Abstract:
A process and apparatus for treating the heavy hydrogen isotope content of the contaminated water by contacting the contaminated water with a molecular separation material including a support medium carrying a plurality of hydration sites having associated waters of hydration, whereby a portion of the waters of hydration are replaced with heavy hydrogen isotope water molecules from the contaminated water. The hydrogen isotope water molecule content of the contaminated water is thus decreased. The molecular separation material is preferably a polymer, such as a polystyrene/divinyl benzene cross-linked polymer, having hydration sites with associated waters of hydration. Preferred hydration sites are obtained by reacting the polymer, which has been sulfonated or phosphonated to create reactive sites, with a salt of, for example, aluminum, sodium, magnesium, copper, zinc, cobalt, iron, nickel, manganese, potassium and chromium. Before or during contact with the molecular separation material, the contaminated water may be brought into contact with a separation membrane selectively permeable to light water molecules relative to hydrogen isotope water molecules, to remove light water molecules from the water, thereby increasing the concentration of said hydrogen isotope molecules.

Description:
This is a divisional application of U.S. patent application Ser. No. 09/275,335, filed Mar. 24, 1999, now U.S. Pat. No. 6,348,153, which is a continuation-in-part of U.S. patent application Ser. No. 09/093,459 filed Jun. 8, 1998, now U.S. Pat. No. 6,110,373, which is a continuation-in-part of U.S. patent application Ser. No. 09/047,648 filed Mar. 25, 1998, now abandoned. These invention were commonly owned at the time of invention. 
    
    
     BACKGROUND OF THE INVENTION 
     1. Field of the Invention 
     The present invention relates to the separation of oxides of heavy isotopes of hydrogen, and in particular to a process and apparatus for separating deuterium oxide (HDO, D 2 O), tritium oxide (HTO, T 2 O) and oxides of deuterium and tritium (DTO) from light water (H 2 O) contaminated with heavy isotopes of water. In addition, this process addresses separation of heavy water isotopes, e.g. DTO from D 2 O, and HTO from D 2 O. Separation is effected by passing the contaminated water through a molecular separation material containing hydration sites, i.e., sites with associated waters of hydration. The heavy isotopic water is held at higher concentrations within the waters of hydration than in the contaminated water thus providing a separation effect. Heavy isotopic water can also replace adsorbed light water. Separation of the isotope molecules may also be effected with a separation membrane that selectively allows passage of light water molecules in preference to the other heavy isotope molecules. These two procedures may also be combined. 
     2. Description of the Prior Art 
     Nuclear power plants must routinely deal with the replacement and disposal of contaminated water taken from the core reactor that is laden with heavy isotopes of hydrogen, namely deuterium oxides, tritium oxides and deuterium-tritium oxides. Tritium in particular is highly radioactive having a half-life of about twelve and one half years emitting beta rays to form helium. 
     Periodically, the contaminated water from nuclear reactors must be replaced. It has become industry practice of dispose of the old contaminated water by simply dispersing it over adjacent ground areas or evaporating the contaminated water into the atmosphere. This is stressful to the environment as the deuterium oxides and tritium oxides are now known to have contaminated ground water sources. One alternative is to sequester contaminated water in concrete at a considerable expense. 
     SUMMARY OF THE INVENTION 
     In accordance with the present invention, a process and related apparatus are described for separating deuterium oxide (HDO, D 2 O ) and tritium oxide (HTO, T 2 O), i.e. heavy water and tritiated water, and deuterium-tritium oxides, from waste water. As used herein, water molecules of the formula H 2 O will be referred to as light water molecules, or simply water molecules, while water molecules in which one or both of the hydrogen atoms have been replaced by one of these hydrogen isotopes will be referred to as isotope water molecules or isotope molecules. 
     In the described process, a portion of the isotope water molecules are removed from contaminated water, i.e., water containing a small amount of isotope water molecules, through selective adsorption by contacting the contaminated water with a molecular separation material containing hydration sites carrying one or more associated waters of hydration. In the process, isotope water molecules present in the contaminated water selectively replace a portion of the waters of hydration associated with the hydration sites. The molecular separation material can then be separated from the water, reducing the percentage of isotope molecules in the water. After separation, the molecular separation material can be regenerated by removing the isotope molecules for long-term storage, and reused repeatedly to separate isotope molecules. 
     In order to improve the efficiency of the selective adsorption process, the percentage of isotope molecules in the contaminated water can be increased, thereby increasing the exposure of isotope molecules to hydration sites, by removing a portion of the light water molecules, before or during the selective adsorption, by bringing the contaminated water into contact with a porous film or membrane that exhibits a greater permeability for light water molecules than for the larger isotope molecules. For some purposes, adequate separation may be effected through membrane separation alone. 
     The Molecular Separation Material 
     Generally, the molecular separation material of the present invention is comprised of a support medium having a plurality of hydration sites, i.e., sites with associated waters of hydration. The effectiveness of the molecular separation material is determined by the number of hydration sites exposed to the contaminated water, and to the number of waters of hydration at each site. The support medium used to carry the hydration sites is not critical to the invention so long as exposure of the contaminated water to numerous sites containing multiple waters of hydration is provided. In general, this objective is preferably achievable with a high surface area support medium having a plurality of hydration attachment sites. 
     The support medium or medium may be, for example, a polymer, such as polystyrene/divinyl benzene (PSDVB), or polyacrylic/divinyl benzene (PADVB). These polymers are commonly used as supports in ion exchange resins in the preparation of ion exchange resins. The polymer may be functionalized for example, by being sulfonated or phosphonated to provide the sites for attachment of metal or other cations with the required associated waters of hydration. Both strong and weak acid resins have been shown to be effective. 
     It is important to note that the present invention involves the preferential adsorption or substitution of the waters of hydration associated with the hydration sites, and not the replacement of the cation or anion as is normally practiced in using this type of resin. Thus, while the resins employed are referred to in some instances as ion exchange resins, since this is the purpose for which they are commonly employed, their function in the present invention is to facilitate molecular exchange of isotope water molecules with the associated light water molecules attached to the hydration sites. 
     Also, while the present invention will be exemplified by the use of the above resins, it will also become apparent that other materials having a large surface area and hydration sites can be used. That is, the present invention involves the interaction between the hydration sites and the isotope molecules, in which one or more light water molecules initially associated with a hydration site are replaced by isotope molecules in the contaminated water. Thus, the support medium serves essentially as a carrier for the hydration sites. Thus, various high surface area materials can be used, so long as they are water insoluble and provide a large number of accessible hydration sites. For example, the support medium can be other kinds of synthetic polymers, or natural materials, such as zeolites, aluminas, silicas, etc. 
     Each hydration site will have at least one, and preferably from about 7 to about 25 waters of hydration and even higher up to almost 50 waters of hydration. Various molecules that form associations with water molecules, i.e., waters of hydration can be used in the present invention. The cationic portion of the hydration site may be non-metallic, e.g., an ammonium cation (NH 4   + ), or a metallic cation. Of the metal cations, aluminum is especially suitable due to the large number of waters of hydration associated with aluminum salts. However, other cations, such as sodium, magnesium, copper, zinc, cobalt, iron, nickel, manganese, potassium or chromium can also be employed. Depending upon the structure of the support and the manner of its production, the anionic portion of the hydration site molecule can include nitrates, sulfates, chlorides, acrylates, hydroxides, or phosphates. Moreover, a broad array of physical constants for inorganic compounds having varying waters of hydration are to be found in reference handbooks such as  Handbook of Chemistry , N. A. Lange, Ph.D. Revised 10th Edition, or  CRC Handbook of Chemistry and Physics  D. R. Lide, Ph.D., 77th Edition. 
     The molecular separation material may be in various physical forms, so long as a large surface area with hydration sites is exposed to the contaminated water. For ease of manufacture and subsequent regeneration, and the availability of a large surface area, the molecular separation material is preferably in the particulate form., e.g. beads of from about 15 mesh to about 400 mesh. Other physical forms, such as gels, can also be used. 
     The Separation Membrane 
     Separation of the isotopes may also be effected with the use of a separation membrane, or a separation membrane may be used simultaneously, or in sequence with selective adsorption. Suitable separation membranes have a porosity that is selective for light water molecules. That is, the membrane will allow a greater percentage of light water molecules than isotope water molecules to pass through the membrane when the contaminated water is placed against one side of the membrane. The separation membrane may be formed of various materials, such as cellulose acetate. Other suitable separation membrane materials will become apparent to one skilled in the use of such materials for molecular separation. 
     When used, the waste or contaminated water is passed against one side of the membrane surface, causing light water molecules, and a relative small percentage of isotope water molecules to pass through the membrane wall. As a result, the percentage of isotope water in the remaining contaminated water is increased. Therefore, the membrane can be used alone to reduce the volume of the contaminated water for subsequent storage, or to concentrate the isotope for treatment with the above-described molecular separation material. 
     The separation membrane may be positioned for contact with the contaminated water in various ways known to one skilled in the art of using separation membranes, so long as the contaminated water can be conveyed on one side of the membrane, with the light water molecules being permitted to pass through the membrane to the opposite side. Other conditions being the same, the permeation rate of the membrane is directly proportional to the surface area of membrane exposed to the contaminated water. 
     A preferred configuration for purposes of the present invention is to use a separation membrane in the form of one or more hollow fibers, with the contaminated water being passed through the interior of these fibers. As a result, the light water molecules preferentially pass through the walls of the fibers to the exterior of the fibers for collection. 
     The separation membrane may be used in combination with the above molecular separation material for sequential or simultaneous water treatment. For example, the contaminated water may be first exposed to the separation membrane to remove a portion of the light water, thereby concentrating the contaminated water stream. The concentrated stream can then be exposed to the molecular separation material, thereby increasing the effectiveness of the molecular separation, since the isotopes comprise a relatively higher percentage of the waste stream. 
     Alternatively, the contaminated water may be simultaneously subjected to membrane and molecular separation. For example, the membrane can be in tubular form, e.g., lengths of hollow core fiber, and the molecular separation material can be packed into the interior of fiber or tube. The contaminated water can then be conveyed through lengths of the filled tube or hollow core fiber, discharging substantially purified water therefrom with the isotope water molecules, i.e., the oxides of heavy isotopes of hydrogen, being held or trapped within the tube or hollow core fiber for appropriate disposal or regeneration. 
     Thus, in one embodiment of the invention, the heavy water or tritiated water content of a contaminated water stream is reduced by exposing the stream to a single elongated length or a bundle of hollow core fibers, each of which is at least partially filled or packed with beads of an exchange resin, or other molecular separation material. 
     Apparatus and Process 
     The configuration of the apparatus used to practice the process of the invention will vary depending on whether the molecular separation material, the separation membrane, or both, are used. The exact nature of the apparatus will also depend upon the volume of water being treated, the manner of disposal of the water discharge streams, and whether or not the molecular separation material, if used, is to be regenerated. 
     In general, however, the apparatus will include at least one separation chamber, a supply conduit for conveying contaminated water into the separation chamber from a supply source, and a first discharge conduit for removing treated contaminated water from the separation chamber. For example, when the molecular separation material is used alone, the apparatus may include a separation chamber to hold the molecular separation material, a conduit to feed contaminated water into the separation chamber from a supply source, and a discharge conduit for removing treated water from which a portion of the isotope molecules has been removed. Provision may also be made for periodic replacement of the molecular separation material. 
     The apparatus may also include a means for regeneration of the molecular separation material to remove adsorbed isotope molecules and regular water molecules. For example, the loaded molecular separation material can be placed in a heated chamber to drive off the isotope molecules and the light water molecules by evaporation. This desorbed or dehydrated molecular separation material can then be used directly, or rehydrated with light water molecules prior to use. 
     When the separation membrane is used alone, the apparatus will also include a separation chamber in which the contaminated water is passed on one side of the membrane. The apparatus will also include a supply conduit, a first discharge conduit for conveying the treated water passing through the membrane, and a second conduit for conveying the remaining concentrated water. When the separation membrane is in tubular form such as a hollow fiber, the first discharge conduit is in communication with the exterior of the tubes or fibers, while the second discharge conduit is in communication with the interior of the tubes or fibers. 
     The two types of apparatus can be joined together for the combined treatment of the contaminated water with the molecular separation material and the separation membrane. For example, a supply conduit can convey water from a supply source to a first treatment chamber containing the separation membrane. Concentrated water from this first stage treatment can then be conveyed to a second separation chamber holding the molecular separation material. 
     Thus, in one embodiment, the percentage of isotope water molecules in water is reduced by the steps of (a) conveying water containing a percentage of isotope molecules into contact with a molecular separation material having a plurality of hydration sites, (b) substituting or hydrating a portion of the waters of hydration with isotope water molecules, and (c) separating the molecular separation material with associated isotope waters of hydration from the contaminated water. 
     In another embodiment of the invention, isotope water molecules in water is reduced by the steps of (a) conveying water containing a percentage of isotope molecules into engagement. with one side of a permeable membrane, that allowing selective passage of light water molecules in preference to isotope water molecules, whereby light water molecules and a relatively minor percentage of isotope molecules pass through the membrane, and (b) collecting the concentrated water that did not pass through the membrane. 
     In the combined process, isotope water molecules in water are reduced by the steps of (a) conveying water containing a percentage of isotope molecules into engagement with one side of a permeable membrane, that allowing selective passage of light water molecules in preference to isotope water molecules, whereby light water molecules and a relatively minor percentage of isotope molecules pass through the membrane, (b) conveying concentrated water that did not pass through the membrane into contact with a molecular separation material having a plurality of hydration sites, (c) substituting a portion of the waters of hydration with isotope water molecules, and (d) separating the molecular separation material with associated isotope waters of hydration from the contaminated water. 
     Each of the above processes may include additional steps. For example, the first or combined process may further include the steps of (a) regenerating the molecular separation material to separate at least some waters of hydration, (b) collecting isotope water molecules separated from the molecular separation material, and (c) returning the regenerated molecular separation material, with or without rehydration, to the separation chamber. 
     The present invention is presumed to be based upon a molecular exchange principle of either adsorption or selective adsorption to accomplish the experimental results reported herebelow. Although the co-inventors herein differ on the precise theory of the operation, it is understood that the test results below speak for themselves with respect to the efficacy of the various embodiments of the invention. 
     OBJECTS OF INVENTION 
     It is therefore an object of this invention to provide an environmentally safe alternative to the ground or air dispersion of water contaminated with heavy isotopes of hydrogen. 
     It is yet another object of this invention to provide means for separating heavy isotopes of hydrogen from light water (H20) and tritiated water from heavy water. 
     It is still another object of this invention to provide a commercially viable apparatus containing a bundle of filled hollow core fiber lengths in a housing for separating heavy isotopes of hydrogen, including tritium, from contaminated water and a method for regenerating said apparatus. 
     It is another object of the invention to provide a process for separating isotope molecules from water by contacting the water with a molecular separation material that includes hydration sites with associated waters of hydration and methods of regenerating same for reuse. 
     Another object of the invention is to provide a process for separating isotope molecules from water by concentrating the isotope molecules using a separation membrane, and contacting the concentrated water with a molecular separation material that includes cation sites with associated waters of hydration and regeneration thereof. 
     In accordance with these and other objects, which will become apparent hereinafter, the instant invention will now be described with reference to the accompanying drawings. 
    
    
     BRIEF DESCRIPTION OF THE DRAWINGS 
     FIG. 1 is a simplified schematic view of the apparatus  10  shown in FIG. 1B, enlargements of portions thereof shown in FIGS. 1A and 1C. 
     FIG. 2 is a graphic summary or composite of the effectiveness of the invention in reducing the deuterium oxide level in contaminated water using a cross linked (X-L) ion exchange resin loaded with aluminum. 
     FIG. 3 is a perspective schematic view depicting one aspect of the tritium and deuterium oxide separation process of the present invention, that being permeation through the walls of the hollow core fiber. 
     FIGS. 4A,  4 B and  4 C show simplified schematic views of the invention depicting a resin particle selectively absorbing heavy water isotopes, in this example HTO. The adsorption is selective in three instances,  4 A starting from a dry condition,  4 B starting from an initially prewet with pure water condition,  4 C in an intermediate condition where the resin has additional capacity to adsorb before saturation. 
     FIG. 5 is a simplified example of a typical set of water contaminate adsorption curves with respect to both contaminant separation aspects or mechanisms of the present invention. 
     FIG. 6 is a simplified perspective view of one commercial embodiment of the invention using separation membranes. 
     FIG. 7 is a graphic presentation of the test performance of a prototype apparatus similar to the embodiment of the invention shown in FIG. 10 showing a graphic comparison between the feed and exit stream concentrations of D20 contaminated water. 
     FIG. 8 is a graphic presentation of the test performance of a prototype apparatus similar to the embodiment of the invention shown in FIG. 10 showing a graphic comparison between the feed and permeate stream concentrations of D20 contaminated water. 
     FIG. 9 is a graphic presentation of the test performance of a prototype apparatus similar to the embodiment of the invention shown in FIG. 10 showing a graphic comparison between the feed and exit stream concentrations of D20 contaminated water during a second test run after regeneration. 
     FIG. 10 is a graphic presentation of the test performance of a prototype apparatus similar to the embodiment of the invention shown in FIG. 6 showing a graphic comparison between the feed and permeate stream concentrations of D20 contaminated water during a second test run after regeneration. 
     FIG. 11 is a graphic presentation of a typical set of performance curves of the invention depicting the various stages of performance effectiveness of both the exit stream and the permeate. 
     FIG. 12 is one example of a typical commercial system embodying the invention. 
     FIG. 13 is an example of a commercial system for regeneration of the contaminate separation apparatus of the invention. 
     FIG. 14 is a schematic view of a commercial system for both contaminate adsorption and sequential regeneration. 
     FIGS. 15A and 15B are schematic views of another commercial system in which the isotope molecules are separated by using multiple modules or chambers that contain the molecular separation material and internal and external regeneration. 
     FIG. 15C is a schematic view of a counterflow commercial system suitable for larger scale, high feed rate applications. 
     FIG. 16 is a graphical comparison of the adsorption effectiveness of PSDVB resins loaded with aluminum, magnesium, chromium and sodium metal sites. 
     FIG. 17 is a graphical comparison of various PSDVB and PADVB resins loaded with aluminum. 
     FIG. 18 is a graphical comparison of the separation of D 2 0 and HTO showing the similarity in results. 
     FIG. 19 is a graph of the adsorption curve observed with the use of a 2 meter TEFLON column filled with 250 g of dry Al loaded PSDVB resin. 
     FIG. 20 is a graphical comparison of the separation properties of an initially dry resin in comparison to a pre-wet resin. 
     FIG. 21 is a graphical representation of isotope separations using one separation module, two separation modules, and four separation modules, when operated in series. 
     FIG. 22 is a graph of the results achieved in regenerating tritium oxide saturated acrylic resin loaded with sodium and aluminum hydration sites using a microwave oven. 
     FIG. 23 is a graph of the results achieved in regenerating tritium oxide saturated PSDVB resin loaded with sodium and aluminum hydration sites using a fluidized bed dryer. 
     FIG. 24 is a graph of the results achieved in regenerating tritium oxide saturated acrylic resin loaded with sodium and aluminum hydration sites using a fluidized bed dryer. 
    
    
     DETAILED DESCRIPTION OF THE INVENTION 
     In the following description, terms such as horizontal, upright, vertical, above, below, beneath and the like, are used solely for the purpose of clarity in illustrating the invention, and should not be taken as words of limitation. The drawings are for the purpose of illustrating the invention and are not intended to be to scale. 
     Referring now to the drawings, the apparatus is shown generally at numeral  10  in FIG.  1 B and includes a length or coil of hollow core fiber  12  which is formed of cellulose acetate and is otherwise well known in the industry. The particular features of this hollow core fiber  12  used in the experiments reported below are an inside diameter of 1.3 mm (range of 1-3 mm), a wall thickness of 0.2 mm (range of 0.05 to 0.20 mm), an outside diameter of 1.7 mm, and a density of 1.20 g/cm 3 . 
     An inlet end of the hollow core fiber length  12  is connected to a plastic feed line  18  leading to a tank  14  filled with water contaminated with heavy isotopes of hydrogen, namely deuterium oxide. This contaminated water  36  is pumped in the direction of the arrow by pump  16  through connecting plastic tubing  18  into the hollow core fiber length  12 . Radioactive tritium is unavailable for routine, unregulated use, but because the tritium oxide molecule is much larger than both hydrogen oxide and deuterium oxide, the results reported herebelow for deuterium oxide separation apply at least equally well for tritium separation. 
     It should be noted that other water permeable membranes may be utilized, the requirement being having a pore size and molecular composition sufficient to substantially allow permeation of H2O therethrough while substantially preventing permeation of heavy isotopes of water, namely deuterium and tritium in their oxide forms. 
     The hollow core fiber  12  as best seen in FIG. 1C is filled or packed with separate beads  28  which are formed form an ion exchange resin as described herebelow. The outlet end of the hollow core fiber length  12  is connected to a length of plastic tubing  20  which discharges the processed and purified water into a separate container  22  as it flows from the hollow core fiber  12 . 
     To prevent the exchange beads  28  from being forced out of the hollow core fiber length  12 , a filter or trap is connected at the discharge end thereof as shown in FIG. 1A, an enlargement of area  26  of FIG.  1 B. Two spaced apart plastic tubes  30  and  32  each having a small longitudinal aperture centrally therethrough, are positioned within the outlet end of the hollow core fiber length  12 . These plastic tubes  30  and  32  are spaced apart by a quantity of packed cotton  34  so that none of the exchange beads  28  will flow beyond plastic tubing member  30 , yet without substantially restricting the flow of processed water flowing out of the hollow fiber core length  12  into tube  20  in the direction of the arrow. 
     Exchange Resin Beads 
     Details of the content and method of producing the ion exchange beads formed of cross linked styrene divinyl benzene polymer are disclosed in detail in Patterson&#39;s earlier U.S. Pat. No. 5,036,031 which is incorporated herein by reference. 
     Loading Procedure for Ion Exchange Resin Beads 
     The procedure described herebelow was used to load cross-linked ion exchange beads with aluminum. It will be understood that the same reaction will be used to add other metal sites instead of aluminum and basically required reaction of the sulfonated or phosphonated resin with a salt, e.g., a sulfate or nitrate salt, in which the metal to be used for the site is cation. The procedure was applied for R SO 3 H with 2%, 3%, 3.25%, 4%, 8%, 10% and 12% cross-linking, 60 mesh, 100-200 mesh and 200-400 mesh screened for size. 
     Pretreat Beads 
     The beads were first cleaned with hydrochloric acid (2% HCl) to take out all residual cations. Ion exchange with HCl will take out Al and other metal ions which were on the beads as shown by the formula:                           
     The beads are then rinsed with D.I. water until the pH returns to 5-6. This will remove the XCl. 
     Load Beads with Al 
     Prepare a solution of Al 2  (SO 4 ) 3  and, preferably warmed D.I water. Apply this solution to the beads to produce this reaction:                           
     Rinse the loaded beads with D.I. water until the pH returns to 5-6. The beads were initially treated prior to loading into the hollow core fiber. 
     After the ion exchange beads  28  were pretreated as above described, the hollow core fiber length  12  was loaded therewith. The loaded hollow core fiber length  12  was dried in an oven at approximately 100° C. for three days in order to drive out all residual water. Three separate lengths of hollow core fiber  12  were then filled with a prepared mixture of light water (H 2 O) and deuterium oxide in a ratio of approximately 61% D 2 O by volume which was taken from a supply bottle used for the entire experiment to insure consistency. The pump rate of the deuterium oxide contaminated water was set at 2 ml per hour using a constant rate high pressure pump  16 . 
     The effluent discharging into container  22  was then analyzed. This effluent was split into separate samples taken at specific time periods from the start of each experiment. These time spaced samples were taken to provide an indication of the variability of the separation capability of the apparatus  10  over time. The test data taken is shown in Table 1 herebelow. 
     
       
         
               
             
               
               
               
               
               
               
             
               
               
               
               
               
               
             
           
               
                 TABLE 1 
               
             
             
               
                   
               
               
                 HOLLOW CORE FIBER PACKED WITH ION EXCHANGE RESIN BEADS 
               
             
          
           
               
                 ION EXCHANGE 
                 VOLUME OF 
                 ELAPSED TIME 
                 FREEZING 
                 CORRES. 
                 ACCUM. 
               
               
                 RESIN 
                 AFFLUENT (ml) 
                 (HRS) 
                 POINT (° C.) 
                 % OF H 2 O 
                 VOL. (ml) 
               
               
                   
               
             
          
           
               
                 (RSO 3 ) 3 Al (12% x-L) 
                 2 
                 1 
                 2.011 
                 52.64 
                 2 
               
               
                 ″ 
                 2 
                 2 
                 1.801 
                 47.15 
                 4 
               
               
                 ″ 
                 2 
                 3 
                 1.983 
                 51.91 
                 6 
               
               
                 ″ 
                 0.5 
                 3 1/4 
                 1.701 
                 44.53 
                 6.5 
               
               
                 (RSO 3 ) 3 Al (4% x-L) 
                 0.5 
                 2 
                 0.312 
                 8.17 
                 0.5 
               
               
                 ″ 
                 2 
                 3 
                 1.979 
                 51.81 
                 2.5 
               
               
                 ″ 
                 2 
                 4 
                 2.248 
                 58.85 
                 4.5 
               
               
                 ″ 
                 1 
                 5 
                 2.255 
                 59.03 
                 5.5 
               
               
                 ″ 
                 0.5 
                 5 1/4 
                 2.254 
                 59.01 
                 6 
               
               
                 (RSO 3 ) 3 Al (2% x-L) 
                 0.25 
                 2 
                 0.148 
                 3.87 
                 0.25 
               
               
                 ″ 
                 6.3 
                 5 
                 2.028 
                 53.09 
                 6.55 
               
               
                 ″ 
                 0.9 
                 5 1/2 
                 2.101 
                 55.00 
                 7.45 
               
               
                 ″ 
                 .8 
                 6 
                 1.856 
                 48.59 
                 8.25 
               
               
                 (RSO 3 )NH 4  (2% x-L) 
                 1 
                 2 
                 1.777 
                 46.52 
                 1 
               
               
                 ″ 
                 3 
                 4 
                 2.267 
                 59.35 
                 4 
               
               
                 ″ 
                 1.5 
                 5 
                 2.264 
                 59.27 
                 5.5 
               
               
                   
               
             
          
         
       
     
     Graphic Display of Data 
     This test data is also shown graphically in FIG. 2 which is a composite of all of the performance data taken depicting separation capability of each of the ion exchange resins utilized in these experiments. Again, the contaminated test water was all taken from a common prepared source. 
     The concentration of deuterium oxide is depicted as a volumetric percentage of the total affluent sample volume and is determined by carefully establishing the freezing point of each sample. The freezing point of pure light water is 0.0° C. while the freezing point of pure deuterium oxide (D 2 O) is 3.82° C. The freezing point measurements were taken utilizing an Advanced Instruments Osmometer, Model 5600. The conversion from freezing point to percent deuterium oxide was shown to be a linear relationship. 
     In reviewing these graphic performance data shown in FIG. 2, the 2% cross-linked sample with aluminum showed the greatest change or decrease in the deuterium oxide level from 61% by volume down to less than 4% deuterium oxide concentration in the first sample taken after two hours of system operation. Note that with respect to both the 2% and 4% cross-linked exchange resin combined with aluminum, after three to five hours of operation, the second and subsequent samples taken demonstrate substantially higher concentrations of deuterium oxide, indicating that the apparatus is most effective in removing deuterium oxide (and presumably oxides of tritium) from the contaminated water within the first period of operation. 
     Combined Exchange-Membrane Separation 
     The separation of isotopes and molecules as above described is affected by the combination of the process of selective adsorption on a resin and the selective permeation through the walls of the hollow core fiber membrane. The resin particles or beads as above-described are contained within the hollow core fibers and, of particular importance, may be regenerated without the need for removal of the resin from the hollow core fibers. 
     Referring now to FIG. 3, a pictorial view of a section of hollow core fiber  12  is there shown as previously described. Water molecules HOH depicted as circles at  40  permeate through the hollow core fiber wall faster than do the tritium oxide (TOH) molecules shown as triangles at  38 . A substantially higher number of water molecules  40  permeate outwardly through the hollow core fiber wall than do the larger tritium oxide molecules  38 . 
     In FIGS. 4A,  4 B and  4 C, the adsorption aspect of the present invention is there depicted as a second separation agent. Each of the above described resin beads or particles  28  shown in FIG. 4A include cation sites M having the ability to hydrate. Each resin particle also contains hydrogen H as an essential aspect of these polymer resins. The resin can be in three typical initial states. In FIG. 4A, the resin is initially dry. When contacted with a mixture of water isotopes, the tritium oxide (HTO) is preferentially adsorbed as a water of hydration and the feed solution is thus depleted in HTO. In FIG. 4B, the resin is initially prewet with water and the tritiated water replaces some of the existing waters of hydration. In FIG. 4C, the resin is initially partially saturated with respect to the feed concentration. An additional tritiated water replaces a preexisting water of hydration. In all cases shown above, there is the probability of some tritium replacement of hydrogen on the molecular structure. This is depicted as one T atom on the final resin particle. Some supports will have cation sites and no exchangeable hydrogen atoms, such as alumina or silica with and without additional cations. In these cases, there would be no tritium atomic exchange with the support. Note also that the adsorption is reversible; thus, a resin which was saturated at a high HTO concentration would desorb HTO if contacted with water having a lower concentration of HTO. 
     Test performance results may be generalized as shown in FIG. 5. A section of resin filled hollow core fiber  12  is shown in the insert of this graph for reference. The feed stream flows into one end while the exit stream flows out of the other end of the hollow core fiber  12  as shown. The permeate passing through the hollow core fiber walls is also shown. The feed stream has an initial and constant concentration of tritium oxide as shown by the symbols F. The typical level of tritium oxide in the permeate is shown by the letter P over time, while the concentration level of tritium oxide in the exit stream over time is shown by the letters E. Note that the tritium oxide level in the permeate P does not raise or increase to the concentration level of the feed stream F but, at some point in time, the exit stream tritium oxide concentration E exceeds that of the feed stream F. This is likely due to the fact that the resin beads  28  initially absorb and hold a high level of tritium oxide, but eventually become saturated. 
     A commercially viable embodiment of the invention is shown generally at numeral  50  in FIG.  6 . This commercial module  50  includes an elongated tubular housing  52  having a header  58  sealingly connected at each end thereof which supports an inlet tube  54  and an outlet tube  56 , respectively. Positioned within the housing  62  is a bundle of elongated hollow core fibers  60 , each of which is filled with ion exchange resin beads as previously described. This bundle of hollow core fibers  60  is held together by header  62  at each end thereof and positioned within housing  52 . The feed stream enters the device  50  at inlet  54  in the direction of arrow E, while the exit stream flows into the direction of arrow F from outlet  56 . Headers  62  insure that all of the feed stream liquid flows through and not outside of the hollow core fiber members  60 . Separately, permeate flows from permeate outlet  64  in the direction of arrow G to a condenser  66 . 
     The experimental test results reported herebelow utilize this experimental module in developing the data shown in FIGS. 11 to  14 . The test module  50  includes thirty two such hollow core fibers  60  filled with ion exchange resin particles  61 . Each of the fibers were eight feet in length. The feed stream had a D 2 O concentration of 4.85 percent by weight within water. The experimental results are described more fully herebelow. 
     Still referring to FIG. 6, the apparatus  50  may be regenerated when the ion exchange resin bead  61  packed within each hollow core fiber member  60  becomes saturated as previously described in FIG.  9 . Saturation may be determined by sensing the D2O and/or the TOH concentrations in the exit stream. To regenerate the resin, the feed stream is interrupted and, preferably, the apparatus  50  is emptied of fluid. Thereafter, a stream of hot air is forced into inlet  68  in the direction of arrow H. Heated air can also be introduced through inlet  54  and removed through outlet  56  and/or outlet  64 . The heat releases waters of hydration TOH and H2O. When the humidity of the heated air exiting the housing  52  at outlet  64  reaches a predetermined humidity level, the exit gas would flow to a separate high capacity condenser (not shown in FIG. 10) to condense the maximum amount of water from this exit airstream. 
     Referring now to FIGS. 7 and 8, the above described module  50 , having thirty two columns of hollow core fiber members  60  longitudinally arranged and packed therein, were test run utilizing a feed stream of light water contaminated with 4.85% D2O by weight. The D2O concentration of the exit stream was monitored and is shown in FIG. 11 with respect to the exit stream flow shown by weight (g) over time. 
     In FIG. 8, during the same experiment, the concentration of the permeate as a function of total permeate flow by weight (g) is there shown. With respect to both the exit stream and the permeate, the D2O concentrations were initially very low indicating a very high efficiency in D2O separation from water which gradually decreased over time. 
     Referring now to FIGS. 9 and 10, the same experiment utilizing the same module  50  having thirty two columns of hollow core fiber members filled with the same ion exchange resin was retested. Prior to this retest, the airflow regeneration process above described was completed. 
     In comparing the test results of the first run to the second run after regeneration, it is noted that, with respect to the exit stream concentrations shown in FIGS. 7 and 9, the greatest reduction in D 2 O was 90% on the first run, increasing to virtually 100% in the second run after regeneration. Likewise, comparing FIGS. 12 and 14, the permeate concentration on the first run showed a maximum near test onset of 55%, increasing to above 60% D2O reduction in the initial sampling after regeneration. 
     Commercial System 
     To commercialize the present invention, it is useful to divide the separation performance curves with respect to both the exit stream and permeate into sections or segments as shown in FIG.  11 . With respect to the exit stream, the first exit product with the highest reduction in heavy water concentration ends at time S. Second exit product and third exit product stages end at times T and U, respectively. After time U, it is recommended that each module be taken out of service and regenerated as above described. 
     With respect to the permeate, there is also a high efficiency time period ending at time R during which the contaminant reduction is at a maximum. During the second permeate stage between time R and U, the decrease in contaminate removal is generally steady and of a very useful nature. Obviously, although the permeate would continue to be at a contaminate level below that of the feed stream, the module should be regenerated because the exit stream would then contain a higher contamination level than that of the feed stream. 
     Putting these concepts of stages into effect, referring to FIG. 12, one example of a commercial system is shown generally at numeral  70 . The feed stream enters a stage  1  absorber  72 , the exit stream therefrom being monitored for contamination level at sensor/valve  74 . The first exit product will be directed to a clean water product tank  76 . When the sensor/valve  74  indicates that the contaminate removal level is declining as after time S in FIG. 15, the exit stream will then be redirected as a second exit product to a stage  3  absorber at  78 . When the sensor  74  detects a contaminate concentration level at time T in FIG. 15, the exit stream is again redirected into a stage  2  absorber  80 . 
     The permeate from the stage  1  absorber  72  will be directed into a stage  1  condenser  82 . Condensed liquid will pass through sensor  84  which will direct the first permeate having a relatively low level of contamination up to time R as shown in FIG. 15 into, for example a stage  8  absorber  86 . At time R, when the concentration of contaminates begins to rise, the second permeate will then be redirected into a stage four absorber  88 . 
     A typical plant or commercial facility of this nature may have between five and fifteen absorber stages dependent upon overall separation desired, each of which will receive different specified amounts of contaminate concentration for further processing or use as desired. 
     Regeneration 
     In a typical regeneration process shown in FIG. 13, each stage or module in a typical system like that shown in FIG. 12 is shown typically at numeral  92 . During regeneration, hot air from a hot air generator  94  is directed into the module  92  as shown by the arrows. Hot air flowing through the module  92  will remove the liquid within the exchange resin of each of the hollow core fiber members by releasing waters of hydration H2O, HTO, D2O, DTO and HDO which are carried from the module  92  into a regeneration condenser  96 . The liquid condensed and discharging from regeneration condenser  96  during the initial time portion of the regeneration cycle will have the least amount of contaminants in this first regeneration stream and may be returned to the system  70  of FIG. 12 for reprocessing. The second regeneration stream carrying higher amounts of contaminants would be collected at  98 , while the third or last regeneration condensate stream would likely be carrying the greatest amount of contaminants such as tritiated water and would be directed to storage tank  100  for appropriate disposal. 
     To further distinguish the contaminant levels of each of these permeate condensate regeneration streams, the temperature of the air exiting the hot air generator  94  may be gradually increased and/or pressure reduced in steps to provide a greater driving force for contaminant removal. The regenerated resin and fiber system is returned to the adsorption cascade and is rehydrated by the feed stream. The adsorption and regeneration cycles are repeated as desired. 
     FIG. 14 illustrates an overall system for both deuterium and tritium removal from the water contaminated with same is there shown. This system  100  may include prefilters  102  and  104  in the form of either commercial reverse osmosis units or deionization units for pretreating the feed stream entering the stage  1  contaminate separating module  106 . Its exit stream enters the stage  2  module  110  and so forth in upward cascade fashion until the final feed stream exits into a container  122  which collects the purest of the processed contaminated water. Permeate from each of the modules is typically collected at condenser  108  and then collected into condensed permeate tank  112  or exiting from  114  or  116  as other stages of contaminated permeate previously described. 
     Each of the modules may be selectively bypassed as the exit stream contamination level reaches the contamination level of the feed stream for regeneration. Disconnected from the system  100 , a typical hot dry air feed  118  forces hot air directly into each separation module du ring the regeneration cycle previously described. To further decontaminate the condensed permeate collecting in each permeate tank  112 , it may be reintroduced at  120  into the feed stream between adjacent modules  110  according to the contamination level of the permeate condensate. 
     FIGS. 15A and 15B illustrate commercial systems in which the isotope molecules are separated by using three modules or chambers that contain the molecular separation material. The contaminated water is conveyed through the first module until the molecular separation material is saturated. The flow is then switched to the second module until the material in the second module is saturated, and then to the third module. Alternately, the flow may proceed through several modules in series. 
     As the contaminated water flow is switched from a given module, the non-bound water, i.e., the water in the module that is not held as waters of hydration is substantially removed by blowing air through the module. The separated non-bound water can then be recycled for additional separation, or removed from the system. 
     After removal of non-bound water, at least a portion of the waters of hydration are removed by heating the molecular separation material. The separated waters of hydration are then collected for disposal, with or without further concentration. The dehydrated resin, with or without rehydration with light water, is then used for further separation. It will also be understood that the saturated resins, before or after removal of non-bound water, can be removed from the modules for regeneration at a separate site, and then returned to the module as shown in FIG.  15 B. 
     Referring specifically to FIG. 15A, it will be seen that contaminate water is fed to feed tank  150  from a source of contaminated water, identified as the “Client HTO Feed,” and from various recycle feeds in the system. The contaminated water is then fed by feed pump  152  to one of modules  154 ,  156  or  158 . More than three modules may also be used. Each module is filled with a resin having a plurality of hydration sites, e.g., beads of polystyrene cross-linked with divinyl benzene and loaded with a combination of sodium and aluminum sites. Various valves  160  are present in the system to control flow through the water or air lines. For this example, filled valves  160  are closed, while outlined valves  160  are open. 
     In operation of the system, each module has a saturation stage, a dewatering stage, and a regeneration stage. Contaminated water from feed tank  150  passes through a module, e.g., module  154 , to remove a part of the isotope molecules, with the water discharged from the tank being directed to one or more finished water tanks  162 , and from tanks  162  to the Client via pump  164 . An HTO monitor  166  is placed in-line between the modules and finish water tanks to monitor the isotope content of the discharged water. When the isotope content reaches a level indicating the resin in the module being used has reached a saturation level, valves  160  are reset to direct flow of contaminated water to the next module in the series, e.g., module  156 . 
     When the module is in the dewatering mode or stage, as illustrated by module  156 , air is blown through the module to remove non-bound water that is carried via dewatering pump  168  back to feed tank  150 . After the dewatering stage, the module is switched to the regeneration stage, as illustrated by module  158 , in which the module is heated with an external heating jacket  170 . Heated air from heater  172  is also blown by blower  174  through module  158  to condenser  178 . The condensed molecules are separated from the air and stored in condensate tank  182 . 
     The air is recycled to heater  172 . In a second, higher temperature stage of drying, the isotope water exiting from condenser  178  is then trapped on the molecular sieve  180  or other system for storage or disposal. Moisture/humidity probe  184  monitors the quantity of water entering condenser  178 , to determine if the stream is collected or recycled. 
     FIG. 15B illustrates a typical arrangement where the resin is regenerated external to the adsorption modules  154 ,  156 , and  158 . In this case, the resin after saturation is slurried to the spent resin tank  186  using feed water which is returned by dewatering pump  168  to the feed tank  150 . The resin is then transferred to the resin dryer  188  where, as before, heated air from  172  is used to dry the resin. The dryer can be a fluidized bed, a rotating drum or other suitable device. Microwaves from  190  can also be supplied to the dryer to augment the drying process. The dry resins are then transferred to tank  192  where they may be mixed with finished water and reintroduced to an adsorption module using sluice pump  194 . The dry resins can also be air transferred to the adsorption module (not shown). The majority of the systems and operations are similar with the two drying options as evident from inspection of FIGS. 15A and 15B. 
     FIG. 15C illustrates a major variation suitable for larger scale (high feed rate) applications. Supporting systems are similar to those in FIGS. 15A and 15B. The adsorption module  198 , however, is a tall column where the resins descend in a countercurrent fashion in the direction of arrow R as the feed water flows up the column in the direction of arrow S. Dry resins from hopper  196  are introduced at the top of the column  198 . Saturated resins are removed at the bottom to a wet resin hopper  200 . The resins are continuously dewatered, transferred to resin dryer  202  and in a second drying stage to dryer  204 . When dry, they are returned to the dry resin hopper  196 . The feed water is fed by pump  152  up the column and the treated water flows to the finished water tank  162 . The resin and water feed rates are set to achieve the desired removal of tritiated water. 
     FIGS. 16-24 further illustrate the experimental results achieved in the practice of the invention. Specifically, FIG. 16, is a comparison of the adsorption effectiveness of PSDVB resins loaded with aluminum, magnesium, chromium, and sodium metal sites. As will be seen from the adsorption curves, the resin with aluminum sites absorbs a greater amount of deuterium. That is, while all of the resins became saturated at about the same time after being exposed to the contaminated water, the aluminum absorbed a greater quantity of deuterium oxide from the stream as shown by the change of the exit stream from the feed stream, at points measured prior to saturation. Magnesium was the next most effective metal site, followed by sodium with chromium being the least effective. 
     FIG. 17 illustrates the test results obtained in testing various PSDVB and PADVB resins loaded with aluminum. The resins were either semi-macroporous, macroporous, or gel type resins, and were obtained from different suppliers. For example, resin R7 is PSDVB resin obtained from Biorad that was sulfonated and loaded with aluminum cations. As can be seen from FIG. 17, there was variability in effectiveness among these tested resins. 
     As shown in Table II, similar test results were achieved in a “beaker test” using 5 g dry Al loaded resin and 20 g contaminated water: 
     
       
         
               
             
               
               
             
               
               
               
             
           
               
                 TABLE II 
               
             
             
               
                   
               
               
                 HTO Resin Adsorption Capacities 
               
               
                 330 micro Ci/L HTO, 30° C., Glass Beakers 
               
             
          
           
               
                   
                 % HTO Reduction 
               
               
                   
                   
               
             
          
           
               
                   
                 Resin 
                   
               
               
                   
                 R7-PSDVB, Gel 
                 4.69 
               
               
                   
                 R4-PSDVB, Gel 
                 2.22 
               
               
                   
                 P7-PADVB, Gel 
                 1.94 
               
               
                   
                 P9-PSDVB, Macroporous 
                 0.96 
               
               
                   
                 Other carrier 
               
               
                   
                 Zeolite, molecular sieve 4A, Na 
                    2.43% 
               
               
                   
                 Aluminum oxide granules 
                    1.60% 
               
               
                   
                 Silica gel 
                    2.57% 
               
               
                   
                   
               
             
          
         
       
     
     The tests with other carriers were similarly performed with 5 g of dry carrier and 2 g of contaminated water. 
     FIG. 18 compares the separation of D2O and HTO using an Al resin packed in a bundle of 30 fibers, each about 8 feet long. As will be seen from a comparison of the two curves, the removal of the two isotopes is at approximately the same level, confirming that experimental results achieved in removal of deuterium is a valid approximation of what would be achieved under comparable conditions in separating tritium. 
     The strength and number of waters of hydration associations will vary with the selected cation, with the selected anions to which the cation is bonded and with the physical and chemical characteristics of the carrier. In general, the maximum number of hydration points selective to HTO or the contaminants to be removed is preferred. However, a lower threshold for selective adsorption in the range of at least 1% HTO reduction is desired when performing the above beaker test at 30° C. with 5 grams of adsorbent and 20 grams of contaminated water. This reduction is considered to be sufficient for obtaining economically substantial and useful results. 
     FIG. 19 illustrates the adsorption curve observed with the use of a 2 meter Teflon column filled with 250 g of dry Al loaded PSDVB resin. As shown, the resins selectively remove a portion of the isotope molecules in the stream until the resin is saturated. Therefore, depending upon the level of separation desired, the stream can be stopped or switched to another resin bed when about 75% saturation has been reached, as indicated by a rise in the curve, after about 100% saturation has been reached, as indicated by leveling of the curve at approximately 0%, or at some point in between. 
     FIG. 20 illustrates the test results obtained when using an initially dry resin in comparison to a pre-wet resin. In the pre-wet case, the majority of the light water originally on the resin is displaced by the feed stream containing tritiated water. The amount of water on the resin before contacting the contaminated water feed stream was predetermined by accounting for all water used to pre-wet the resin, slurry the resin into the column, and subtracting the water collected from the blowdown step before feeding tritiated water. The zero point on the horizontal axis marks the point where the exit stream equals the initial water on the resin. In the initially dry case, there was no water on the resin and thus the entire curve starts at zero. It can be seen that the net selective tritiated water adsorption is similar for the two cases. In some commercial embodiments, it may be preferential to start with a pre-wet resin, for example where the water is used to transfer the resin from a separate regeneration vessel back to the adsorption column. In other cases, the resin may be initially dry, for example, when regenerated within the adsorption column or when transferred via an air slurry rather than a water slurry. 
     FIG. 21 compares separations using one separation module, two separation modules, and four separation modules, when operated in series. As seen, the two module system removes about twice the isotopes on a percent of feed basis of the one module system, and the four module system removes approximately twice the isotopes of the two module system again on a percent of feed basis. Thus, the efficiency of the overall separation is shown to be essentially linear with the amount of resin used. 
     FIG. 22 illustrates the results achieved in regenerating tritium oxide saturated acrylic resin loaded with sodium and aluminum hydration sites using a microwave oven. 
     FIG. 23 illustrates the results achieved in regenerating tritium oxide saturated PSDVB resin loaded with sodium and aluminum hydration sites using a fluidized bed dryer. 
     FIG. 24 illustrates the results achieved in regenerating tritium oxide saturated acrylic resin loaded with sodium and aluminum hydration sites using a fluidized bed drier. 
     While the instant invention has been shown and described herein in what are conceived to be the most practical and preferred embodiments, it is recognized that departures may be made therefrom within the scope of the invention, which is therefore not to be limited to the details disclosed herein, but is to be afforded the full scope of the claims so as to embrace any and all equivalent apparatus and articles.