reactor fuel by the EURO-GANEX solvent extraction process." Radiochimica Acta 107, no. 9-11 (September 25, 2019): 917–29. http://dx.doi.org/10.1515/ract-2018-3089.

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Abstract The EURO-GANEX process was developed for co-separating transuranium elements from irradiated nuclear fuels. A hot flow-sheet trial was performed in a counter-current centrifugal contactor setup, using a genuine high active feed solution. Irradiated mixed (carbide, nitride) U80Pu20 fast reactor fuel containing 20 % Pu was thermally treated to oxidise it to the oxide form which was then dissolved in HNO3. From this solution uranium was separated to >99.9 % in a primary solvent extraction cycle using 1.0 mol/L DEHiBA (N,N-di(2-ethylhexyl)isobutyramide in TPH (hydrogenated tetrapropene) as the organic phase. The raffinate solution from this process, containing 10 g/L Pu, was further processed in a second cycle of solvent extraction. In this EURO-GANEX flow-sheet, TRU and fission product lanthanides were firstly co-extracted into a solvent composed of 0.2 mol/L TODGA (N,N,N′,N′-tetra-n-octyl diglycolamide) and 0.5 mol/L DMDOHEMA (N,N′-dimethyl-N,N′-dioctyl-2-(2-hexyloxy-ethyl) malonamide) dissolved in Exxsol D80, separating them from most other fission and corrosion products. Subsequently, the TRU were selectively stripped from the collected loaded solvent using a solution containing 0.055 mol/L SO3-Ph-BTP (2,6-bis(5,6-di(3-sulphophenyl)-1,2,4-triazin-3-yl)pyridine tetrasodium salt) and 1 mol/L AHA (acetohydroxamic acid) in 0.5 mol/L HNO3; lanthanides were finally stripped using 0.01 mol/L HNO3. Approximately 99.9 % of the TRU and less than 0.1 % of the lanthanides were found in the product solution, which also contained the major fractions of Zr and Mo.

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14

Carrott, Michael, Andreas Geist, Xavier Hères, Steve Lange, Rikard Malmbeck, Manuel Miguirditchian, Giuseppe Modolo, Andreas Wilden, and Robin Taylor. "Distribution of plutonium, americium and interfering fission products between nitric acid and a mixed organic phase of TODGA and DMDOHEMA in kerosene, and implications for the design of the “EURO-GANEX” process." Hydrometallurgy 152 (February 2015): 139–48. http://dx.doi.org/10.1016/j.hydromet.2014.12.019.

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15

Serrano-Purroy, Daniel, P. Baron, Birgit Christiansen, R. Malmbeck, C. Sorel, and J. P. Glatz. "Recovery of minor actinides from HLLW using the DIAMEX process." Radiochimica Acta 93, no. 6 (January 1, 2005). http://dx.doi.org/10.1524/ract.93.6.351.65642.

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16

Myasoedov, B. F., T. A. Maryutina, M. N. Litvina, D. A. Malikov, Yu M. Kulyako, B. Ya Spivakov, Clement Hill, J. M. Adnet, M. Lecomte, and Charles Madic. "Americium(III)/curium(III) separation by countercurrent chromatography using malonamide extractants." Radiochimica Acta 93, no. 1 (January 1, 2005). http://dx.doi.org/10.1524/ract.93.1.9.58300.

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AbstractThe separation of Am(III) and Cm(III) by countercurrent chromatography (CCC) was achieved using the liquid phase systems "diamide–hydrogenated tetrapropylene (TPH)–HNOThe following diamide extractants have been studied: (i) N,N´-dimethyl-N,N´-dibutyltetradecylmalonamide (DMDBTDMA), (ii) N,N´-dimethyl-N,N´-dioctylhexyl-ethoxymalonamide (DMDOHEMA) and (iii) N,N´-dimethyl-N,N´-dibutyldodecylethoxymalonamide (DMDBDDEMA). It is shown that these diamides can be used for the separation of Am(III) and Cm(III) by CCC. Increasing the column length leads to an increase of the stationary phase retention on the column while improving the Am/Cm separation. Increasing the speed of rotation of the centrifuge from 660 to 950 rpm also results in increasing the stationary phase retention but does not influence the resolution of the Am/Cm separation. Decreasing the flow rate of the mobile phase from 1.0 to 0.5 mL/min leads to a better resolution of Am and Cm separation. The best Am/Cm separation was achieved with systems based on DMDBDDEMA and DMDOHEMA in TPH using a two-layer coil column and an isocratic elution mode. The application of CCC makes it possible to separate the elements within 100 min: the Cm fraction contains 99.5% of Cm(III) and 0.6% of Am(III) inventories and the Am fraction contains 99.4% of Am(III) and 0.5% of Cm(III).

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