AU2002310305B2 - Process for the recovery of a radioisotope from an irradiated target - Google Patents

Process for the recovery of a radioisotope from an irradiated target Download PDF

Info

Publication number
AU2002310305B2
AU2002310305B2 AU2002310305A AU2002310305A AU2002310305B2 AU 2002310305 B2 AU2002310305 B2 AU 2002310305B2 AU 2002310305 A AU2002310305 A AU 2002310305A AU 2002310305 A AU2002310305 A AU 2002310305A AU 2002310305 B2 AU2002310305 B2 AU 2002310305B2
Authority
AU
Australia
Prior art keywords
target
dissolution medium
radioisotope
sonication
irradiated
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Ceased
Application number
AU2002310305A
Other versions
AU2002310305A1 (en
Inventor
Michael Drobnik
Noboru Minamiguchi
Shintarou Ogata
Gerald Wilgus
Hirohiko Yamauchi
Toshiyuki Yoshioka
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nihon Medi Physics Co Ltd
Original Assignee
Nihon Medi Physics Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Nihon Medi Physics Co Ltd filed Critical Nihon Medi Physics Co Ltd
Publication of AU2002310305A1 publication Critical patent/AU2002310305A1/en
Assigned to NIHON MEDI-PHYSICS CO., LTD. reassignment NIHON MEDI-PHYSICS CO., LTD. Request for Assignment Assignors: MEDI-PHYSICS, INC.
Application granted granted Critical
Publication of AU2002310305B2 publication Critical patent/AU2002310305B2/en
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21GCONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/04Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
    • G21G1/10Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by bombardment with electrically charged particles
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21GCONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G4/00Radioactive sources
    • G21G4/04Radioactive sources other than neutron sources
    • G21G4/06Radioactive sources other than neutron sources characterised by constructional features
    • G21G4/08Radioactive sources other than neutron sources characterised by constructional features specially adapted for medical application

Landscapes

  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Particle Accelerators (AREA)
  • Radiation-Therapy Devices (AREA)
  • Medicines That Contain Protein Lipid Enzymes And Other Medicines (AREA)
  • Saccharide Compounds (AREA)

Description

WO 02/099816 PCT/US02/17678 Target Process Field of the Invention.
The present invention relates to an improved process for the recovery of a radioisotope from an irradiated target, such as a target from a cyclotron. The improvement comprises sonication of the target dissolution medium.
Background to the Invention.
It is known to prepare radioisotopes by bombardment of a non-radioactive target with particles, especially protons in a cyclotron, to convert a small percentage of the irradiated target surface into one or more radioisotopes. The radioisotope is then separated from the target by either: complete dissolution of the target plus radioisotope, (ii) partial dissolution of the target plus radioisotope, such that only the target surface containing the radioisotope is removed, leaving the target ready for further irradiation and purification cycles.
In both cases, the dissolution medium is subjected to further purification steps involving one or more selective separation techniques such as ion exchange chromatography, solvent extraction or precipitation. Method (ii) may employ controlled conditions such as limited concentrations or amounts of chemicals, or solvents in which only the target surface has significant solubility. Method (ii) is preferred where the target is relatively precious, eg. an artificially enriched level of a particular isotope to improve the yield of the desired radioisotope product, or the target comprises a precious metal. Method (ii) also has the advantage that there are lower levels of the non-radioactive target material present in solution. This makes the subsequent separation and purification of the radioisotope more straightforward. This is particularly useful when the radioisotope is to be used for medical applications involving administration to the human body (ie. a radiopharmaceutical), where removal of the potentially toxic levels of the non-radioactive target material (typically a heavy metal) is highly desirable.
US 4487738 discloses that carrier-free 6 7 Cu can be produced by proton spallation of a zinc oxide target with subsequent chemical separation and purification. The zinc oxide WO 02/099816 PCT/US02/17678 target is irradiated with protons having an energy of 800 MeV, and the irradiated target dissolved in concentrated acid. The 67 Cu is then separated by a series of ion exchange chromatography and precipitation procedures.
US 3993538 discloses that 201 T1 suitable for use as a myocardial imaging radiopharmaceutical can be prepared by bombardment of a thallium target with 20-30 MeV protons via the reaction 203 T1 (p,3n) 201 Pb. The 2 01 Pb radioisotope formed has a halflife of 9.4 hours, and decays to the desired 201 T1. After irradiation, the target is completely dissolved in concentrated nitric acid forming soluble lead and thallium nitrates.
Evaporation and further chemical purification steps gave the desired 201T product.
Use of target materials comprising two or more metals is known. Thus, US 4297166 discloses a thallium target for the production of the radioisotope 201 T1, in which the 23Tl target material is electroplated onto an electroconductive support such as copper or silver. The electroconductive support has two advantages. First, it can be used to provide efficient cooling of the thallium layer (via a circulating fluid such as water or gas).
Second, it can facilitate target processing, since only the thallium target layer and radioisotope formed is dissolved during processing. This makes the purification of the 2 01 T radioisotope more straightforward, since the processed target solution does not contain substantial amounts of the non-radioactive electroconductive support (eg. copper).
After chemical processing, the target electroconductive support can then simply be reused by electroplating with more thallium, and subsequent proton bombardment.
JP 04-326096 A (1992) discloses a cyclotron target which comprises silver plated onto a copper support. The desired target material 68 Zn) is plated onto the silver, and then irradiated with a proton beam. The silver layer means that no copper is present in the acid processing solutions, ie. the recovery and purification of the desired 68 Zn radioisotope is simplified.
US 6011825 discloses a cyclotron method for the production of radioisotopes, especially 6Cu. The 64Cu is produced by proton bombardment of a target which comprises 6Ni deposited onto a gold substrate. The irradiated 64Ni together with the 64CU product are dissolved off the gold disk in 6.0 M hydrochloric acid at 90 °C.
ID
0 Prior art chemistry used to process targets therefore typically employs concentrated solutions of mineral acids (eg. hydrochloric acid), or powerful oxidising d agents such as hydrogen peroxide. Acids which are also powerful oxidising agents, such as concentrated nitric acid may also be used. Heating is often also applied. Such forcing C1 5 conditions are understandable given that the target material to be dissolved may be a relatively unreactive metal such as rhodium. The difficulty of achieving the required dissolution of the target may also mean that extended contact times are required. For radioisotopes, all such target processing time is time during which radioactive decay of Cthe desired product is occurring, ie. product is being lost. The shorter the half-life of the radioisotope product, the bigger the potential problem this represents.
An additional problem with the use of such prior art forcing conditions is that careful handling of the radioactive process solution is required due to the chemical hazard as well as the radioactive hazard. In addition, when it is intended that only the surface of the irradiated target should be dissolved, such conditions increase the likelihood of dissolution of other elements of the target e.g. the electroconductive support. It is also the case that the process solutions consequently require more chemical processing, eg. to neutralise the strong acid, before proceeding further with the isolation and purification of the radioisotope.
There is therefore a need for an improved method of processing such radioisotope targets under milder conditions.
The Present Invention In a first aspect, the present invention provides a process for the production of a preparation containing a radioisotope from an irradiated target comprising: providing an irradiated target having a support material comprising silver; and a surface solid material comprising said radioisotope; wherein the surface solid material is disposed on said support material; (ii) treating the irradiated target with a dissolution medium; N]\Melbourne\Cases\Patent\51000-51999\P51497.AU\Specis\P51497.AU Specification 2006-12-18.doc 21/12/06 3
IO
c (iii) applying sonication to the dissolution medium whilst it is in contact with Sthe surface solid material of said irradiated target so that a portion of the radioisotope in the surface solid material dissolves in the dissolution material; (iv) isolating the dissolution medium containing the radioisotope; subjecting the dissolution medium to purification, thereby producing a Spreparation containing the radioisotope; and C (vi) optionally repeating steps (ii) to wherein the applying step is carried out under milder conditions CN compared to other conditions without sonication.
The target of the present invention suitably comprises a 'surface solid material' which, when irradiated with charged particles reacts to give one or more radioisotopes.
The surface solid material is thus that part of the irradiated target which reacts during the irradiation to give the desired radioisotope product. The charged particles are suitably derived from an accelerator, preferably a cyclotron. The charged particles may be protons, deuterons, alpha, 3He or electrons, and are preferably protons. Suitable surface solid materials include metals such as thallium, cadmium, rhodium, molybdenum or zinc, or metal oxides such as zinc oxide, strontium oxide or gallium oxide, plus such materials containing an artificially enriched level of a particular isotope. Preferred surface solid materials are those which are suitable for plating (eg. by electroplating or electroless deposition) onto a support material.
The target comprises a 'support material' onto which is provided an outer coating of the surface solid material to be irradiated. The support material functions to provide effective cooling of the irradiated surface solid material during the irradiation, and permits separation of the radioisotope product, leaving the support material substantially unchanged, ready to be reused. The 'support material' comprises a material which is a good conductor of heat and/or electricity, ie. electroconductive such as silver. The support material is suitably of a shape and size that permits facile N,\Melbourne\Cases\Patent\51000-51999\P51497.AU\Specls\P51497.AU Specification 2006-12-1B.doc 21/12/06 production, as well as ease of attachment and detachment from the target assembly. A preferred shape of the support material is a plate.
The support material may comprise silver, but most preferably is made entirely of silver, since silver has advantages over copper. The non-radioactive copper of a copper support material can dissolve in acidic dissolution media (especially nitric acid).
This makes purification and isolation of the radioisotope more difficult, by eg.
increasing the viscosity of the dissolution medium, making solvent extraction of the radioisotope product more difficult. Hence one advantage of the use of silver as the support material is that silver does not dissolve readily in nitric acid, which makes subsequent purification of the radioisotope easier. Silver does, however, have a finite Ni\Melbourne\Cases\Patent\51000-51999\P51497.AU\Specis\P51497.AU Specification 2006-12-18.doc 21/12/06 4a WO 02/099816 PCT/US02/17678 solubility in concentrated hydrobromic acid, hence is less advantageous when the dissolution medium comprises concentrated hydrobromic acid.
In addition, when copper is the support material, and the target is subjected to proton bombardment, any protons which penetrate the surface solid material and are captured by the copper lead to the production of the potential impurity radioisotope At least a portion of any 65 Zn formed may dissolve in the dissolution medium, especially when the dissolution medium comprises aqueous acid, since Zn(0) dissolves in acid. 65 Zn has a half-life of 244 days, and hence both the copper target support material and the dissolution medium are, in effect, contaminated for a prolonged period. For the copper support plate, the period necessary to await radioactive decay of the 65 Zn is so long (minimum 10 half-lives), that corrosion of the copper support is likely to occur during the storage period to allow for decay. Hence, in effect the copper plate cannot be reused.
Also, any 6Zn contamination of the dissolution medium means that, even after the desired radioisotope product has been isolated or extracted, the dissolution medium must be kept for prolonged periods to await decay of the 65 Zn. In contrast, when the support material comprises silver, any protons captured by the silver generate the radioisotopes 05 Ag and o106Ag, which have half-lives of 41.3 and 8.5 days respectively. The result is that such silver target supports can be reused after an appropriate decay period (suitably of approximately one year).
Radioisotopes which can be prepared using the present process include 201 T1, 8 3 Rb, 88Y, 88Zr, 96 Tc, 97 Ru, 1 1 n, 67 Ga, 68 Ge, 57 Co, 1 03 Pd, 62 Cu and 67 Cu. The process is especially useful for 201 T1, 111n, 67Ga, 03 Pd, 57 Co and 62Cu, particularly 201 T1. The present invention may also be applied to the production of parent radioisotopes which decay to give positron emitters useful as radiopharmaceuticals, as used in so-called radioisotope generators. Suitable parent radioisotopes (with positron-emitting daughter) include: 8 2 Sr 82 Rb), 68Ge 68 Ga) and 62 Zn 62
CU).
When the target of the present invention includes a support material, the support material may optionally further comprise an 'inert layer' at its' outer surface. The inert layer suitably forms an unreactive layer interspersed between the surface solid material and the bulk of the support material. The inert layer comprises a material which is WO 02/099816 PCT/US02/17678 essentially insoluble in the dissolution medium, and thus protects the support material from partial dissolution when the irradiated target is processed. Preferably, the inert layer is provided at a thickness of less than 10 lan, to maximise the transparency of the inert layer to the charged particles used in the target irradiation, and hence minimise potential radioisotopic impurities arising due to capture of the charged particles by the inert layer itself. The inert layer functions to minimise dissolution of the target support material, together with any radioisotopic impurities formed via irradiation of the target support material (eg. the low energy gamma emitters 05 Ag or 10 6 mAg from a silver support material), into the dissolution medium. Any such dissolution could introduce potential impurities into the desired radioisotope product. Suitable inert layers comprise unreactive metals such as silver, gold, platinum, tungsten, tantalum or nickel. When the surface solid material is zinc, and the support material is copper, then nickel represents a preferred inert layer material. Preferably the inert layer comprises gold or silver, most preferably gold.
Gold has the advantage that it has greater passivity (ie. is less reactive chemically), and is most suitable for accepting the plated solid material of the target.
The sonication of the present invention may suitably be provided either by an ultrasonic probe which is immersed in the dissolution medium, or via external sonication of the container or bath containing the dissolution medium. Suitable sonication probes and sonication baths are commercially available.
The sonication apparatus converts the frequency of the power supply (eg. 50 to Hz) to high frequency 20 kHz electrical energy. This high frequency electrical energy is in turn converted via a transducer in the sonication apparatus to mechanical vibrations (either of the sonication probe or sonication bath). The mechanical vibrations are intensified by the sonication apparatus, thus creating pressure waves within the dissolution medium. These pressure waves form microbubbles in the dissolution medium, which expand during the negative pressure phase, and implode violently during the positive pressure phase. This phenomenon is known as cavitation, and causes the molecules in the dissolution medium to become intensely agitated. Suitable sonication probes have a level of cavitation at the horn tip of ca. 500 W/cmz, and a frequency of ca. 20 kHz, whereas suitable sonication baths may have a lower cavitation level of ca. 1 W/cm 2 at the horn tip, with a frequency of 36-42 kHz.
WO 02/099816 PCT/US02/17678 The sonication bath may comprise any material compatible with the dissolution medium, but is preferably TeflonTM. For the production of 201 T1, it has been found that there are separation distance effects (see Examples 1 and Thus, whilst the dissolution can be accelerated using an ultrasonic immersion probe, the irradiated 20 3 T-enriched target material in proximity to the probe was found to be dissolved smoothly, whereas those parts of the irradiated target more distant from the probe were harder to dissolve.
Thus, an immersion probe gives less uniform effects due to inhomogeneity, whereas ultrasonic baths give more uniform or homogeneous performance. It is therefore preferred that, when the size and geometry of the target is suitable for immersion of the whole target in a sonication bath, that such a sonication bath is used, ie. that external sonication of the dissolution medium is applied. External sonication also gives shorter dissolution times (see Example and is more convenient since there is no need to wash or decontaminate the immersion probe between preparations. Internal sonication may, however, be the best option when the size and geometry of the target is such that only a portion of the target can be immersed in a sonication bath.
The shorter dissolution times of the present invention are believed to result from improved kinetics of mixing the dissolution medium with the surface solid material, due to the cavitation of the dissolution medium. This confers particular improvements where the solubility of the irradiated target material in the dissolution medium is low, especially when it is necessary to dissolve the whole irradiated target. For the radioisotope product, any reduction in the target processing time results in an improved yield, because there is reduced loss due to radioactive decay during target processing. Clearly, this problem is exacerbated the shorter the half-life of the radioisotope, such as positron emitters which may have half-lives of the order of a few hours. Shorter processing times also reduce the risk of radiation dose to the operator, by reducing the time spent in target processing.
The process of the present invention also permits the use of much milder conditions for processing the irradiated target. This includes the use of more dilute solutions of acids and/or oxidants, lower temperatures, and shorter reaction times. In the case of a 20 3 T1 target for the production of 20T11, dilute aqueous nitric can be used as the dissolution medium instead of the conventional concentrated nitric acid solution (7 molar).
By the term 'dilute aqueous nitric acid' is meant an aqueous solution which is 0.5 to WO 02/099816 PCT/US02/17678 molar; preferably 0.8 to 1.2 molar, most preferably about 1 molar. The use of such dilute nitric acid results in a significant reduction in the undesirable dissolution of the silver or copper support of the irradiated target, and thus facilitates purification of the 201 T1 product.
The use of such milder dissolution media also has the advantage that it presents less of a corrosion hazard to the plant used to carry out the process.
In a second aspect, the present invention provides an improved process for the production of 201 T1. The improved process comprises the use of the sonication process as described above, together with a target which comprises 20 3 Tl as the surface solid material, where the target is irradiated with protons, and the dissolution medium is 'dilute nitric acid' as defined above. The support material preferably comprises silver, and most preferably is made entirely of silver metal. The use of silver as the support medium has the advantages described above, and the sonication method provides a shorter processing time, which gives improved yields of 201
T.
The radioisotope 201Tl illustrates an additional reason why shorter processing times are important. It is typically produced by proton beam irradiation of a 20 3 T-enriched solid target material, giving 201 Pb via a (p,3n) nuclear reaction, and subsequent extraction of the trace amount of 201 Pb produced. The 20 1 Pb initial product decays to 201 T1 with a half-life of 9.4 hours. This means that the 20 1 Pb must be chemically separated from the target 203 T1 before the desired 20 1 T1 can be obtained, since once the 201 T1 decay product has formed, it is chemically identical to the 203 T1 target material, and hence impossible to separate therefrom. Therefore it is critically important to decrease the loss of 20 1 T1 by shortening the time period necessary to achieve the separation of the 2 01 Pb initial product from the 203TI-enriched target material after the completion of the proton irradiation. Thus, in the case of 2 01 T, there is a chemical separation reason why shorter irradiated target dissolution times are important. Theoretical calculations indicate that every one hour increase in the processing period results in a 7.7 loss of yield of the final product 201 T1.
WO 02/099816 PCT/US02/17678 The invention is illustrated by the following Examples: Example 1: Sonication of 203 T1 Targets (Comparative Example).
Three identical silver target plates (ie. targets where solid silver is used as the support material, in the shape of a plate, without an inert layer) were electroplated with 1200mg of 20 3 T1, and immersed into a dissolution medium of 5% aqueous nitric acid solution (molarity ca. 1M) in three separate baths. The dissolution of the 203 Tl-thallium target material was carried out: without sonication, with a 100 W ultrasonic probe, with an ultrasonic bath (300 W).
Dissolution of all the 203 T1 target material took 20 minutes using internal sonication with the immersed probe and 13 minutes using external sonication via the bath Without sonication, ie. method the thallium target material could not be dissolved even at 30 minutes after the addition of the dilute nitric acid.
Example 2: Production of 20 1 T1 Using a Silver-containing Target.
A target having solid silver in the shape of a plate as the support material, and having 1200 mg of 20 3 T-enriched material plated thereon as the surface solid material, was attached to a target support assembly made of aluminium. The target was irradiated for 8 hours with protons, using a proton beam of about 30 MeV. The dissolution of the irradiated 20 3 T-enriched target material was carried out in an ultrasonic bath of 300 W sonication power, with 5% aqueous (ie. ca. IM) nitric acid as the dissolution medium.
The dissolution was complete in about 10 minutes. Hydrochloric acid was then added to the solution.. The separation of the 201 Pb radioisotope produced was achieved by solvent extraction of the irradiated 20 3 TI-enriched target material using diisopropylether.
WO 02/099816 PCT/US02/17678 The 201 Pb separation from the end of the proton bombardment took 1.6 hours to complete. Thus the total processing times compared to those without sonication are as follows: Without sonication Example 2 (Prior art) Dissolution time (min) 25-30 10-15 Evaporation time for the 40 0 nitric acid (min) Total processing time 2.4 hours 1.6 hours Thus, the method of the present invention saves ca. 0.8 hours.
The yield of radioactivity of 201T obtained via this method was 21.9 GBq per target plate at 15 hr after the completion of the 201 Pb separation.
Example 3: Production of 2 01 T1 using a Copper-containing Target.
A target plate made of copper as the support material, and having 203Tl-enriched target material plated onto its' surface was attached to a target support assembly made of aluminium for 2 01 T1 preparation, and irradiated with protons as per Example 2. After dissolution of the target material in a bath using 7 M nitric acid as the dissolution medium, the extraction of the irradiated 20 3TI-enriched target material was performed in the same way as Example 2; except that the separation sequence was as follows: evaporation of the nitric acid, (ii) dissolution of the precipitate (which includes a copper salt) with a small volume (ca. 10 ml) of aqua regia, (iii) addition of hydrochloric acid, and (iv) solvent extraction.
Using this method, it took 2.5 hours to complete the 20 'Pb separation from the end of the bombardment. The amount of radioactivity of 2 01 T1 obtained using this method was 18.8 GBq per plate at 15 hr after the separation of 201 Pb in this reference method. The lower yield of 201 T1 compared to Example 2 can be attributed to:the process period for the 20 'Pb separation is longer than that of Example 2 by 1 hour, the dissolution of significant amounts of the copper plate into the nitric acid dissolution medium reduces the efficiency of the process after the separation of the 201'Pb.
In the claims which follow and in the preceding description of the invention, except where the context requires otherwise due to express language or necessary implication, the word "comprise" or variations such as "comprises" or "comprising" is used in an inclusive sense, i.e. to specify the presence of the stated features but not to preclude the presence or addition of further features in various embodiments of the invention.
It is to be understood that, if any prior art publication is referred to herein, such reference does not constitute an admission that the publication forms a part of the common general knowledge in the art, in Australia or any other country.
H:\adrianag\keep\2002310305speci.doc 31/07/06

Claims (10)

  1. 2. The process of claim 1, where only the surface solid material is dissolved.
  2. 3. The process of claim 1 or 2, where the irradiated target further comprises an inert layer interspersed between the surface solid material and the support material.
  3. 4. The process of any one of claims 1 3, where the irradiated target is irradiated with protons.
  4. 5. The process of any one of claims 1 4, where the dissolution medium comprises an oxidising agent. Ni\Melbourne\Casea\Patent\51000-51999\P51497.AU\Specis\P51497.AU Specification 2006-12-18.doc 21/12/06 12 O 6. The process of any one of claims 1 5, where the dissolution medium comprises N an acid.
  5. 7. The process of any one of claims 1 6, where the sonication is applied via a C 5 sonication probe immersed in the dissolution medium. O 8. The process of any one of claims 1 6, where the sonication is applied via 0 external sonication of the dissolution medium. (N,
  6. 9. The process of any one of claims 1 8, where the surface solid material C1 comprises molybdenum, nickel, rhodium, zinc, zinc oxide, copper, thallium, cadmium or gallium oxide. The process of any one of claims 1 9, where the radioisotope is 201, 83 Rb, 88Y, Zr, 9Tc, 9Ru, 62 Cu, 67 Cu, 'In, 6 7 Ga or 68 Ge.
  7. 11. A process for the production of a preparation containing a 20'T1 radioisotope from an irradiated target comprising: providing an irradiated target having a surface solid material which comprises 203T1 and 201 Pb on a support material; (ii) treating the irradiated target with a dissolution medium which comprises dilute aqueous nitric acid; (iii) applying sonication to the dissolution medium whilst it is in contact with the 23T1 and 20'Pb surface solid material of said irradiated target so that a portion of the 201 Pb radioisotope in the surface solid material dissolves in the dissolution medium; (iv) isolating the dilute nitric acid dissolution medium containing the 201Pb radioisotopes; subjecting the dissolution medium to purification, thereby producing a preparation containing the 201 T1 radioisotope; and (vi) optionally repeating steps (ii) to (iv). N,\Melbourne\Cases\Patent\51000-51999\P51497.AU\Specis\P51497.AU Specification 2006-12-18.doc 21/12/06 13
  8. 12. The process of claim 11, where the support material is silver.
  9. 13. The process of claim 11 or 12, where the sonication is applied via external sonication of the dissolution medium.
  10. 14. A process for the separation of a radioisotope from an irradiated target substantially as herein described with reference to either example 2 or 3. N:\Melbourne\CaaeB\Patent\S1000-51999\PS149AtI\pecis\PS1497.A Specification 2006-12-18.doc 21/12/06 14
AU2002310305A 2001-06-05 2002-06-04 Process for the recovery of a radioisotope from an irradiated target Ceased AU2002310305B2 (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
US29598001P 2001-06-05 2001-06-05
US60/295,980 2001-06-05
PCT/US2002/017678 WO2002099816A2 (en) 2001-06-05 2002-06-04 Process for the recovery of a radioisotope from an irradiated target

Publications (2)

Publication Number Publication Date
AU2002310305A1 AU2002310305A1 (en) 2003-05-08
AU2002310305B2 true AU2002310305B2 (en) 2007-01-25

Family

ID=23140059

Family Applications (1)

Application Number Title Priority Date Filing Date
AU2002310305A Ceased AU2002310305B2 (en) 2001-06-05 2002-06-04 Process for the recovery of a radioisotope from an irradiated target

Country Status (5)

Country Link
JP (1) JP4231779B2 (en)
KR (1) KR100858265B1 (en)
CN (1) CN1264170C (en)
AU (1) AU2002310305B2 (en)
WO (1) WO2002099816A2 (en)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4571109B2 (en) * 2006-09-12 2010-10-27 行政院原子能委員会核能研究所 Production process of radioisotope thallium-201
JP4674727B2 (en) * 2006-10-27 2011-04-20 行政院原子能委員会核能研究所 Separation apparatus for radioisotope thallium-201
EP2131369A1 (en) * 2008-06-06 2009-12-09 Technische Universiteit Delft A process for the production of no-carrier added 99Mo
ES2674360T3 (en) * 2013-06-27 2018-06-29 Mallinckrodt Nuclear Medicine Llc Germanium-68 generation process
CN108780672B (en) 2016-04-21 2022-03-01 株式会社钟化 Support substrate for radioisotope production, target plate for radioisotope production, and method for producing support substrate
CN108780670B (en) 2016-04-28 2022-04-05 株式会社钟化 Beam intensity conversion film and method for manufacturing beam intensity conversion film
EP3637437B1 (en) * 2017-06-09 2022-11-16 Kaneka Corporation Target for proton-beam or neutron-beam irradiation and method for generating radioactive substance using same
EP3662728B1 (en) * 2017-07-31 2024-05-08 Triumf Inc. System, apparatus and method for producing gallium radioisotopes on particle accelerators using solid targets and ga-68 composition produced by same
IT201700102990A1 (en) * 2017-09-14 2019-03-14 Istituto Naz Fisica Nucleare METHOD FOR OBTAINING A SOLID TARGET FOR THE PRODUCTION OF RADIOPHARMACEUTICALS
JP6554753B1 (en) * 2019-03-11 2019-08-07 株式会社京都メディカルテクノロジー Technetium 99m isolation system and technetium 99m isolation method
JP7506055B2 (en) * 2019-03-28 2024-06-25 住友重機械工業株式会社 Target irradiation system and method for recovering radioisotopes from solid targets - Patents.com
US20210225546A1 (en) * 2020-01-17 2021-07-22 BWXT ITG Canada, Inc. System and method for germanium-68 isotope production

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3007814A (en) * 1956-10-04 1961-11-07 Bendix Corp Method of cleaning radioactive articles
US4297166A (en) * 1978-02-20 1981-10-27 Nihon Medi-Physics, Co., Ltd. Thallium-carrying target material and its production
FR2600203A1 (en) * 1986-06-17 1987-12-18 Lemmens Godfried Process for the decontamination of materials with radioactive contamination
FR2642889A1 (en) * 1989-02-07 1990-08-10 Doryokuro Kakunenryo Process for cleaning containers contaminated with a radioactive substance

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3007814A (en) * 1956-10-04 1961-11-07 Bendix Corp Method of cleaning radioactive articles
US4297166A (en) * 1978-02-20 1981-10-27 Nihon Medi-Physics, Co., Ltd. Thallium-carrying target material and its production
FR2600203A1 (en) * 1986-06-17 1987-12-18 Lemmens Godfried Process for the decontamination of materials with radioactive contamination
FR2642889A1 (en) * 1989-02-07 1990-08-10 Doryokuro Kakunenryo Process for cleaning containers contaminated with a radioactive substance

Also Published As

Publication number Publication date
CN1522448A (en) 2004-08-18
KR20040028770A (en) 2004-04-03
KR100858265B1 (en) 2008-09-11
JP2004535288A (en) 2004-11-25
WO2002099816A2 (en) 2002-12-12
WO2002099816A3 (en) 2003-05-08
JP4231779B2 (en) 2009-03-04
CN1264170C (en) 2006-07-12

Similar Documents

Publication Publication Date Title
AU2002310305B2 (en) Process for the recovery of a radioisotope from an irradiated target
Meijs et al. Production of highly pure no-carrier added 89Zr for the labelling of antibodies with a positron emitter
JP2023052329A (en) Process for cyclotron production of technetium-99m, system, and apparatus
RU2432632C2 (en) METHOD OF EXTRACTING PURE 225Ac OBTAINED FROM IRRADIATED 226Ra TARGETS
AU2002310305A1 (en) Process for the recovery of a radioisotope from an irradiated target
JP5197603B2 (en) Methods for purifying radium from various sources
KR102518999B1 (en) Metal-molybdate and its preparation method
KR102490805B1 (en) A method for purifying a solution containing 226Ra, a method for producing a 226Ra target, and a method for producing 225Ac
AU763373B2 (en) Production of palladium-103
WO1995027987A1 (en) Production of high specific activity copper -?67¿
US20060023829A1 (en) Medical radioisotopes and methods for producing the same
JP4690328B2 (en) Radium target and production method thereof
US7781744B2 (en) Procedure for the preparation of radioisotopes
EP1892728B1 (en) Process of producing the radioisotope TL-201
RU2332735C1 (en) Method of production of carrier-free radionuclide palladium-103
Mirzaii et al. Electrodeposition iron target for the cyclotron production of 55 Co in labeling proteins
FR2739216A1 (en) METHOD OF TREATING METALLIC ALUMINUM-BASED FUELS AND / OR NUCLEAR TARGETS WITH TETRAMETHYLAMMONIUM HYDROXIDE SOLUTIONS
US5057269A (en) Production of aluminum-26
EP1883079A1 (en) Procedure for the preparation of radioisotopes
US20050252781A1 (en) Method for packing electrochemically-deposited elements
Sadeghi et al. Electroplating/electrodissolution/recovery cycle for rhodium target used for an industrial scale cyclotron production of palladium-l03
Huszâr et al. c H 3 MOSS r

Legal Events

Date Code Title Description
PC1 Assignment before grant (sect. 113)

Owner name: NIHON MEDI-PHYSICS CO., LTD.

Free format text: FORMER APPLICANT(S): MEDI-PHYSICS, INC.

FGA Letters patent sealed or granted (standard patent)
MK14 Patent ceased section 143(a) (annual fees not paid) or expired