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WO2011132266A1 - Procédé et dispositif pour la production d'un radionucléide au moyen d'un accélérateur - Google Patents

Procédé et dispositif pour la production d'un radionucléide au moyen d'un accélérateur Download PDF

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Publication number
WO2011132266A1
WO2011132266A1 PCT/JP2010/057013 JP2010057013W WO2011132266A1 WO 2011132266 A1 WO2011132266 A1 WO 2011132266A1 JP 2010057013 W JP2010057013 W JP 2010057013W WO 2011132266 A1 WO2011132266 A1 WO 2011132266A1
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Prior art keywords
target
radionuclide
accelerator according
producing
rotating body
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Japanese (ja)
Inventor
弘太郎 永津
利光 福村
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National Institutes For Quantum Science and Technology
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National Institutes For Quantum Science and Technology
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Priority to PCT/JP2010/057013 priority Critical patent/WO2011132266A1/fr
Priority to JP2012511443A priority patent/JP5263853B2/ja
Publication of WO2011132266A1 publication Critical patent/WO2011132266A1/fr
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/04—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
    • G21G1/10—Arrangements 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/001—Recovery of specific isotopes from irradiated targets
    • G21G2001/0036—Molybdenum

Definitions

  • the present invention relates to a method and apparatus for simultaneously producing multiple nuclides using an accelerator, and in particular, efficiently producing radionuclides such as molybdenum 99 and technetium 99m, which are in great demand as radiopharmaceuticals regardless of the heat generated during irradiation.
  • the present invention relates to a method and an apparatus for producing a radionuclide using an accelerator.
  • Molybdenum 99 and Technetium 99m Technetium 99m which is used worldwide in nuclear medicine and diagnostic imaging, is the leading role of over 70% of the radioisotopes used in nuclear medicine. This is a nuclide obtained as a daughter nuclide of molybdenum 99 (Mo-99, half-life 66 hours). The nuclide required as a radiopharmaceutical is Tc-99m, and Mo-99 is only the raw material.
  • Tc-99m As a specific method for producing Tc-99m, a technique in which Tc-99m produced by Mo-99 decay is simply eluted and recovered with a physiological saline solution or the like is mainly used. Therefore, the production amount (radioactivity) of Mo-99 dominates the production amount (radioactivity) of Tc-99m. Because this feature can be thought of as squeezing milk (Tc-99m) from dairy cows (Mo-99), this mechanism is called “Milking” or “Generator”, which has been commercialized. It is commercially available.
  • reactor-specific problems include 1) potential operational risks including reactor aging, and 2) conflict with nuclear non-proliferation resistance caused by the use of high-concentration uranium (U-235 is less than 20%)
  • Mo-99 cannot be obtained sufficiently from low concentrations of U).
  • it is not easy to install a nuclear reactor because of the great investment and maintenance costs.
  • nuclear weapons development becomes possible it is also true that there are restrictions on installation depending on the country, and the stable supply of Mo-99 is an international issue. In Japan only, there are many nuclear reactors, but Mo-99 is not produced and is 100% dependent overseas. The importance of establishing a domestic Mo-99 supply system has been accused for some time. However, there is no concrete progress for the reasons mentioned above.
  • the production method as shown here specifically, the activation method using neutrons has a drawback that the yield is only about 1/10 compared with the case of directly obtaining the fission-derived Mo-99. is there.
  • other methods for avoiding problems have been developed, and it is not impossible to obtain a Tc-99m preparation.
  • Non-Patent Document 1 estimates the amount of Tc-99m and Mo-99 generated when Mo-100 is irradiated with protons of energy range 68 ⁇ 8 MeV and Non-Patent Document 2 applies 22 ⁇ 10 MeV protons. It is. Although it is written that any nuclide will be obtained in a yield according to energy, there is no description about a specific irradiation method or apparatus configuration. It is a previous paper on the experimental element that explores so-called feasibility, and can be said to be a report investigating physical phenomena.
  • Non-Patent Documents 3 and 4 describe that radionuclides are simultaneously manufactured by arranging different types of targets in series and simultaneously irradiating them, although the nuclides to be manufactured are different.
  • the target substances are a gas target for 11 C production and a liquid target for 18 F production
  • a 16 O (p, pn) 15 O reaction as a previous stage target.
  • 13 N-labeled compounds such as 13 NH 3 , 13 N 2 O and 13 N 2 are obtained.
  • Non-Patent Document 5 Na-22 and Ge-68 ( ⁇ Ga-68) are formed by using two Mg and Ga targets in series to make two long nuclides at the same time, or Rb and Ga. In the same manner to produce Sr-82 ( ⁇ Rb-82) and Ge-68 ( ⁇ Ga-68).
  • ⁇ indicates a daughter nuclide of the generator.
  • Non-Patent Document 5 when producing the target nuclide, it is necessary to prepare a target substance in some container, in this case, in the capsule in order to compensate for melting.
  • the work (preparation) for sealing the target is very troublesome.
  • the material constituting the capsule itself absorbs the beam energy and attenuates the energy necessary for the original nuclear reaction (particularly for the second stage).
  • miscellaneous nuclides derived from the capsule material are generated, which may adversely affect the quality.
  • the two targets are aligned and fixed, it seems necessary to take them out at the same time.
  • the present invention has been made to solve the above-described conventional problems, and enables efficient production of radionuclides such as molybdenum 99 and technetium 99m, which are in great demand as radiopharmaceuticals, regardless of the heat generated during irradiation. Let it be an issue.
  • Mo-99 and Tc-99m required for practical use are to be obtained by a reaction represented by the nuclear reaction formulas 100 Mo (p, pn) 99 Mo and 100 Mo (p, 2n) 99m Tc)
  • the required current value is 1 to 2 [mA], that is, the estimated heat generation is 40 to 80 [kW]. If recoil neutrons generated by the nuclear reaction are also used, it contributes to the production of Mo-99 and Tc-99m. In that case, the resulting heat generation does not significantly affect the heat generation estimation.
  • the establishment of the irradiation system is determined by how the heat quantity is removed and dispersed on the target side that receives the beam.
  • a practical heat resistance density in a system having a general cooling efficiency is considered to be several hundreds [W / cm 2 ] at most. For example, when 300 [W / cm 2 ] is set, a necessary target area is required. Ranges from 100 to 200 [cm 2 ].
  • the spread of the area means an increase in the amount of target preparation, which further reduces the low specific activity, and there is a concern about the adverse effect on the subsequent processing.
  • another technical problem increases.
  • the target is a replacement type (for example, a turbine rotary type in which the target 70 is disposed on the six rotor blades shown in FIG. 1)
  • the beam 10 is irradiated over a substantially wide range without increasing the diameter.
  • 16 is a beam duct
  • 72 is a rotating shaft
  • 74 is a rotating body.
  • the rotating body 74 can be reduced in weight as being hollow.
  • each target has a thickness capable of absorbing energy of 5 MeV and a beam current of 100 ⁇ A is applied.
  • the rotating body is rotating once per second in FIG. 2 (A) and twice per second in FIG. 2 (B). Regardless of the number of rotations, since the maximum chance (location) where the beam can collide is up to 0 ⁇ ⁇ ⁇ ⁇ from the viewpoint of one target, the time for heat generation is also reduced to less than half.
  • the configuration for rotating the target is not limited to that shown in FIG. 1.
  • six blades of rotating bodies 74A and 74B are arranged opposite to each other, or as shown in FIG. 74 and 12 blades 75 can be arranged in tandem.
  • a target 70 made of a single metal molybdenum thin film having a thickness of 5 mm or less is fixed to a U-shaped holder 78, or as shown in FIG.
  • molybdenum trioxide or a powder-sintered target 70 can be sandwiched and held between thin films 80 made of aluminum or gold that do not get in the way when activated.
  • heat removal is required for any irradiation method of the target.
  • a cooling medium is present on the beam trajectory, it has a beam energy absorption capability proportional to the product of thickness and density, whether it is water or gas. That is, energy prepared for causing the intended nuclear reaction is lost to the cooling medium, and the target reaction may not be sufficiently performed.
  • a low density for example, helium or air is usually used to cool the target on the beam trajectory.
  • An apparatus (for example, a jet outlet) 50 for ejecting these can be installed at an arbitrary position and number inside the irradiation apparatus, and can be used as a driving force for the rotating body 74 while cooling the target 70 as shown in FIG.
  • a small amount of water can be ejected, and the vaporization heat of water during evaporation can be expected to have a great effect on cooling.
  • the gravity and the centrifugal force of the rotating body can be applied to the ejection of the small amount of liquid.
  • a small diameter hole 74X can be arbitrarily formed in the lower part of the cooling water storage area 74W provided at the center of the rotating body to secure a water channel.
  • a rotary blade serving as a target is provided at the outlet of the water channel, and water is supplied from the center of the rotary body toward this. Since the target itself generates heat under the influence of irradiation, all of the small amount of water boils here, and at the same time as the vaporization, the heat of the target can be taken as the heat of vaporization.
  • Optimal control such as the amount of water, can be determined comprehensively, including the hole diameter, channel shape, and rotational speed. Since the final use of cooling water is "heat removal by vaporization", some water leakage does not affect the function (where the water leakage is from and where it is intended to discharge is not essential, it is vaporized from multiple locations Is more efficient). Furthermore, there is an advantage that the manufacture and assembly of the parts constituting this function are remarkably facilitated.
  • the irradiation device needs to be a sealed space except for piping provided for cooling the entire system.
  • a rotating body can be provided on the left or right side of the beam trajectory or arbitrarily.
  • a condenser is provided at the top of the rotating body to liquefy and recover the vaporized vapor. Probably not all liquid can be recovered, so it is possible to fill the interior space with cooling water in advance. In this case, a part of the cooling water is sucked with a pump or the like and returned to the center of the rotating body, thereby completing a series of cooling water supply systems.
  • the space can have a simple opening / closing structure so that the target can be easily taken out after irradiation.
  • Mo-99 and Tc-99m which are examples of the target production nuclide of the present invention, differ in half-life by about 10 times. By optimizing the irradiation operation method using this difference, it becomes possible to increase the total amount of radioactivity generated in a certain irradiation period of Tc-99m to be finally used.
  • Saturation rate represents the generation and decay of radioactivity with respect to the length of irradiation time in the production of radionuclides by an accelerator.
  • Tc-99m can be conveniently supplied to a place at a distance that does not require time to transport the source.
  • the physical attenuation of Mo-99 is suppressed more than that of Tc-99m, so the supply with Mo-99 is efficient.
  • the presence of Mo-99 has the advantage that Tc-99m, which is about 1.7 times the original Mo-99 radioactivity, can be obtained in one week. Therefore, the motivation for studying this irradiation technique is to answer the needs of Mo-99 production in conjunction with Tc-99m.
  • Figure 10 (Scholten, B et al., Excitation functions for the cyclotron production of 99mTc and 99Mo., Appl. Radiat. Isot. 51 (1999) 69-80) Show. In the figure, attention was paid to the point that the effective irradiation energy range of Tc-99m having a short half-life is shifted to the lower side so as to partially overlap the effective irradiation energy range of Mo-99 having a long half-life. That is, the incident energy of a proton capable of efficiently producing molybdenum 99 from Mo-100 is 60-20 MeV, while the incident energy of a proton capable of efficiently producing technetium 99m is 30-20 MeV.
  • the energy range effective for the production of Mo-99 is 40 ⁇ 20 [MeV] and that of Tc-99m is 20 ⁇ 10 [MeV], as shown in FIG.
  • the first target 11 for producing Mo-99 is placed on the high energy side, and the beam 10 having the residual energy attenuated according to the passage of the first target 11 is collided with the first target 11 for Tc-99m.
  • the beam operation is important in that the second stage target 12 is exchanged with a six-hour irradiation period which is a half-life of Tc-99m.
  • the beam energy attenuation varies depending on the situation depending on the incident energy and the thickness and density of the passing substance (target). The thicker and the higher the density, the easier it is to stop the beam. The higher the incident energy, the harder the beam to stop (the energy is less likely to drop).
  • FIG. 11 shows an example in which the incident energy is 40 MeV and the thickness of each target is 0.25 mm (250 ⁇ m). The number after the arrow is the energy that is attenuated and the number in parentheses is the target. It is lost energy.
  • the number of target stages is not limited to two, but may be three, 11, 12, 13 as shown in FIG. 11 (B), or four, 11, 12, 13, 14 as shown in FIG. 11 (C). It is also possible to increase the number of stages.
  • all the targets shown in FIG. 11 may be the same Mo-100 regardless of the generated nuclides, which contributes to the simplification of the preparation work.
  • the chemical form may be arbitrary, and for example, a metal simple substance Mo-100, a metal oxide MoO 3 or the like can be used.
  • all chemical compositions may be the same.
  • the chemical composition may be different among a plurality of targets.
  • the present invention has been made on the basis of the above knowledge, and has solved the above problems by a method for producing a radionuclide using an accelerator characterized by replacing a plurality of solid targets during beam irradiation.
  • the target is supported by a rotating body and rotated around an axis outside the beam trajectory, so that one target supported by the rotating body receives a beam in a heated state and does not receive a beam.
  • the cooling state can be taken.
  • the rotating body can be intermittently rotated to stop the target one after another at the irradiation position for a predetermined time.
  • the rotating body can be reciprocally rotated.
  • the target can be supported as a rotor blade on the outer periphery of the turbine-like rotor.
  • the target can be tilted with respect to the beam axis.
  • a plurality of the rotators can be provided across the beam, and the targets supported by the rotators can alternately hit the beam.
  • the rotating body can be rotated by a fluid used for cooling the target.
  • a part of the fluid used for cooling the target can be guided to the inside of the rotating body and supplied to the target site via a flow path extending in the centrifugal force acting direction of the rotating body.
  • the target can be supported on the rotation plane of the turret-like rotating body.
  • the periphery of the rotating body and the target can be filled with a cooling medium.
  • a plurality of solid targets arranged in series are irradiated with a particle beam from an accelerator, Each beam reacts with energy attenuated as the beam passes through the target, Further, by exchanging the target according to the irradiation time of the target, a plurality of nuclides having different half-lives can be obtained efficiently.
  • the target for obtaining a nuclide with a short half-life is obtained by continuing or suspending the irradiation of the beam until the target for obtaining the nuclide having a long half-life is collected after the irradiation of the total irradiation amount is completed. Can be recovered by exchanging them sequentially.
  • the irradiation time until the exchange can be set to a period of about 0.5 to 2.5 times the half-life of the production nuclide.
  • At least one material of the target can be a metal and / or a metal oxide.
  • nuclides with different half-lives can be obtained separately from the target having the same chemical composition and / or isotope abundance ratio.
  • the particles can be protons and the target can be molybdenum 100.
  • nuclide produced can be molybdenum 99 and technetium 99m.
  • the incident energy of protons used for manufacturing the molybdenum 99 can be 60-20 MeV, or the incident energy of protons used for manufacturing the technetium 99m can be 30-20 MeV.
  • molybdenum 100 as a target is activated by recoil neutrons generated when the proton collides, and as a result, molybdenum 99 and / or technetium 99m can be manufactured.
  • the present invention also provides an apparatus for producing a radionuclide using an accelerator, characterized by comprising means for replacing a plurality of solid targets during beam irradiation.
  • radionuclides such as molybdenum 99 and technetium 99m, which are in great demand as radiopharmaceuticals, regardless of heat generation during irradiation.
  • the figure which shows the basic composition of the rotary target which concerns on this invention Diagram showing the action of the rotary target Diagram showing a variation of the rotary target
  • the figure which shows another modification similarly An exploded perspective view showing an example of a target holding structure in a rotary target
  • action of embodiment of this invention Diagram showing the relationship between cross-sectional area and irradiation energy
  • the side view which shows the basic composition of embodiment of this invention The perspective view which shows the principal part structure of 1st Embodiment of this invention.
  • FIG. 1 shows the principal part structure of 3rd Embodiment of this invention.
  • FIG. 1 shows the principal part structure of 5th Embodiment of this invention.
  • FIG. 1 shows the 1st target part of 5th Embodiment of this invention which employ
  • FIG. Side view showing another modification of the rotary target The perspective view which shows the principal part structure of 6th Embodiment of this invention.
  • FIG. 12 for example, six upper targets 11 disposed on the circumference of a rotating body 74 disposed on the upstream side of the beam 10 irradiated from the accelerator 8. And a rear target unit 40 including a disc-shaped rear target 12 and a support 45 for holding the rear target 12, which are disposed on the downstream side of the upper target unit 20. .
  • the front stage target 11 and the rear stage target 12 are both made of Mo-100, and the front stage target 11 mainly generates Mo-99 and the rear stage target 12 generates Tc-99m.
  • Mo-99 and Tc-99m can be efficiently manufactured by exchanging the post-stage target 12 every about 6 hours, which is the half-life of the post-stage target 12 until the half-life of the pre-stage target 11 is reached.
  • the beam current value may be determined according to the required amount of Tc-99m and Mo-99 required, and it is considered that the required amount is about 100 to 200 [ ⁇ A].
  • Tc-99m When the required amount of Tc-99m is 170 Ci / week (Mo-99 production amount is 100 Ci / week), the irradiation current is 15 ⁇ A in the normal range, 170 ⁇ A in the challenging region, and 1 mA required in the fast neutron method. Table 1 shows the results of comparison between these three types.
  • Irradiation time is 6 hours (half life of Tc-99m) compared with 4 types of 12 days, which is about half a day, 66 hours, which is the half life of Mo-99, and 7 days required for fast neutron method. did.
  • the Mo-99 yield A in the table is the production amount of the energy region (40 ⁇ 20 MeV) obtained by the former target 11 alone, and the total milking amount B is the total amount obtained from Mo-99 produced by the former target 11 in one week.
  • the value of the amount of Tc-99m (1st to 5th day), the single Tc-99m yield C is the production amount of the energy region (20 ⁇ 10 MeV) obtained by the latter stage target 12 alone, and the total Tc-99m yield D is The ratio of the value given by the sum (B + C) of the front stage target 11 and the rear stage target 12 and the single Tc ⁇ 99m is (B + C) / C.
  • FIG. 13 (disassembled perspective view) and FIG. 14 (front stage target) show the detailed configuration of the second embodiment of the present invention in which the rotary body of the front stage target portion 20 of the first embodiment is an opposed type of two rotary bodies 74A and 74B. Sectional view).
  • 28 is a sealing lid
  • 50 is a cooling nozzle for cooling the target
  • 52 is a condenser.
  • FIG. 15 shows a third embodiment of the present invention in which the rear stage target portion 40 of the first embodiment is a rotary type by a turret 43 that is driven to rotate by a motor 44.
  • FIG. 22 shows a fourth embodiment of the present invention in which all targets are turret types and three stages of targets 11, 12, 13 are provided.
  • reference numeral 23 denotes a one-stage turret rotated by the motor 24, 80 denotes a three-stage turret section, and 83 denotes a three-stage turret rotated by the motor 84.
  • the target 70 on the turbine type rotator 74 is provided perpendicular to the beam 10.
  • FIG. 19 shows a front stage target portion 20 according to a fifth embodiment of the present invention in which the targets 11A and 11B are arranged obliquely as shown in FIG. 17 on the rotating bodies 74 and 74B that rotate in the opposite directions of the upper stage target.
  • the method of tilting the target with respect to the beam is not limited to the method illustrated in FIG. 17, and the rotation shaft 72 of the rotating body 74 may be tilted with respect to the beam 10 as illustrated in FIG. 20.
  • FIG. 21 shows a sixth embodiment of the present invention in which the front stage target 11 and the rear stage target 12 are arranged together on the rotating body 74.
  • the rack and pinion gear may be continuously rotated counterclockwise in the figure, but as shown in FIGS. 22 (A), (B), and (C), the rack and pinion gear is constituted by a cylinder 90 composed of two cylinders.
  • the three sets of targets 11 and 12 can be exchanged by causing the rotating body 74 to rotate intermittently.
  • the targets 11 and 12 are composed of three groups, group 1, group 2 and group 3, and when the target group 1 stops at the direct irradiation position of the beam 10 as shown in FIG.
  • One of the cylinders 90 is actuated and instantaneously rotates 120 degrees counterclockwise, and the group 2 stops at the direct irradiation position of the beam 10 as shown in FIG.
  • the other of the cylinders 90 instantly operates and rotates again counterclockwise by 120 degrees, and the group 3 stops at the direct irradiation position of the beam 10 as shown in (C). And receive the necessary time.
  • Each target after irradiation is appropriately replaced or removed at the non-irradiation position.
  • the rotating body 74 can be exchanged as follows, for example. That is, a rubber grip 78 that is inwardly expanded by a fluid (for example) air pressure as shown in FIG. 23B is provided inside the rotating shaft holding portion 77 of the motor 76 shown in FIG. Then, as shown in FIG. 24, for example, the robot hand 66 holds the rotating body 74, and as shown in FIG. 25, the pneumatic pressure to the rubber grip 78 can be turned on and off.
  • a fluid for example
  • the target may be one.
  • Mo-100 is arranged in the front stage to produce Mo-99 with a half-life of 66 hours, and Mo100 is also arranged in the latter stage to produce Tc-99m with a half-life of 6 hours.
  • FIG. 26 shows a time chart of Example 1 in which different nuclides are obtained separately.
  • a shorter interval between beam irradiations is preferable because physical attenuation in the previous stage can be suppressed. For example, re-irradiation is possible in about 10 minutes.
  • the reason for setting the irradiation time to a half-life of 6 hours is that the half-life irradiation of the production nuclide is effective in terms of yield.
  • irradiation time can be made arbitrary.
  • FIG. 27 shows a time chart of the second embodiment in which 62 is generated alternately.
  • ⁇ ⁇ Continuing to emit a continuous beam over a relatively long period of several days to a week is concerned that it may have a heavy load on the production schedule of other nuclides.
  • the irradiation can be covered by a relatively short time irradiation, for example, if a long irradiation time is required, for example, a part of the targets arranged in the first stage may be It is not impossible to produce a third nuclide by using a target other than molybdenum.
  • FIG. 28 shows a time chart of Example 3 in which Mo-100 is arranged in the subsequent stage to generate Tc-99m with a half-life of 6 hours.
  • the arrangement of the targets 11A and 11B may be either FIG. 29A in which the same target is arranged for each rotator or FIG. 29B in which the target is changed even in the same rotator.
  • the present embodiment is very effective as a method for efficiently using precious machine time.
  • Example 4 The time of Example 4 in which the front stage Cu-nat was arranged to produce Zn-62 with a half-life of 9 hours, and the latter stage was arranged to produce Tb-152 g with a half-life of 5.3 days. A chart is shown in FIG.
  • irradiation may be performed by exchanging the previous stage target.
  • the irradiation end time of the last target of the target having a short half-life coincides with the irradiation end time of the target having a long half-life in order to effectively use the irradiation beam. Is set.
  • the target / irradiation time / generated nuclide / beam type / exchange target / exchange time are not limited as long as the energy range and the half-life match the configuration intended in the present invention.
  • Radionuclides such as molybdenum 99 and technetium 99m, which are in great demand as radiopharmaceuticals used in radiology, nuclear medicine, diagnostic imaging, etc., can be efficiently produced and supplied at low cost.

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Abstract

Selon l'invention, au moyen d'un échange d'une pluralité de cibles solides pendant une irradiation de faisceau, des radionucléides, tels que le molybdène-99 et le technétium-99m, qui sont très demandés en tant que produits pharmaco-radioactifs, sont produits efficacement et à un faible coût, indépendamment de la chaleur générée pendant l'irradiation.
PCT/JP2010/057013 2010-04-20 2010-04-20 Procédé et dispositif pour la production d'un radionucléide au moyen d'un accélérateur Ceased WO2011132266A1 (fr)

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JP2012511443A JP5263853B2 (ja) 2010-04-20 2010-04-20 加速器による放射性核種の製造方法及び装置

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Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2012139220A1 (fr) * 2011-04-10 2012-10-18 The Governors Of The University Of Alberta Production de technétium à partir d'une cible en molybdène métallique
JP2017534878A (ja) * 2014-11-17 2017-11-24 ロスアラモス・ナショナル・セキュリティ，エルエルシー 医療用放射性同位元素を準備するための装置
WO2018142459A1 (fr) * 2017-01-31 2018-08-09 住友重機械工業株式会社 Dispositif cible
CN108696980A (zh) * 2018-07-05 2018-10-23 厦门大学 一种轰击Mo靶件的方法和高纯度99mTc及其生产方法和应用
JP2021001803A (ja) * 2019-06-21 2021-01-07 株式会社千代田テクノル 非破壊検査用放射線源、並びに、その製造方法及び装置
JP2021096147A (ja) * 2019-12-17 2021-06-24 株式会社東芝 放射性同位体製造方法および放射性同位体製造装置
WO2024143205A1 (fr) * 2022-12-26 2024-07-04 住友重機械工業株式会社 Dispositif de production de ri
WO2025202800A1 (fr) * 2024-03-27 2025-10-02 Agenzia Nazionale Per Le Nuove Tecnologie, L'energia E Lo Sviluppo Economico Sostenibile (Enea) Dispositif de rayonnement de particules générées par fusion et son procédé de rayonnement

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62160400U (fr) * 1986-03-31 1987-10-12
JP2005024466A (ja) * 2003-07-04 2005-01-27 Sumitomo Heavy Ind Ltd ターゲット着脱装置

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62160400A (ja) * 1986-01-09 1987-07-16 日立建機株式会社 管埋設装置
US5784423A (en) * 1995-09-08 1998-07-21 Massachusetts Institute Of Technology Method of producing molybdenum-99

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62160400U (fr) * 1986-03-31 1987-10-12
JP2005024466A (ja) * 2003-07-04 2005-01-27 Sumitomo Heavy Ind Ltd ターゲット着脱装置

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2012139220A1 (fr) * 2011-04-10 2012-10-18 The Governors Of The University Of Alberta Production de technétium à partir d'une cible en molybdène métallique
JP2017534878A (ja) * 2014-11-17 2017-11-24 ロスアラモス・ナショナル・セキュリティ，エルエルシー 医療用放射性同位元素を準備するための装置
WO2018142459A1 (fr) * 2017-01-31 2018-08-09 住友重機械工業株式会社 Dispositif cible
CN108696980A (zh) * 2018-07-05 2018-10-23 厦门大学 一种轰击Mo靶件的方法和高纯度99mTc及其生产方法和应用
JP2021001803A (ja) * 2019-06-21 2021-01-07 株式会社千代田テクノル 非破壊検査用放射線源、並びに、その製造方法及び装置
JP2021096147A (ja) * 2019-12-17 2021-06-24 株式会社東芝 放射性同位体製造方法および放射性同位体製造装置
WO2024143205A1 (fr) * 2022-12-26 2024-07-04 住友重機械工業株式会社 Dispositif de production de ri
WO2025202800A1 (fr) * 2024-03-27 2025-10-02 Agenzia Nazionale Per Le Nuove Tecnologie, L'energia E Lo Sviluppo Economico Sostenibile (Enea) Dispositif de rayonnement de particules générées par fusion et son procédé de rayonnement

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