Continuous Separation of Radionuclides by Shock Electrodialysis
20210158986 · 2021-05-27
Assignee
Inventors
- Kameron Conforti (Malden, MA, US)
- Mohammad Ayman Alkhadra (Cambridge, MA, US)
- Tao Gao (Cambridge, MA, US)
- Huanhuan Tian (Cambridge, MA, US)
- Martin Z. BAZANT (Wellesley, MA, US)
Cpc classification
B01D61/4281
PERFORMING OPERATIONS; TRANSPORTING
Y02A20/124
GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
B01D61/461
PERFORMING OPERATIONS; TRANSPORTING
B01D61/428
PERFORMING OPERATIONS; TRANSPORTING
B01D2311/08
PERFORMING OPERATIONS; TRANSPORTING
B01D61/48
PERFORMING OPERATIONS; TRANSPORTING
B01D61/42
PERFORMING OPERATIONS; TRANSPORTING
International classification
Abstract
Radioactive nuclides (radionuclides) are separate from an aqueous radioactive liquid by feeding the liquid into a chamber between a porous anode and a porous cathode of a shock electrodialysis device. Meanwhile, an anolyte is fed through the porous anode, and a catholyte is fed through the porous cathode. A voltage is applied to the porous anode and to the porous cathode to create a voltage differential across the chamber. The liquid is passed through the chamber, and cations are selectively driven from the liquid into the cathode by the voltage differential. The voltage differential creates a desalination shock that produces an ion-enriched zone on one side of the desalination shock and a deionized zone on an opposite side. A brine including the radioactive cations is extracted from the ion-enriched zone through a brine outlet, and fresh water is extracted from the deionized zone through a fresh-water outlet.
Claims
1. A system for separating radioactive nuclides, the system comprising: a source of an aqueous radioactive liquid including radioactive nuclides; a feed conduit for liquid flow from the source of aqueous radioactive liquid; a shock electrodialysis device configured to receive the aqueous radioactive liquid from the feed conduit and including: a chamber including: respective inlets for: the aqueous radioactive liquid, wherein the inlet for the radioactive liquid is in fluid communication with the feed conduit from the source; an anolyte; and a catholyte; respective outlets for: fresh water; a brine that includes the radioactive nuclides; the anolyte; and the catholyte; a porous anode contained in the chamber and configured for flow of the anolyte therethrough; a porous cathode contained in the chamber and configured for flow of the catholyte therethrough; at least two of the following functioning as ion separators: an ion-selective boundary; the anode being configured for ion separation; and the cathode being configured for ion separation, wherein the ion separators are configured to selectively pass at least some cations, wherein a channel for flow of the aqueous radioactive liquid from the feed conduit is defined between the ion separators, and wherein the anode and the cathode are configured to drive ionic current in the aqueous radioactive liquid across the channel when the aqueous radioactive liquid fills the channel, and wherein the ion separator is configured to conduct the ionic current; and a cationic porous medium between the ion-selective boundaries in the channel, wherein the cationic porous medium has a positive surface charge to promote flow of the ionic current across the channel and production of a desalination shock with a region of fresh water on one side of the desalination shock and a brine that includes the radioactive nuclides from the aqueous radioactive liquid on an opposite side of the desalination shock.
2. The system of claim 1, further comprising a splitter positioned to separate (a) flow of the fresh water to the outlet for the fresh water and (b) flow of the brine to the outlet for the brine.
3. The system of claim 1, wherein the source of the radioactive aqueous liquid is a nuclear reactor.
4. The system of claim 1, wherein the radioactive aqueous liquid comprises cobalt and cesium.
5. The system of claim 1, wherein the radioactive aqueous liquid further comprises boric acid and lithium.
6. The system of claim 1, wherein the ion separators comprise a pair of the ion-selective boundaries.
7. The system of claim 6, wherein the ion separators are ion-selective cation exchange membranes.
8. The system of claim 1, further comprising a voltage source electrically coupled with the anode and the cathode.
9. The system of claim 1, further comprising: a first capacitive deionization unit with an inlet configured to receive the brine from the shock electrodialysis device; a second capacitive deionization unit with an inlet configured to receive the fresh water from the shock electrodialysis device.
10. The system of claim 9, wherein each capacitive deionization unit comprises: a first electrode capable of intercalating and deintercalating Li+ ions; a porous second electrode; a pair of membranes between the first electrode and the porous second electrode, wherein a channel for fluid flow is defined between the membranes.
11. A method for separating radioactive nuclides, comprising: feeding an aqueous radioactive liquid including radioactive nuclides into a chamber between a porous anode and a porous cathode of a shock electrodialysis device; feeding an anolyte through the porous anode; feeding a catholyte through the porous cathode; applying a voltage to the porous anode and to the porous cathode to create a voltage differential across the chamber; passing the aqueous radioactive liquid through the chamber and selectively driving cations from the aqueous radioactive liquid into the porous cathode via the creation of the voltage differential; creating a desalination shock in the aqueous radioactive liquid via the creation of the voltage differential, the desalination shock producing an ion-enriched zone on one side of the desalination shock and a deionized zone on an opposite side of the desalination shock. extracting a brine including the radioactive cations from the ion-enriched zone through a brine outlet; and extracting fresh water from the deionized zone through a fresh-water outlet.
12. The method of claim 11, further comprising generating the aqueous radioactive liquid in a nuclear reactor.
13. The method of claim 11, wherein a pair of ion-selective boundaries are positioned between the porous anode and the porous cathode and define the chamber therebetween.
14. The method of claim 13, wherein the ion-selective boundaries are ion-selective cationic membranes.
15. The method of claim 11, further comprising: passing the brine through a first capacitive deionization unit; and passing the fresh water through a second capacitive deionization unit.
16. The method of claim 15, further comprising: applying a voltage to a first electrode in the first capacitive deionization unit to intercalate lithium ions from the brine into the first electrode; applying a voltage to a porous second electrode in the first capacitive deionization unit to extract anions from the brine into the porous second electrode; applying a voltage to a first electrode in the second capacitive deionization unit to deintercalate lithium ions from the first electrode into the fresh water; and applying a voltage to a porous second electrode in the second capacitive deionization unit to extract anions from the porous second electrode into the fresh water.
Description
BRIEF DESCRIPTION OF THE DRAWINGS
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[0027] In the accompanying drawings, like reference characters refer to the same or similar parts throughout the different views; and apostrophes are used to differentiate multiple instances of the same item or different embodiments of items sharing the same reference numeral. The drawings are not necessarily to scale; instead, an emphasis is placed upon illustrating particular principles in the exemplifications discussed below. For any drawings that include text (words, reference characters, and/or numbers), alternative versions of the drawings without the text are to be understood as being part of this disclosure; and formal replacement drawings without such text may be substituted therefor.
DETAILED DESCRIPTION
[0028] The foregoing and other features and advantages of various aspects of the invention(s) will be apparent from the following, more-particular description of various concepts and specific embodiments within the broader bounds of the invention(s). Various aspects of the subject matter introduced above and discussed in greater detail below may be implemented in any of numerous ways, as the subject matter is not limited to any particular manner of implementation. Examples of specific implementations and applications are provided primarily for illustrative purposes.
[0029] Unless otherwise herein defined, used or characterized, terms that are used herein (including technical and scientific terms) are to be interpreted as having a meaning that is consistent with their accepted meaning in the context of the relevant art and are not to be interpreted in an idealized or overly formal sense unless expressly so defined herein. For example, if a particular composition is referenced, the composition may be substantially (though not perfectly) pure, as practical and imperfect realities may apply; e.g., the potential presence of at least trace impurities (e.g., at less than 1 or 2%) can be understood as being within the scope of the description. Likewise, if a particular shape is referenced, the shape is intended to include imperfect variations from ideal shapes, e.g., due to manufacturing tolerances. Percentages or concentrations expressed herein can be in terms of weight or volume. Processes, procedures and phenomena described below can occur at ambient pressure (e.g., about 50-120 kPa—for example, about 90-110 kPa) and temperature (e.g., −20 to 50° C.—for example, about 10-35° C.) unless otherwise specified.
[0030] Although the terms, first, second, third, etc., may be used herein to describe various elements, these elements are not to be limited by these terms. These terms are simply used to distinguish one element from another. Thus, a first element, discussed below, could be termed a second element without departing from the teachings of the exemplary embodiments.
[0031] Spatially relative terms, such as “above,” “below,” “left,” “right,” “in front,” “behind,” and the like, may be used herein for ease of description to describe the relationship of one element to another element, as illustrated in the figures. It will be understood that the spatially relative terms, as well as the illustrated configurations, are intended to encompass different orientations of the apparatus in use or operation in addition to the orientations described herein and depicted in the figures. For example, if the apparatus in the figures is turned over, elements described as “below” or “beneath” other elements or features would then be oriented “above” the other elements or features. Thus, the exemplary term, “above,” may encompass both an orientation of above and below. The apparatus may be otherwise oriented (e.g., rotated 90 degrees or at other orientations) and the spatially relative descriptors used herein interpreted accordingly. The term, “about,” can mean within ±10% of the value recited. In addition, where a range of values is provided, each subrange and each individual value between the upper and lower ends of the range is contemplated and therefore disclosed.
[0032] Further still, in this disclosure, when an element is referred to as being “on,” “connected to,” “coupled to,” “in contact with,” etc., another element, it may be directly on, connected to, coupled to, or in contact with the other element or intervening elements may be present unless otherwise specified.
[0033] The terminology used herein is for the purpose of describing particular embodiments and is not intended to be limiting of exemplary embodiments. As used herein, singular forms, such as those introduced with the articles, “a” and “an,” are intended to include the plural forms as well, unless the context indicates otherwise. Additionally, the terms, “includes,” “including,” “comprises” and “comprising,” specify the presence of the stated elements or steps but do not preclude the presence or addition of one or more other elements or steps.
[0034] Additionally, the various components identified herein can be provided in an assembled and finished form; or some or all of the components can be packaged together and marketed as a kit with instructions (e.g., in written, video or audio form) for assembly and/or modification by a customer to produce a finished product.
Shock Electrodialysis (SED):
[0035] A desalination and purification system 10 is shown in
[0036] The porous medium 12 has a rigid structure and has ideally a high surface charge. In one embodiment, the cationic porous medium 12 is a porous glass frit with approximately 1-micron pores, and the cation exchange membrane 16 is formed of a sulfonated-tetrafluoroethylene-based fluoropolymer-copolymer (commercially available as a NAFION membrane from E. I. du Pont de Nemours and Company), which is assembled together with a porous cathode 18.
[0037] In the embodiment of
[0038] As shown in
[0039] The pore channel 14 can be conceptually divided into three regions, as shown in
[0040] In contrast to electrodialysis, these porous media are used to produce desalination shocks that drive localized “membrane-less” desalination and purification processes within the porous media.
[0041] In addition to the above discussion of shock electrodialysis, this disclosure utilizes and incorporates by reference the teachings of U.S. Pat. Nos. 8,801,910 B2 and 8,999,132 B2, and K. Conforti, “Continuous Ion-Selective Separation by Shock Electrodialysis,” Massachusetts Institute of Technology PhD Thesis (2019) and describes various advances from these disclosures, including but not limited to using a multi-pass/stage approach with different parameters for each pass/stage of ion separation and managing the chemistry of the streams in the ion-separation process.
[0042] The operating principles of a light-water nuclear reactor 32 and an SED device 10 used for decontamination are shown in
[0043] After the steam 36 from the reactor 32 passes through the turbine 38, the steam 36 is condensed by a condenser 44 through which cooling water 46 is passed. The condensate 48 (including boric acid, lithium, cobalt, and cesium) formed in the condenser 44 is passed as contaminated water 50 (interchangeably also referred to herein as “practical water” or “radioactive water”) through a feed conduit and an inlet to the shock electrodialysis (SED) device 10.
[0044] At right, a rectangular cross section of the SED device 10 shows water splitting (H.sub.2O.fwdarw.½H.sub.2O+H.sup.++¼O.sub.2) at the anode 52 and formation of molecular hydrogen (H.sub.2) at the cathode 54, which is maintained under acidic conditions to prevent precipitation of metal hydroxides, which are the primary electrochemical reactions that provide electrical current to the cell. As shown in
[0045] An anolyte 60 is fed from an inlet to the SED through the porous anode 52 on one side of the SED device 10, while a catholyte 62 is fed from another inlet to the SED through the porous cathode 54 on an opposite side of the SED device 10. A splitter 70 divides the output from the porous frit 56 into fresh water 72 exiting from the deionized zone 66 on one side and brine 74 on an opposite side of the splitter 70 from the ion-enriched zone 64. The fresh water 72 is recirculated via a conduit to the reactor 32.
[0046] The first laboratory scale prototype to successfully demonstrate SED was designed, built, tested, and patented by our group. To achieve continuous operation, subsequent iterations of this system introduced a novel cross-flow architecture, in which the feed flows through a porous glass frit 12 in a channel placed between identical cation exchange membranes 16, as shown in
[0047] By placing a splitter 70 downstream of the frit 12, the exiting fluid was separated into an enriched (brine) stream 74 and a deionized (fresh water) stream 72 exiting through respective outlets from the anodic (represented by anode 52) and cathodic (represented by cathode 54) sides of the shock wave, respectively. Previous work showed that SED can continuously deionize electrolytes comprising monovalent cations (represented as C.sup.+), including those from NaCl, KCl, KNOB, and Na.sub.2SO.sub.4. These measurements were made by quantifying changes in electrical conductivity of the solution. This work also revealed that water recovery (defined as the fraction of fluid recovered as desalinated water from the concentrated feed) can be increased to over 80% by increasing the applied current and without repositioning the splitter 70. Improved water recovery was attributed to electroosmotic flow perpendicular to the imposed flow, which conveniently delivered more fluid to the depleted (deionized) region 66.
[0048] Because many radionuclides and harmful products of corrosion are dissolved in water as multivalent ions, these SED methods can be used to purify water contaminated with radioactive ions and byproducts of various nuclear processes.
[0049] The concentrations of prevalent species in practical water, the non-radioactive analog of contaminated process water in nuclear reactors, are provided in Table 1, below.
TABLE-US-00001 TABLE 1 Concentration Species (ppm[mM]) Role boron 4.000 [370] present in boric acid; boron-10 serves as neutron poison lithium-7 2.2 [0.32] used (as LiOH) to stabilize pH and control corrosion cobalt-59 20 [0.34] cobalt-60 is the main contributor to high levels of radiation cesium-133 100 [0.75] cesium-137 is one of the most abundant fission byproducts
[0050] In this study, we prepared model radioactive water (referred to hereafter as “practical water”) with the composition outlined in Table 1. This solution includes non-radioactive isotopes of the ions most abundant and active in the process water of light water reactors (LWRs), namely cobalt and cesium. Boric acid is included abundantly as it is often used as neutron poison in these reactors because boron-10 can reduce the likelihood of thermal fission by absorbing neutrons. Lastly, lithium-7 is used (in the form of LiOH) as an additive to control water chemistry and minimize the corrosive effects of boric acid. During operation, small amounts of hazardous corrosion and fission byproducts (e.g., cobalt and cesium) are released into the process water, such that non-radioactive species may undergo radioactivation near the hot reactor core. For example, cobalt-60 is produced when its precursor, cobalt-59, is bombarded with thermal neutrons; cobalt-59 is the naturally occurring isotope of cobalt with 100% abundance, and it is used in alloys that are required to possess thermal and mechanical resilience. These species are then able to settle onto surfaces of the cooling system and recirculation pipes, and the quantity of undesired deposits of radionuclides increases with time. Accumulation of radioactive matter in the structural portions of nuclear reactors is thus an occupational hazard to those who work in the vicinity of these systems and are exposed to such radiation. We note, however, that demineralization of process water in LWRs is just one possible application of SED, and the study of selective removal of cobalt and cesium is generally relevant to treatment of nuclear (waste) water.
[0051] This continuous, laboratory scale architecture of an SED device 10 is illustrated in an exploded view in
[0052] This exemplification of the device included three inlets, two to respectively transport an anolyte 60 and a catholyte 62 to the anode 52 and the cathode 54 (to which voltages are applied) and a third to deliver contaminated feed 50, as well as four outlets—two to transport fluid 60 and 62 from the electrodes 52 and 54 and the other two to generate fresh-water 72 and brine 74 streams at the splitter 70, as shown in
[0053] The electrodes 52 and 54 in this device were platinum meshes (Sigma-Aldrich) that were connected to a REFERENCE 3000 potentiostat/galvanostat (from Gamry Instruments) using titanium wires 82 (from Alfa Aesar). The electrodes 52 and 54 and wires were secured in place by compressible VITON gaskets 80.
[0054] Cation exchange membranes 16 [sulfonated-tetrafluoroethylene-based fluoropolymer-copolymer (NAFION N115) membranes from Ion Power, Inc.] that permit passage only of cations and that have a thickness of approximately 130 μm served as fluidic barriers between the electrode channels and the porous medium 56, which in this study was a microporous borosilicate frit (from Adams & Chittenden Scientific Glass) with ultrafine pores (nominally ranging from 0.9 to 1.4 μm in size), an internal surface area of 1.75 m.sup.2g.sup.−1 based on Brunauer-Emmett-Teller (BET) theory, a mass density of 1.02 gm.sup.−3, a porosity of 0.31, and dimensions of 20 mm×10 mm×9 mm. Prior to assembly, the frit 56 was glued onto an acrylic frame using DEVCON 2-Ton Epoxy (from McMaster-Carr). The splitter 70 (placed midway down the frit for ease of assembly) was made of cast acrylic and was sealed against the top face of the frit 56 using 0.04-inch GORE expanded polytetrafluoroethylene (ePTFE) gasket tape. Holes in all of the acrylic portplate slabs 78 and rubber gaskets 80 were formed using a laser cutter (from Universal Laser Systems) and refined with a drill press (a Palmgren 10-inch, 5-speed bench model). These layers 70, 16, 80, and 78 were then stacked and held together with nuts, bolts, and washers made of 316 stainless steel.
[0055] To prepare practical water with the composition shown in Table 1, we formulated stock solutions with 1,000 times the target concentrations made from lithium hydroxide monohydrate (LiOH*H.sub.2O), cobalt (II) chloride hexahydrate (CoCl.sub.2*6H.sub.2O), and cesium chloride (CsCl). Appropriate volumes of these solutions were then diluted in deionized water, followed by the addition of solid boric acid (H.sub.3BO.sub.3) to achieve a concentration of 370 mM. All reagents were purchased from Sigma-Aldrich and used as received. We note that H.sub.3BO.sub.3 is a weak acid with a first pKa of 9.24 in pure water at room temperature, with the following equation for dissociation equilibrium:
H.sub.3BO.sub.3H.sup.++H.sub.2BO.sub.3.sup.− (1)
we determined the concentration of H.sub.2BO.sub.3.sup.− to be approximately 0.015 mM in solution. This weak dissociation implied that virtually all of the boron was present as electrically neutral boric acid and thus was not separated by SED. We recognized, however, that H.sub.3BO.sub.3 could have influenced the pH of practical water, the dynamics of proton transport, and the extent of ionic separation.
[0056] The pH of practical water (assumed here to be an ideal solution) was indeed calculated assuming partial dissociation of H.sub.3BO.sub.3 as well as complete dissociation of LiOH. By definition of the equilibrium constant, K.sub.a, we obtained the following:
where brackets denote concentration (molarity), [H.sub.3BO.sub.3].sub.0=0.37 M, [LiOH].sub.0=0.32 mM, and pKa=9.24. Solving this algebraic equation gave the following:
[H.sup.+]=6.6×10.sup.−7 M.Math.pH=−log([H.sup.+])=6.2. (3)
[0057] In preparing practical water, the anolyte 60 and contaminated feed 50 were identical in composition, whereas the catholyte 62 included an additional dose of hydrochloric acid (HCl) with a concentration of 10 mM. This dose of HCl was deliberately added to prevent precipitation of cobalt hydroxide that could have formed as a result of hydrogen evolution in the otherwise basic catholyte.
[0058] With these solutions prepared, experiments began by setting the flow rates of all streams. All flow rates were held constant: 0.21±0.01 mLmin.sup.−1 for the electrode streams (anolyte 60 and catholyte 62) and 0.065±0.003 mLmin.sup.−1 for the contaminated feed 50. To transport these streams to the SED device 10, we used peristaltic pumps equipped with TYGON chemical tubing 76 (from Saint-Gobain). With such pumps and at low speeds of rotation, the flow would be pulsed, though it was made smooth by incorporating a small buffering tank 84, known commonly as a hydraulic accumulator (or capacitor), just upstream of the device. In this exemplification of the design, the accumulators 84 were capped glass vials that held a small volume of (compressible) air above the (incompressible) liquids being pumped at the bottom to smooth out pulsations. With flow rates set and tubing connected, the accumulators 84 were left to pressurize and the system to equilibrate overnight, after which the potentiostat/galvanostat was set to operate in galvanostatic mode. Air inside the accumulators 84 became pressurized over time until the fluidic resistance downstream, such as that created by the porous frit, was overcome by the pumped liquid. The measured voltage was allowed to stabilize for at least one hour until it reached steady state.
[0059] Samples were collected directly from the device in graduated cylinders and stored in conical centrifuge tubes for analysis, which included measurement of volume, conductivity, pH, and composition of cations. Conductivity and pH were measured using a SEVENCOMPACT pH/fond S213 meter (from Mettler Toledo analytical instruments), and composition was determined using inductively coupled plasma mass spectrometry using an AGILENT 7900 ICP-MS mass spectrometer. The plasma in the inductively coupled plasma mass spectrometry (ICP-MS) was made from argon gas and was supplemented by helium, which is normally needed to analyze elements with high ionization energies (e.g., Co) for which argon plasma alone is not a sufficient source of ionization. To improve the accuracy of our data and subsequent analysis, we incorporated an internal standard that introduced 100 ppb of indium to all of our samples. Since the output of ICP-MS was numerical (in counts per second), quantitative analysis involved calibration of the measurements, which was achieved by processing a set of reference standards and producing a calibration curve. These standards (for Li, Co, Cs, and In) were purchased from Sigma-Aldrich and serially diluted to prepare a set of samples encompassing the concentrations relevant to this study. All samples and standard solutions were diluted in 2 vol % nitric acid prior to analysis by ICP-MS.
[0060] A quantitative analysis of the deionization of (a) lithium, (b) cobalt, and (c) cesium in practical water is provided in
[0061] The key phenomenon that governs deionization in SED is propagation of a shock wave across which concentration varies drastically and a depletion zone is formed. This shock is generated by providing the system with an overlimiting current, which is current in excess of the flow-limited current (him) defined as follows:
where v is valence (charge), Cis molar concentration, F is Faraday's constant, Q′ is the volumetric flow rate of the feed, and the sum is taken over all cations, k. This definition of I.sub.lim can be interpreted as the rate of forced convection of positive charge carriers into the device, and it was assumed that the flux of anions is 0 at steady state in the presence of ideal cation exchange membranes. Using the composition of practical water in Table 1 and with Q′=0.065 mLmin.sup.−1, we found that I.sub.lim=180 μA. We verified this value experimentally by performing a conventional voltage sweep from 0 to 10 V and measuring the current. After exceeding I.sub.lim, the (overlimiting) current increased linearly with voltage and effected constant conductance, which was consistent with the governing theory as well as previous experimental observations in negatively charged porous media.
[0062] Based on a previous study by our group, we operated our SED system in galvanostatic mode because it facilitates the formation of a stable deionization shock wave when supplying overlimiting current. Potentiostatic operation, on the other hand, tends to result in overshoot and oscillation about a desired overlimiting current and is associated with variability in the shock wave. In the results for treatment of practical water, as presented in
where enrichment factor 88 (EF) is defined as follows:
and where dimensionless current (Ĩ) is defined as Ĩ=I/I.sub.lim. The upper half of
[0063]
[0064] Given the importance of water recovery and energy efficiency in desalination systems, we analyzed the recovery ability and energy demand of SED when used to treat practical water. Water recovery (WR), sometimes referred to as the recovery ratio, is defined as follows:
where Q.sub.F is the volumetric flow rate of the fresh stream; and it is shown in
P.sub.pump=N[Q′Δp.sub.frit+Q(Δp.sub.anolyte+Δp.sub.catholyte)]=2.0×10.sup.−3 kWh year.sup.−1,
Ê.sub.pump=N[Ê.sub.frit+Ê.sub.anolyte+Ê.sub.catholyte]=4.2×10.sup.−2 kWh.sup.−3 (8)
where N is the number of passes (three here), Δp is pressure drop [6.1 pounds per square inch (psi) across the frit and 0.67 psi across each of the electrodes], and Q=0.21 mLmin.sup.−1 is the volumetric flow rate of the electrode streams. At commercial scales, however, we expect that the cost of pumping will become important and will increase according to the desired level of throughput.
[0065] A more intuitive way of understanding the energy efficiency of SED is to consider cost rate 94 (
[0066] For common desalination technologies, performance is improved and energy consumption is reduced by using multiple units or stages of the technology in series, and by operating each stage at lower power. Such an approach is especially suitable for SED because power 92 increases quadratically with current (
[0067]
[0068] In addition to removal of target ions, effective methods for decontamination of water also optimize total deionization, water recovery, and energy density. These quantities are shown for our three-step process in
[0069] Thus far, we quantified the ability of SED to remove target species from practical water and identified general rules to optimize the design of a real system that can treat nuclear waste. In particular, we inferred a complex coupling between the extent of deionization—convoluted by the selective nature of separation by SED—water recovery, and energy demand. The relationship between these parameters is nonlinear, and indeed we observe quadratic growth in energy density with applied current (
ψ=DI.sup.2×WR.sup.n×f(Ê), (9)
where DI is deionization (squared to emphasize this metric), WR is water recovery, n is a positive integer (either 1 or 2 here), and f(Ê) is a dimensionless function of energy density that ranges from 0 to 1. This function may be constant:
f(Ê)=1 (no penalty on energy demand), (10)
linear:
or nonlinear with respect to Ê:
where “min” and “max” operate on the entire array of energy densities in
[0070] Introducing a figure of merit allows us to quantitatively decide which operating conditions in each pass maximize deionization in our system. Characterization of the performance of our three-step process is shown in
[0071] To select the most suitable operating conditions, we compared total (and individual) deionization, water recovery, and energy density, all of which are summarized in Table 2, below, for the sequence of passes that maximizes the corresponding variation of Ψ. The sequence that maximizes Ψ.sub.Co in each step, for instance, leads to relatively low water recovery; but the energy density it consumes is also the least. In comparison, the sequence that maximizes Ψ.sub.tot in each step gives water recovery of 58%; and it maintains almost 99% deionization of Co.sup.2+ with little additional demand for energy. This level of water recovery is similar to those achieved by conventional purification technologies, though it can be increased by selecting an alternate sequence in our process. To make a quantitatively motivated selection, more weight is given to water recovery by setting n=2 and f(Ê)=1 in our definition of Ψ, as shown in
[0072] In Table 2, below, a summary is provided of total (and individual) deionization, DI; water recovery, WR; and energy density, Ê, for the sequence of passes that maximizes the figure of merit, Ψ, in
TABLE-US-00002 TABLE 2 DI.sub.tot DI.sub.Li DI.sub.Co DI.sub.Cs WR Ê 9%) (%) (%) (%) (%) (kWhm.sup.−3) Optimal 98.1 ± 0.2 98.0 ± 0.2 99.5 ± 0.1 97.3 ± 0.5 43 ± 2 1.76 ± 0.04 Sequence for Ψ.sub.Co Optimal 98.6 ± 0.1 98.8 ± 0.2 98.9 ± 0.3 98.3 ± 0.2 58 ± 2 2.18 ± 0.05 Sequence for Ψ.sub.tot Optimal 98.2 ± 0.2 98.5 ± 0.3 98.3 ± 0.4 98.1 ± 0.2 66 ± 2 4.8 ± 0.2 Sequence for Ψ.sub.WR
[0073] This process intensification of SED can, in principle, be achieved in two steps by using CDI to recycle Li.sup.+ in two steps, as illustrated in
[0074] In the second step, the fresh water stream 72 produced by SED is passed through the CDI unit 106. By reversing the direction of electric field (by reversing the respective voltages applied to the electrodes 108 and 110), lithium and its counterion(s) are released from the first electrode 108 back into solution and are recovered for later use.
[0075] Although methods and systems designed to target removal of cations are a focus of the above discussion, adapted versions of these methods and systems can alternatively be employed to remove anions. To remove anions, the charges of the components in the SED chamber would be switched. For example, the cation exchange membranes (or alternative form of cation separator) would be replaced with anion exchange membranes (or alternative form of anion separator); and the cationic porous medium would be replaced with an anionic porous medium. Such anion-targeted applications can include radionuclide separations that involve target anions, including complexes of cations with over-compensating anions. Further discussion of the use of SED for the removal of anions can be found in U.S. Pat. Nos. 8,801,910 B2 and 8,999,132 B2, which are incorporated herein by reference.
[0076] In describing embodiments, herein, specific terminology is used for the sake of clarity. For the purpose of description, specific terms are intended to at least include technical and functional equivalents that operate in a similar manner to accomplish a similar result. Additionally, in some instances where a particular embodiment includes a plurality of system elements or method steps, those elements or steps may be replaced with a single element or step. Likewise, a single element or step may be replaced with a plurality of elements or steps that serve the same purpose. Further, where parameters for various properties or other values are specified herein for embodiments, those parameters or values can be adjusted up or down by 1/100.sup.th, 1/50.sup.th, 1/20.sup.th, 1/10.sup.th, ⅕.sup.th, ⅓.sup.rd, ½, ⅔.sup.rd, ¾.sup.th, ⅘.sup.th, 9/10.sup.th, 19/20.sup.th, 49/50.sup.th, 99/100.sup.th, etc. (or up by a factor of 1, 2, 3, 4, 5, 6, 8, 10, 20, 50, 100, etc.), or by rounded-off approximations thereof or within a range of the specified parameter up to or down to any of the variations specified above (e.g., for a specified parameter of 100 and a variation of 1/100.sup.th, the value of the parameter may be in a range from 0.99 to 1.01), unless otherwise specified. Further still, where methods are recited and where steps/stages are recited in a particular order—with or without sequenced prefacing characters added for ease of reference—the steps/stages are not to be interpreted as being temporally limited to the order in which they are recited unless otherwise specified or implied by the terms and phrasing.
[0077] This invention has been shown and described with references to particular embodiments thereof, those skilled in the art will understand that various substitutions and alterations in form and details may be made therein without departing from the scope of the invention. Further still, other aspects, functions, and advantages are also within the scope of the invention; and all embodiments of the invention need not necessarily achieve all of the advantages or possess all of the characteristics described above. Additionally, steps, elements and features discussed herein in connection with one embodiment can likewise be used in conjunction with other embodiments. The contents of references, including reference texts, journal articles, patents, patent applications, etc., cited throughout the text are hereby incorporated by reference in their entirety for all purposes; and all appropriate combinations of embodiments, features, characterizations, and methods from these references and the present disclosure may be included in embodiments of this invention. Still further, the components and steps identified in the Background section are integral to this disclosure and can be used in conjunction with or substituted for components and steps described elsewhere in the disclosure within the scope of the invention.