Selection and design criteria of supported liquid membrane for the treatment of rad-waste
19 May 2011-International Journal of Nuclear Desalination (Inderscience Publishers)-Vol. 4, Iss: 3, pp 248-260
TL;DR: In this paper, the authors presented the basic views of SLM, selection of carrier by experimental verification with respect to both feed and strippant for further processing, and structural aspects with evidences (from FT-IR studies).
Abstract: Supported Liquid Membrane (SLM) is an emerging trace metal pre-concentration technique. It has the ability to decontaminate radionuclides even from lean secondary effluent. SLM can be considered as a part of process intensification, which implies a closed loop operation. It has reduced space requirement as well as minimised secondary effluent generation and the number of unit steps. Proper selection of molecular design criteria helps in deciding performances such as selectivity, compatibility, permeability, etc., that is attributed to both feed and desired strippant characteristics, and great effort has been applied for nuclear plant waste treatment generated in the uranium metal plant of Trombay, India. This paper articulates basic views of SLM, selection of carrier by experimental verification with respect to both feed and strippant for further processing, and structural aspects with evidences (from FT-IR studies).
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10 Apr 2018
TL;DR: In this paper, the authors have discussed the necessity of uranium concentration quantification for recovery as well as safe disposal of plant effluent, working mechanism of voltammeter w.r.t.
Abstract: Determining uranium in ppb level is considered to be most crucial for reuse of water originated in nuclear industries at the time of decontamination of plant effluents generated during uranium (fuel) production, fuel rod fabrication, application in nuclear reactors and comparatively small amount of effluents obtained during laboratory research and developmental work. Higher level of uranium in percentage level can be analyzed through gravimetry, titration etc, whereas inductively coupled plasma-atomic energy spectroscopy (ICP-AES), fluorimeter are well suited for ppm level. For ppb level of uranium, inductively coupled plasma - mass spectroscopy (ICP-MS) or Differential Pulse Anodic Stripping Voltammetry (DPASV) serve the purpose. High precision, accuracy and sensitivity are the crucial for uranium analysis in trace (ppb) level, which are satisfied by ICP-MS and stripping voltammeter. Voltammeter has been found to be less expensive, requires low maintenance and is convenient for measuring uranium in presence of large number of other ions in the waste effluent. In this paper, necessity of uranium concentration quantification for recovery as well as safe disposal of plant effluent, working mechanism of voltammeter w.r.t. uranium analysis in ppb level with its standard deviation and a data comparison with ICP-MS has been represented.Determining uranium in ppb level is considered to be most crucial for reuse of water originated in nuclear industries at the time of decontamination of plant effluents generated during uranium (fuel) production, fuel rod fabrication, application in nuclear reactors and comparatively small amount of effluents obtained during laboratory research and developmental work. Higher level of uranium in percentage level can be analyzed through gravimetry, titration etc, whereas inductively coupled plasma-atomic energy spectroscopy (ICP-AES), fluorimeter are well suited for ppm level. For ppb level of uranium, inductively coupled plasma - mass spectroscopy (ICP-MS) or Differential Pulse Anodic Stripping Voltammetry (DPASV) serve the purpose. High precision, accuracy and sensitivity are the crucial for uranium analysis in trace (ppb) level, which are satisfied by ICP-MS and stripping voltammeter. Voltammeter has been found to be less expensive, requires low maintenance and is convenient for measuring uranium in prese...
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TL;DR: In this article, a review of the works performed in the Separation Chemistry Group of the Chemistry Division of Argonne National Laboratory on the transport and separation properties of supported liquid membranes (SLM) is presented.
Abstract: The works performed in the Separation Chemistry Group of the Chemistry Division of Argonne National Laboratory on the transport and separation properties of supported liquid membranes (SLM) are reviewed. The models and equations which describe the permeation through SLMs of metal species are described. These models have been tested with various carriers absorbed on flat-sheet and hollow-fiber SLMs by measuring the permeation of several metal species of hydrometallurgical and nuclear interest. An equation for the separation factor of metal species in SLM processes and examples of separations of metal ions are reported. The possibility of bypassing the single stage character of SLM separations by using multilayer composite SLMs, arranged in series, is also analyzed. Finally, the factors which control the stability of SLMs are briefly discussed.
563 citations
"Selection and design criteria of su..." refers background in this paper
...Various liquid membrane processes are now finding use (Sifniades et al., 1981; Danesi, 1984; IAEA, 2004; Mohapatra and Manchanda, 2009) in the treatment of large volumes of low-level radioactive liquid effluents generated in the various stages of nuclear fuel cycle of the nuclear industry....
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TL;DR: In this article, a carrier-facilitated transport of uranium (VI) against its concentration gradient from aqueous nitrate acidic solutions across an organic bulk liquid membrane (BLM) and flat-sheet supported liquid membranes (SLM) containing tributyl phosphate (TBP) as the mobile carrier and dodecane as the membrane solvent has been investigated.
47 citations
"Selection and design criteria of su..." refers methods in this paper
...As an innovative and most challenging application, the process (SLM) can be used (Shukla and Misra, 1991; Shailesh et al., 2006; Shailesh et al., 2008) for metal purification/ mineralisation process and for rad-waste treatment....
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TL;DR: In this paper, Di(2-ethylhexyl)isobutyramide (D2EHIBA) has been evaluated as a carrier for U/Th separation in supported liquid membrane.
36 citations
TL;DR: In this article, a supported liquid membrane (SLM) technique was used for the separation of uranium (VI) from phosphoric acid medium using Di-2 ethyl hexyl phosphoric acids (D2EHPA)/n-dodecane as a carrier and ammonium carbonate as a receiving phase.
Abstract: Present studies deal with the application of supported liquid membrane (SLM) technique for the separation of uranium (VI) from phosphoric acid medium using Di-2 ethyl hexyl phosphoric acid (D2EHPA)/n-dodecane as a carrier and ammonium carbonate as a receiving phase. The studies involve the investigation of process controlling parameters like feed acidity of phosphoric acid, carrier concentration, stripping agents, and the effect of thickness and the pore size of the membrane. The transport of uranium decreases with increase in the concentration of phosphoric acid in feed solution whereas it increases with increase in carrier concentration in supported liquid membrane. More than 90% uranium (VI) is recovered in 360 minutes using 0.5 M D2EHPA/dodecane as carrier and 0.5 M ammonium carbonate as stripping phase from the 0.001 M H3PO4 feed. Lower concentration of phosphoric acid and higher carrier concentration is found to be the most suitable condition for maximum transport of uranium (VI) from its l...
35 citations
TL;DR: In this article, the average uranium flux from simulated solutions of wet-process phosphoric acid at 90% uranium transfer was estimated to be 1.3 × 10 −11 mol cm −2 sec −1, or 0.09 lb ft −2 yr −1.
32 citations
"Selection and design criteria of su..." refers background in this paper
...Various liquid membrane processes are now finding use (Sifniades et al., 1981; Danesi, 1984; IAEA, 2004; Mohapatra and Manchanda, 2009) in the treatment of large volumes of low-level radioactive liquid effluents generated in the various stages of nuclear fuel cycle of the nuclear industry....
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