The present invention relates generally to the chemical separation of radionuclides. More specifically it relates to a method of automated chemical separation of one radionuclide from another, and more specifically, it relates to the automation of the separation of a short lived daughter isotope from a longer lived parent isotope, where the daughter isotope is useful in nuclear medicine.

Separation of short lived alpha and beta emitting radionuclide daughter isotopes from long lived parent isotopes has been done for medical treatment, especially against cancer. The widespread recognition of the use of radiation to kill or neutralize unwanted cell growth such as cancer has led to increasing interest in various species of radionuclides. Of particular interest are radionuclides, such as ²¹³Bi, which emit alpha radiation, or alpha emitters, because the alpha radiation emitted by these radionuclides does not penetrate deeply into tissue. ²¹³Bi is normally produced as a daughter product of ²²⁹Th (t_1/2 = 7300 y). The radioactive decay chain in which ²¹³Bi is found is well known:²³³U (1.62x10⁵ yr t_1/2) to ²²⁹Th to ²²⁵Ra (14.8 day t_1/2) to ²²⁵Ac (10 day t_1/2) to ²¹³Bi 47 min t_1/2). The daughters of interest for biological applications include ²²⁵Ra which decays to ²²⁵Ac. ²²⁵Ac in turn decays through a series of steps to ²¹³Bi (t_1/2 = 45.6 m).

Briefly, by placing alpha emitters adjacent to unwanted cell growth, such as a tumor, the tumor may be exposed to the alpha radiation without undue exposure of surrounding healthy tissue. In many such schemes, the alpha emitter is placed adjacent to the tumor site by binding the alpha emitter to a chelator which is in turn bound to a monoclonal antibody which will seek out the tumor site within the body. Unfortunately, in many instances, the chelator will also bind to metals other than the desired alpha emitter. It is therefore desirable that the number of monoclonal antibodies bonded to metals other than the desired alpha emitter be minimized. Thus, it is desirable that the alpha emitter be highly purified from other metal cations. In addition, alpha emitters such as²¹³Bi (47 min t_1/2) have very short half-lives. Thus, to utilize these short lived radionuclides effectively in medical applications, they must be efficiently separated from other metals or contaminants in a short period of time to maximize the amount of the alpha emitter available. Moreover, there exists low abundance, low energy γ-emissions associated with ²¹³Bi that are useful for patient imaging. A more detailed description of the use of such radionuclides is found in numerous articles including Pippin, C. Greg, Otto A. Gansow, Martin W. Brechbiel, Luther Koch, R. Molinet, Jaques van Geel, C. Apostolidis, Maurits W. Geerlings, and David A. Scheinberg. 1995. "Recovery of Bi-213 from an Ac-225 Cow: Application to the Radiolabeling of Antibodies with Bi-213", Chemists' Views of Imaging Centers, Edited by A. M. Emran, Pleaum Press, New York, NY (Pippin, 1995).

In 1996, Dr. David Scheinberg of the Memorial Sloan-Kettering Cancer Center, New York, NY, began administering ²¹³Bi to a patient for treatment of acute leukemia. ²¹³Bi is an alpha emitter which can be linked to a monoclonal antibody, "an engineered protein molecule" that when attached to the outside of the cell membrane - can deliver radioactive ²¹³Bi, an alpha emitter with a half-life of 47 minutes. This initial trial represented the first use of alpha therapy for human cancer treatment in the U.S.

Various methods to separate bismuth from other radionuclides have been developed over the last few years. Recent work designed to develop Bi generators has focused on the use of an actinium-loaded organic cation exchange resin (Pippin, 1995; Wu, C., M. W. Brechbiel, and O. A. Gansow. 1996. An Improved Generator for the Production of Bi-213 from Ac-225, American Chemical Society Meeting, Orlando, FI, August, 1996 (Wu, 1996); and Mirzadeh, S., Stephen J. Kennel, and Rose A. Boll. 1996. Optimization of Radiolabeling of Immunoproteins with Bi-213, American Chemical Society Meeting, Orlando, Fl, August, 1996). The major problem with the organic cation exchange method is that, with the need for larger amounts of "²²⁵Ac cow" (>20 mCi), the generator is limited by the early destruction of the actinium-loaded organic cation exchange resin. Attempts to minimize this destruction have been employed by Dr. Wu at the National Institute of Health (Wu, 1996) and Dr. Ron Finn (Finn, R., M. McDevitt, D. Scheinberg, J. Jurcic, S. Larson, G. Sgouros, J. Humm, and M. Curcio (MSKCC); M. Brechbiel and O. Gansow (NIH); M. Geerlings, Sr.(Pharmactinium Inc., Wilmington, DE); and C. Apostolidis, and R. Molinet (European Commission, Joint Research Centre, Institute for Transruanium Elements, Karlsruhe, FRG.). 1997. "Refinements and Improvements for Bismuth-213 Production and Use as a Targeted Therapeutic Radiopharmaceutical", J. Labelled Compounds and Radiopharmaceuticals, XL, p. 293 (MSKCC, 1997)). Instead of loading the ²²⁵Ac as a "point" source on the top surface of a cation exchange column (Karlsruhe approach), the actinium is exchanged onto a portion of the organic resin in a batch mode. The loaded ion exchange beads are then mixed with non-loaded beads to "dilute" the destructive effect, when placed in an ion exchange column used for Bi separation. The ²¹³Bi that is eluted from the generator is chemically reactive and antibody radiolabeling efficiencies in excess of 80% (decay corrected) are readily achieved. The entire process including the radiolabeling of the monoclonal antibody takes place at abient temperature within 20-25 minutes. The immunoreactivity of the product has been determined at a nominal value of 80%. The resultant radiopharmaceutical is pyrogen-free and sterile. However, under this approach, the preparation of the "cow" prior to separation of the Bi from the organic resin is time consuming and may not meet ALARA radiation standards. In addition, the²²⁵Ac remains associated with the organic resin during the life time of the generator (~20 days) releasing organic fragments into the ²¹³Bi product solution each time the "cow" is milked.

The Karlsruhe radionuclide generator described in Koch, 1997 was developed in support of Dr. David Scheinberg's (Memorial Soan-Kettering Cancer Center (MSKCC), New York, NY) linking ²¹³Bi to a recombinant humanized M195 (HuM195) antibody. All ²²⁵Ac was loaded on an inlet edge of an AGMP-50 cation exchange resin column. Because of radiation damage to the ion exchange column and resin, MSKCC altered the Karlsruhe radionuclide generator to spread the ²²⁵Ac throughout the resin bed. This alteration reduced local radiation damage, but because the ²²⁵Ac is maintained in the resin, the resin does suffer damage from the alpha activity.

An inorganic ion exchange "generator" concept, has been developed by Gary Strathearn, Isotope Products Laboratories, Burbank, CA and is described (Ramirez Ana.R. and Gary E. Strathearn. 1996.Generator System Development of Ra-223, Bi-212, and Bi-214 Therapeutic Alpha-Emitting Radionuclides, American Chemical Society Meeting, Orlando, FI, August, 1996 (Ramirez, 1996)). In this approach, inorganic polyfunctional cation exchangers are used to avoid damage from the intense alpha bomhardment. A column of Alphasept 1™ is pretreated with nitric acid (HNO₃), the ²²⁵Ac in 1M HNO₃ feed is then loaded on to the column and the ²¹³Bi product is eluted with 1M HNO₃. The product HNO₃ must then be evaporated to dryness to remove the nitric acid. It is then brought back into solution with a suitable buffered solution to prepare the final binding of the alpha emitter to a chelator and monocolyl antibody. The evaporation step extends the time required to prepare the final product and limits the usefulness of this approach.

An anion exchange bismuth separator and method was developed as described in U.S. patent application 08/789,973, now U.S. patent           . The method requires hand operation of syringes and therefore has the disadvantage of needing technical labor with the inherent possibility of radioactive exposure to the laborer.

Because of the need for increasing amounts of therapeutic radionuclides, there is need for a method of rapid and safe (low operator exposure)separation and purification of daughter radioisotopes from parent radioisotopes from example ²¹³Bi from ²²⁹Th. US-A-5,154,897 discloses a process and apparatus for separating daughter radioisotopes from a stock solution (cow) comprising both daughter and parent radioisotopes comprising a pump (not shown and not specifically defined as being bi-directional), multiway valve and separation bed. The cow is supplied to the separation bed, which retains the daughter isotope. A wash solution is passed through the separation bed to release any trace of parent isotope and finally the daughter isotope retained in bed is eluted with eluent.

The present invention is method of separating a short-lived daughter isotope from a longer lived parent isotope, with recovery of the parent isotope for further use. Using a system with a bi-directional pump and one or more valves. a solution of the parent isotope is processed to generate two separate solutions, one of which contains the daughter isotope, from which the parent has been removed with a high decontamination factor, and the other solution contains the recovered patent isotope. The process can be repeated on this solution of the parent isotope. The system with the fluid drive and one or more valves is controlled by a program on a microprocessor executing a series of steps to accomplish the operation.

In one approach, the cow solution is passed through a separation medium that selectively retains the desired daughter isotope, while the parent isotope and the matrix pass through the medium. After washing this medium, the daughter is released from the separation medium using another solution.

With the automated generator of the present invention, all solution handling steps necessary to perform a daughter/parent radionuclide separation, e.g. Bi-213 from Ac-225 "cow" solution, are performed in a consistent, enclosed, and remotely operated apparatus. Operator exposure and spread of contamination are greatly minimized compared to the manual generator procedure described in U.S. patent application 08/789.973

Using 16 mCi of Ac-225, there was no delectable external contamination of the instrument components.

It is an object of the present invention to separate and purify a shorter lived daughter isotope from a longer lived parent isotope in an automated system, recovering the parent isotope tor future use.

It is an object of this invention that the parent isotope can be reused to recover more daughter isotope at a later time, with no manual manipulation of the parent isotope involved.

It is an object of this invention that the radiolytic exposure of the separation medium is minimized.

The subject matter of the present invention is particularly pointed out and distinctly claimed in the concluding portion of this specification. However, both the organization and method of operation, together with further advantages and objects thereof, may best be understood by reference to the following description taken in connection with accompanying drawings wherein like reference characters refer to like elements.

• FIG. 1 is a schematic diagram of the apparatus of the present invention with separate valves.
• FIG. 2 is a schematic diagram of the apparatus of the present invention with a multiposition valve.
• FIG. 3a is a schematic diagram of a system apparatus of the present invention with two multiposition valves and a separator.
• FIG. 3b is a schematic diagram of the system apparatus as in FIG. 3a, but with an optional two-position valve.
• FIG. 4a is a graph of activity versus eluent volume, elution profile. (Ex. 1)
• FIG. 4b is a graph of %Bi recovered versus eluent volume. (Ex. 1)
• FIG. 5a is a graph of activity versus eluent volume, elution profile. (Ex. 3)
• FIG. 5b is a graph of %Bi recovered versus eluent volume. (Ex. 3)

The apparatus of the present invention is shown in FIG. 1. A bi-directional pump 100 is connected to a tubing segment 102. The bi-directional pump 100 and tubing segment 102 are filled with a buffer liquid (not shown). A first valve104 is connected to the tubing segment 102 and connected to a gas supply (not shown) for drawing a volume of a gas in contact with the buffer liquid. A second valve 106 is connected to the tubing segment permitting drawing a first liquid sample (not shown) of a mixture of said short lived daughter isotope and said long lived parent isotope into the tubing segment by withdrawing an amount of the buffer liquid. The first liquid sample is prevented from contacting the buffer liquid by the volume of gas therebetween. The size (inside diameter) of the tubing segment and other tubing is selected so that the surface tension of liquids in cooperation with the inside diameter is sufficient in the presence of a gas to prevent flow of the liquid past the gas. Isolation valves 108 may be included.

Because additional streams, for example wash stream, eluent stream, waste stream, reagent stream are needed for full operation of a separation system, it is preferred that the valves 104,106, and others connected to the tubing segment 102 for the additional streams be collected into a multiposition valve 200 as shown in FIG. 2

A complete system for separating Bi-213 from Ac-225 is shown in FIG. 3a. The bi-directional pump 100 is a high precision digital syringe pump (syringe volume 10 ml) (Alitea USA, Medina WA). The tubing segment 102 is a coil connected to a first multiposition valve 200 containing the gas valve or port 104. the sample or cow valve or port 106 and others as shown. An outlet port 300 directs fluids to a separator 302. The separator outlet is connected to a second multiposition valve 304. A cow reservoir 306 is connected to ports on both the first and second multiposition valves. A product reservior 308 collects the desired radionuclide solution. For separating Bi-213 from Ac-225, the separator302 is an anion exchange membrane.

An alternative embodiment is shown in FIG. 3b including a 4 port two-position valve 310. In this embodiment, the first multiposition valve 200 is connected to a separation reactor port (two-position value 310, port 1) and a stack of zones is delivered from the tubing segment 102 through the two-postiton valve 310 to the separator 302 at a specified flow rate. The purpose of the two-position valve 310 is to provide tor the possibility of flow direction reversal through the separator 302. The two-position valve 310 is optional.

A preferred material for separation is an anion absorbing resin in the form of an membrane system, provided by 3M. St. Paul, MN. The membrane system has a paper thin organic membrane containing the anion exchange resin, incorporated into a cartridge. The anion exchange resin, Anex™, from Sarasep Corp., Santa Clare, CA; is ground to a powder and is secured in a PTFE (polytrifluoroethylene) membrane in accordance with the method described in a 3M, U.S. Patent 5,071,610. For our testing, the cartridge was 25mm in diameter. Both the cartridge size and the type of anion exchange resin used can be varied depending on the size required by the generator. Alternatively, the anion exchange resin may be in the form of particles placed in a column. Size of the cartridge or column may be determined by the desired exchange capacity.

All valves are preferably non-metallic, for example Cheminert™ obtained from Valco Instrument Company, Inc., (Houston TX). Also, reagent and transport lines including the tubing segment 102 are preferably non-metallic and chemically inert, for example, polytetrafluoroethylene (Teflon), polyvinylidene fluoride resin (Kynar), polyetherethylketone (PEEK) and combinations thereof.

The pump and valves are controlled remotely from a microprocessor. Any microprocessor and operating software may be used, for example a lap-top PC using FIALAB software (Alitea).

The method of the present invention is for separating a short lived daughter isotope from a long lived parent isotope, and has the steps of:

• (a) filling a bi-directional pump connected and a tubing segment connected thereto with a buffer liquid;
• (b) drawing a volume of a gas in contact with the buffer liquid by withdrawing a first amount of said liquid buffer; and
• (b) drawing a first liquid sample of a mixture of said short lived daughter isotope and said long lived parent isotope into the tubing segment by withdrawing a second amount of the buffer liquid, wherein said first liquid sample is separated from said buffer liquid by the volume of the gas.

Specifically, a Bi generator can have as the starting material either ²²⁵Ac, separated from the parents, or a mixture of ²²⁵Ra/²²⁵Ac. There are advantages and disadvantages to the use of ²²⁵Ra as a starting material. If ²²⁵Ra is not separated from the ²²⁵Ac, the amount of Bi in terms of available radioactivity as a function of time is greatly extended. However, if the ²²⁵Ra also contains a fraction of ²²⁴Ra, because the original thorium "cow" contained both ²²⁹Th and a small percent of ²²⁸Th, separation to remove the radium is desirable.

The apparatus of the present invention may be used in two modes, stacking and sequential. The stacking mode has multiple "slugs" of liquid separated by multiple "slugs" of gas, whereas the sequential mode has only one "slug" of gas to separate sequentially loaded "slugs" of liquid from the buffer liquid.

For separation of Bi-213 from Ac-225 (without ²²⁵Ra), the steps using the apparatus of the present invention are:

• 1.1 Valve 200 in waste position (port 7). Syringe is emptied at 10 ml/min.
• 1.2 0.250 ml air segment is aspirated into the holding coil at 10 ml/min.

• 2a.1. gas, preferably air, is drawn or pulled into the tubing segment 102 through valve 104 (port 1 on first multiposition valve 200), preferably about 2 ml at about 10 ml/min flow rate.
• 2a.2. a membrane conditioning reagent (same as liquid containing "cow" but without the "cow") is drawn into the tubing segment 102 through valve 200, port 2, preferably 4 ml of 0.5 HCl at 10 ml/min flow rate.
• 2a.3. the membrane conditioning agent is expelled from the tubing segment 102, through the separator 302 (valve 200, port 6) to waste (valve 304, port 6), followed by air, preferably about 1.9 ml air at about 4 ml/min flow rate. Flow direction: down-flow (In FIG. 3b, ports 1 and 2 on the 2-way valve are connected).
• 2a.4. Valve 200 is switched to waste (port 7) and remaining air (about 0.1 ml) is expelled from the tubing segment 102 to waste, followed by 0.5 ml of buffer liquid (or carrier solution). The flow rate is preferably about 10 ml/min buffer liquid (or carrier solution) is a liquid that does not wet the tubing and/or valve internal surface(s). The preferred carrier solution is deionized water. For clinical applications, the carrier solution can be a sanitizing solution (e.g., 50-80% ethanol solution). By utilizing ethanol solution as a carrier solution, the generator instrument can be maintained sterile. By washing the tubing with ethanol its tendency to wet is minimized.

At this point the separator 304 is conditioned and ready for separation. All transport lines and the separator 304 are filled with air.

• 2b.1 Gas, preferably air is pulled into the tubing segment 102 through valve 200, port 1, preferably about 1 ml at about 18 ml/min flow rate.
• 2b.2 Membrane conditioning reagent is aspirated from valve 200, port 2 into the tubing segment 102, preferably about 4 ml of about 0.5 HCl at about 18 ml/min flow rate.
• 2b.3 The membrane conditioning reagent is expelled from the tubing segment 102, through the separator 302 (valve 200, port 6) to waste (valve 304, port 6), followed by air, preferably about 1 ml with a flow rate of about 8 ml/min. Flow direction: down-flow (ports 1 and 2 on the 2-way valve 310 (FIG. 3b) are connected).
• 2b.4 Air is aspirated through valve 200, port 1 into the tubing segment102, preferably about 10 ml at about 18 ml/min flow rate.
• 2b.5 Valve 200 is switched to membrane position (port 6). About 10 ml of air is expelled through the separator 302 at about 15 ml/min flow rate to waste (valve 304, port 6).

• 3a.1. Air is pulled into the tubing segment 102 through valve 200, port 1, preferably about 2 ml at about 10 ml/min flow rate.
• 3a.2. Scrub solution is pulled into the tubing segment 102 through valve200, port 4, preferably about 4 ml of about 0.005 M HCl at about 10 ml/min flow rate.
• 3a.3. Air is pulled into the tubing segment 102, preferably about 2 ml at about 10 ml/min.
• 3a.4. "Cow" solution is drawn through valve 200, port 5 into the tubing segment 102, preferably about 4 ml at about 4 ml/min flow rate. Note that the "cow" volume is only about 3 ml. Aspiration of about 4 ml volume insures quantitative transfer of the cow solution into the tubing segment 102.

At this point the tubing segment 102 contains sequentially stacked zones of "cow" and scrub solutions separated with the air segments. Alternatively,

• 3a.5. Multiposition valve 304 is in the "cow" position (port 1)
• 3a.6. Multiposition valve 200 is in the membrane position (port 6)
• 3a.7. Two-position valve 310 (optional) is switched to up-flow position (ports 1 and 4 are connected)
• 3a.8 "Cow" solution and air (preferably about 1.8 ml) are delivered to the separator 302 and the effluent is directed to the original "cow" storage container or reservior 306 through valve 304 (port 1). This step is accomplished by dispensing about 6.350 ml from the holding coil at 4 ml/min flow rate. (Note that the actual volumes and dispensed volumes are different. The dispensed volumes were found experimentally in cold tests and account for the elasticity of the air segments stacked in the holding coil. We confirmed that the overall reproducibility of the solution handling was not affected.)
• 3a.9. Multiposition valve 304 is in the scrub position (port 2).
• 3a.10. Scrub solution (preferably about 4 ml of about 0.005 M HCl) and air (preferably about 1.9 ml) are delivered to the separator 302 and directed to valve 304 (port 2). The scrub fraction is collected for subsequent analysis.
• 3a.11. Valve 200 is switched to waste (port 7) and remaining air (about 0.1 ml) is expelled from the holding coil to waste, followed by the carrier solution (about 0.5 ml). The flow rate is preferably about 10 ml/min

At this point, Bi-213 is retained on the anion exchange membrane within the separator 302 and is separated from the parent Ac-225. The Ac-225 "cow" solution is recovered in the original storage vial or reservoir 306. The separator302 and transport lines are flushed with air. The separator 302 is ready for Bi-213 elution.

• 3b.1 Air is aspirated through valve 200, port 1 into the tubing segment102, preferably about 1 ml at about 10 ml/min.
• 3b.2 Valve 200 is switched to "cow" position (port 5). About 4 mL cow is drawn into the tubing segment 102 at about 4 ml/min flow rate. Ac-225 "cow" solution volume is nominally 3.1 ml. Aspiration of about 4 ml insures quantitative transport of the "cow" solution into the tubing segment 102.
• 3b.3 Operator is requested to confirm further proceeding with the automated separation.
• 3b.4 Valve 200 is switched to the membrane position (port 6). Valve304 is switched to "cow" return position (port 1). Two-position valve 310 is switched to up-flow position (ports 1 and 4 are connected).
• 3b.5 About 5 ml is expelled from the tubing segment 102 to cow storage vial 306 (Valve 304, port 1) at about 4 ml/min flow rate. Ac-225 "Cow" solution is propelled through the separator 302 and is returned to the storage vial306.
• 3b.6 Valve 200 is switched to "air" position (port 1). About 10 ml of air is aspirated into the tubing segment 102 at about 8 ml/min flow rate.
• 3b.7 Valve 200 is switched to membrane position (port 6). Two-position valve xx is switched to down-flow position (ports 1 and 2 are connected).
• 3b.8 About 10 ml of air is expelled from the tubing segment 102 to the "cow" storage vial 306 through valve 304, port 1 at about 15 ml/min flow rate.

At this point Bi-213 is loaded into the separator 302, Ac-225 solution is returned to the original storage vial 306.

• 3b.9 Valve 200 is switched to air position (port 1). Valve 304 is switched to scrub position (port 2).
• 3b.10 Air is aspirated into the tubing segment 102 through valve 200, port 1 preferably about 1 ml at about 10 ml/min.
• 3b.11 Valve 200 is switched to scrub position (port 4). About 4 ml of scrub solution is pulled into the tubing segment 102 at about 20 ml/min.
• 3b.12 Valve 200 is switched to membrane position (port 6). About 5 ml is expelled from the tubing segment 102 through the separator 302 to scrub position of Valve 304, port 2 at about 6 ml/min (up-flow direction through the separator 302).
• 3b.13 Valve 200 is switched to "air" position (port 1). About 10 ml of air is aspirated into the tubing segment 102 at about 18 ml/min.
• 3b.14 Valve 200 is switched to separator position. About 10 ml of air is expelled from the tubing segment 102 to waste (valve 304, port 6) at about 15 ml/min.

• 4a.1. Two position valve 310 is switched. The flow direction through the separator 302 is reversed for Bi-213 elution (down flow, ports 1 and 2 on two-position valve 310 are connected)
  
  Note, that flow direction through the separator 302 is reversed relative to Ac-225 load and scrub (wash) steps.
• 4a.2 Multiposition valve 304 is set in the Bi-213 product position (port 3)
• 4a.3. An air segment is pulled into the tubing segment 102 through valve 200, port 1, preferably about 2 ml at about 10 ml/min flow rate.
• 4a.4. Eluent is pulled into the tubing segment 102 through valve 200, port 3, preferably about 8 ml portion of about 0.1 M sodium acetate at about 18 ml/min flow rate.
• 4a.5. The eluent is expelled from the tubing segment 102 through the separator 302 (valve 200, port 6) to product vial 306 (valve 304, port 3), preferably about 8 ml of about 0.1 M sodium acetate at about 1 ml/min flow rate.
• 4a.6. Air is dispensed, preferably about 1.9 ml at about 4 ml/min flow rate.
• 4a.7. Valve 200 is switched to waste (port 7) and remaining air (about 0.1 ml) is expelled from the tubing segment 102 to waste, followed by about 0.5 ml of carrier solution. The flow rate is about 10 ml/min.

At this point the Bi-213 product is eluted from the anion exchange membrane in the separator 302 and collected in the product vial 306. The separator 302 and all transport lines are flushed with air. The system is ready for the next separation run.

• 4b.1 Valve 200 is switched to air position (port 1). Valve 304 is switched to product position (port 3).
• 4b.2 Air is aspirated into the tube segment 102 through valve 200, port 1, preferably about 1 ml at about 10 ml/min.
• 4b.3 Valve 200 is switched to eluent position (port 4). About 4 mL of about 0.1 M NaOAc is pulled into the tubing segment at about 20 ml/min.
• 4b.4 Two-position valve 310 is switched to down-flow position (ports 1 and 2 are connected). Note that flow direction is opposite relative to Ac-225 load and membrane scrub(wash) steps.
• 4b.5 Valve 200 is switched to separator position (port 6). About 5 ml is expelled from the tubing segment 102 through the separator 302 to product vial 308 (Valve 304, port 3) at about 1 ml/min (down-flow direction).
• 4b.6 Valve 200 is switched to "air" position (port 1). About 5 ml of air is aspirated into the tubing segment 102 at about 18 ml/min.
• 4b.7 Valve 200 is switched to separator position. About 5 ml of air is expelled from the tubing segment 102 to product vial 308 (port 3, valve 304) at about 15 ml/min.

After the membrane is replaced or possibly washed for reuse, the instrument is ready to proceed with a next separation.

All reagent and transport lines were constructed from 0.8 mm i.d. FEP Teflon tubing (Upchurch Scientific, Oak Harbor WA). The holding coil was made of 1.6 mm i.d. FEP tubing (Upchurch). The length of the tubing segment 102 was 6.25 m (calculated volume 12.5 ml) and wound into a coil. The purpose of the tubing segment 102 is to accommodate reagent solutions required in the separation run without their introduction into the syringe pump. All necessary reagents including the "cow" solution were placed around Valve 200 . Valve 304 was used to collect the effluents into separate vials or direct them to waste.

The efficiency of the automated separations was monitored using a portable high purity germanium (HPGe) gamma-spectroscopy unit. The Bi-213 product fractions, scrub fractions, and Ac-225 "cow" solutions were collected and counted to estimate Bi-213 recovery and purity, and Ac-225 losses during the separation run. The counting experiments were performed using standard procedures.

An experiment was conducted using the apparatus and stacked method of the present invention to demonstrate separation of about 3 milli-curie Bi-213 from Ac-225.

A 25 mm anion exchange membrane disc (3M company, St. Paul MN) was used as separation media in the separator 302. Because of the low activity of the radionuclides, low pressure valves (34.5 bar (500 psi) gas pressure rating) were used.

Table E1-1 and FIG.'s 4a, 4b show results. The eluent fractions were collected in 1 ml increments in order to evaluate the elution profile of Bi-213. The gamma spectroscopy indicated that Ac-225 "cow" solution was quantitatively (within counting errors) recovered in the original storage container. Good product recovery was achieved using 0.1 M sodium acetate eluent. FIG. 4a shows that Bi-213 elution provides about 73% of Bi-213 activity recovered in first ml of the eluent solution. FIG. 4b shows that over 87% of the Bi-213 product was recovered with 4 ml of the sodium acetate eluent. Solution Ac-225 Bi-213 Feed 3 ml 0.5 M HCl tracer Ac225/Bi213 102% 0% Scrub 4 ml 0.005 M HCl Not detected 1.51% Strip 8 ml 0.1 M NaOAc Not detected 90.3% Membrane Not detected 4.36% Product Balance 96.17%

An experiment was conducted with the apparatus and stacked method of the present invention wherein the separator 302 had a miniature anion exchange column instead of an anion exchange membrane. Valves were as in Example 1.

The miniature sorbent column was constructed from 1.6 mm i.d. FEP tubing (Upchurch) using 1/4-28 flangeless connectors and fittings (Upchurch); and 25 µm FEP frits (Alltech Associates, Deerfield, IL). The length of the column was 3 cm (calculated volume 0.06 ml). The column was packed with surface derivatized styrene-based strongly basic anion exchanger particles (particle size 50 µm) in Cl^- form obtained from OnGuard-A™ column (Dionex Corporation, Sunnyvale CA).

The volume of an air segment used to separate aspirated zones was 2 ml. Reagent volumes and flow rates for the column separation experiment are listed in Table E2-1.

Just as before, the flow direction for the elution step was reversed. The eluent fractions were collected in 1 ml increments. The separation was performed using a 3 ml of the cow solution containing tracer quantities of Ac-225/Bi-213. However, only ca. 2 ml of the cow solution was used in the run (due to a programming error). In order to assess the effectiveness of the separation procedure, the used portion of the cow was recovered in a separate vial. Step Reagent Volume Flow Rate Column conditioning 0.5 M HCl 2 ml 1 ml/min Cow load 0.5 M HCl tracer Ac225/Bi213 c.a. 2 ml 1 ml/min Scrub 0.005 M HCl 0.5 ml 1 ml/min Bi elution (flow direction reversed) 0.1 M NaOAc 3 ml 0.5 ml/min

Results of the automated Bi-213 separation using a miniature ion exchange column are given in Table E2-2. Solution Ac-225 Bi-213 Feed 2 ml 0.5 M HCl tracer Ac225/Bi213 101% 0% Scrub 0.5 ml 0.005 M HCl Not detected 1.51 % Strip 3 ml 0.1 M NaOAc Not detected 94% Column Not detected 5.7% Product Balance 101.2%

Just as in case of a membrane separation, the Ac-225 "cow" recovery was quantitative within the counting errors. Good product recovery was obtained. First ml of the product eluent contained ca. 70% of the product activity. Approximately 94% of the Bi-213 product was recovered with 3 mL of 0.1 M sodium acetate eluent. These preliminary results demonstrate that automated Bi-213 production can be efficiently carried using a miniature ion exchange column. The choice of the sorbent (surface functionalized, non porous ion exchanger beads) provides fast exchange kinetics. Moreover, it was observed that miniature column is very efficiently flushed with air which removes any interstitial liquid. This is advantageous for the recovery of a "cow" solution. Furthermore, the dead volumes of the column reactor were substantially smaller relative to a membrane disk used in a previous experiment. This is desirable for high separation factors.

In supplementary experiments we evaluated performance of a commercially available tapered microcolumn (0.05 ml volume) packed with On-Guard-A ion exchange beads. The "cow" and scrub solutions were loaded on the narrow end, while the elution step was carried out from wider end. Experimental results (Bi recovery and elution profile) were comparable with those obtained using non-tapered column.

Experiments were conducted to demonstrate automated separation of Bi-213 using about 16 mCi of Ac-225. The ~16 mCi of ²²⁵Ac was received from ORNL as a dried chloride salt in a V-vial as shown in Table 3-1. The ²²⁵Ac was dissolved in 3.1 ml of 0.5M HCl and sampled. The ²²⁵Ac received was found to be 16.35 mCi. The ²²⁵Ac to ²²⁵Ra ratio was 391 as compared to product ²²⁵Ac of >1,068. The ²²⁵Ac to ²²⁹Th ratio was determined as 2.54 E+4. The ICP analysis shows contamination from Al and Cr. This contamination is equal to 0.07 mg Al and 0.005 mg Cr per mCi of ²²⁵Ac.

A 25 mm anion exchange membrane disc (3M Company, St. Paul MN) was used as separation media in the separator 302 as in Example 1. However, high pressure valves (5000 psi gas pressure rating) were used because of the greater radionuclide activity compared to Examples 1 and 2.

The experimental procedure used in this experiment was sequential, mimicking a manual operation. Thus, Ac-225 "cow" and scrub (wash) solutions were not stacked in the tubing segment 102 as in Examples 1 and 2, but rather "cow" and scrub solutions were aspirated and delivered sequentially. Isotope Activity Ratio Ac-225/Isotope At 10:34 12/16/97 Ac-225 16.35 mCi 1 Bi-213 17.2 mCi ∼1 Ra-225 0.059 mCi 391 Th-229 <0.64 µCi 2.54E+4 Pu239/240 <0.062 mCi >264 ICP Analysis

(3 mL feed: 16.35mCi) Al 391 ppm Cr 27 ppm Other < detectable

A 0.25 ml air segment was placed into the tubing segment 102 in the beginning of the separation procedure and was not expelled until the end of the separation run. The volume of the air segment used to separate zones in the holding coil was 1 ml. This air segment was propelled through the membrane to recover solutions. Following the solution delivery, additional volume of air (10 ml) was pulled into the coil and delivered through the membrane to ensure complete removal of liquid from the membrane disc and transport lines. The separation run starts with the membrane disk and all transport lines filled with air.

The membrane disc is positioned vertically, luer adapter side at the top. The 3M disc was washed with 0.005M HCl to remove the interstitial feed and acid. The sorbed ²¹³Bi chloro complexed anion was then eluted at 1 ml/min increments using 0.1M NaOAc, pH 5.5. The 3M web (after elution), the 4 ml of wash solution, and each of the 1 ml effluent fractions were sampled and counted using the portable GEA system. A sample (10 µl) of the first 1 ml of effluent was sent to the analytical laboratory for complete analysis; and the balance of the 1 ml was used for linking studies. The above test was repeated after approximately 3 hours of ²¹³Bi in-growth. The conditions and results are shown in Table E3-2. Conditioning 5 ml of 0.5M HCl @ 10 ml/min. ²²⁵Ac "Cow" 3 ml of 0.5M HCl, ∼16 mCi ²²⁵Ac, @ 4 ml/min. Wash Solution 4 mL of 0.005M HCl, @ 10 ml/min. Elution 4 mL of 0.1M Na acetate, pH ∼5.5, @ 1 ml/min.    Results (Table E3-3) for an elution test using the method and apparatus of the present invention: Elution,1 ml #1

%Bi 1 69.8 2 11.9 3 4.0 4 2.1 3M Web 8.6 Wash,4 ml 2.5 Material 99.9

Experimental procedure outlined above was applied to separate Bi-213 from 16 mCi of Ac-225. Approximately, 88% of the ²¹³Bi was recovered in 4 mL of 0.1M NaOAc, pH 5.5, FIG. 5a, 5b. Approximately 80% of the recovered Bi-213 was present in the first milliliter of the eluent solution.

Two experiments were conducted demonstrating linking of the ²¹³Bi products from Example 3. The two proteins included a canine monoclonal antibody CA12.10C12 which is reactive with the CD45 antigen on hematopoietic cells and recombinant streptavidin (r-Sav). The r-Sav was midified with 1.5 CHX-B DTPA chelates/molecule. In each labeling/linking reaction, a 200 µg quantity of r-Sav in 120 µl phosphate buffered saline solution (PBS) was used. The anti-CD45 canine monoclonal antibody was modified with a 3.6 CHX-B DTPA chelates/molecule. In each reaction, a 100 µg quantity of monoclonal antibody in 120 µl of PBS was used. The 120 µl of protein solution was mixed with 100 µL of 1M NaOAc, pH 5, and ∼300 µl of ²¹³Bi from the first fraction of eluent. An initial determination of the amount of radioactivity was determined using a Capintec CRC-7 dose calibrator. After 10 minutes reaction time, the mixture was placed on the top of a NAP-10 (G-25) size exclusion column and eluted. Elution fractions (200 µl of PBS each) were collected in separate micro centrifuge tubes and counted. The empty reaction vial and the eluted NPA-10 column were also counted. The empty reaction vial and the eluted NPA-10 column were also counted. The counting results were decay corrected for the half-life of ²¹³Bi, and a radioactivity balance was determined. Results from two runs are shown in Tables 4-1 and 4-2. Protein - 120 µl (200 µg r-SAv) Buffer - 100 µl, 1 M NaOAc, pH 4 300 µL, ²¹³Bi containing 2.36 mCi Results: Time Capintec CRC-7 Reading Corrected Reading % of Initial Initial 11:50 256 256 1-1 12:21 0.2 0.3 0.1 1-2 12:22 0.0 0 0 1-3 12:23 0.2 0.3 0.3 1-4 12:25 0.5 0.83 0.3 1-5 12:27 8.3 14.2 5.5 1-6 12:30 32.3 56.7 22.1 1-7 12:32 46.2 84 32.8 1-8 12:34 32.3 61 23.8 1-9 12:35 13.8 26.3 10.3 Column 12:39 4.0 8.2 3.2 251.7^A 1-7 Rerun 12:37 43.0 84.3 Balance ^A 98.3% Activity Protein - 120 µl (100 µg anti-CD45 canine mAb) Buffer - 100 µl. 1 M NaOAc, pH 4 200 µL, containing 1.9 mCi ²¹³Bi Results: Time Reading Corrected Reading % of Initial Initial 2:06 207 207 2-1 2:34 0.2 0.3 0.15 2.2 2:35 0.1 0.15 0 2-3 2:36 0.1 0.15 0 2-4 2:37 0.1 0.17 0.08 2-5 2:37 6.1 9.5 4.7 2-6 2:38 24.6 39.0 19.3 2-7 2:39 33.0 52.8 26.2 2-8 2:39 22.2 35.5 17.6 2.9 2:40 7.4 12.0 6.0 2-10 2:40 2.4 3.9 1.9 2.11 2:41 1.7 2.8 1.4 Column 2:31 20.9 30.0 14.8 Vial 2:41 9.4 15.4 7.6 201.7 99.7% Activity Balance

After purification on NAP-10 columns. 72% (1.7 mCi) of the ²¹³Bi labeled with r-SAv, and 69% (1.31 mCi) labeled with anti-CD45 canine mAb, 12. 10C12. These percentages are derived from the data in Tables 4-1 and 4-2 and are sufficient for therapeutic use.