WO2012039036A1 - Processus et dispositif pour la production d'un radionucléide à l'aide d'un accélérateur - Google Patents

Processus et dispositif pour la production d'un radionucléide à l'aide d'un accélérateur Download PDF

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Publication number
WO2012039036A1
WO2012039036A1 PCT/JP2010/066433 JP2010066433W WO2012039036A1 WO 2012039036 A1 WO2012039036 A1 WO 2012039036A1 JP 2010066433 W JP2010066433 W JP 2010066433W WO 2012039036 A1 WO2012039036 A1 WO 2012039036A1
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Prior art keywords
liquid
target container
target
radionuclide
accelerator
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PCT/JP2010/066433
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English (en)
Japanese (ja)
Inventor
弘太郎 永津
克行 峯岸
滋夫 内田
恵子 田上
Original Assignee
独立行政法人放射線医学総合研究所
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Priority to PCT/JP2010/066433 priority Critical patent/WO2012039036A1/fr
Priority to JP2012534854A priority patent/JP5322071B2/ja
Priority to EP10857530.9A priority patent/EP2620949A4/fr
Publication of WO2012039036A1 publication Critical patent/WO2012039036A1/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
    • H—ELECTRICITY
    • H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05H—PLASMA TECHNIQUE; PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS
    • H05H6/00—Targets for producing nuclear reactions
    • 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
    • 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
    • G21G2001/0042—Technetium

Definitions

  • the present invention relates to a radionuclide production method and apparatus using an accelerator, and in particular, radionuclides such as technetium 99m and molybdenum 99, which are in great demand as radiopharmaceuticals, can be repeatedly produced remotely in one target container.
  • the present invention relates to a method and an apparatus for producing a radionuclide using an accelerator.
  • Technetium 99m (Tc-99m, half-life 6 hours), which is used worldwide in the fields of nuclear medicine and diagnostic imaging, is the leading role of over 70% of the radioisotopes used in nuclear medicine.
  • Molybdenum 99 (Mo-99, half-life 66 hours) is a radioisotope called Tc-99m parent nuclide because Tc-99m is produced as Mo-99 decays.
  • Devices that can selectively recover the produced Tc-99m by adsorbing Mo-99 onto a support such as alumina are commercially available (Mo-99 / Tc-99m generator).
  • Mo-100 molybdenum 100
  • proton proton
  • the present invention is a method for producing Tc-99m or Mo-99 by 100 Mo (p, 2n) 99m Tc or 100 Mo (p, pn) 99 Mo nuclear reaction using charged particles obtained from an accelerator. Therefore, the prior art will be verified for all methods using accelerators. In either case, the yield (radioactivity) at a practical level was not obtained, and the evaluation was completed through the examination or verification of the concept.
  • Non-Patent Document 1 estimated the generation amounts of Tc-99m and Mo-99 when irradiating Mo-100 with a proton beam of energy range 68 ⁇ 8 MeV and Non-Patent Document 2 with 22 ⁇ 10 MeV. 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.
  • the present invention has been made to achieve the above-described conventional problems, and in order to produce practical technetium 99m and / or molybdenum 99, a specific structure and irradiation process applicable when irradiating molybdenum 100 is performed.
  • the task is to establish an operation method.
  • the present inventors tried to solve the problem by dissolving molybdenum as a target material in an appropriate solvent, drying it before irradiation, and changing the liquid to a solid.
  • a liquid target molybdenum solution
  • the liquid absorbs the energy of the beam and as a result hinders sufficient nuclear reaction of the molybdenum target. Therefore, the yield of Tc-99m or Mo-99 expected by this method is significantly reduced.
  • the theoretical nuclear reaction yield can be obtained by removing the liquid from the target material before irradiation and increasing the density of the molybdenum target existing on the incident beam orbit.
  • the present invention has been made on the basis of the above knowledge, introduced a target substance dissolved in a liquid or mixed with a liquid into a target container, A method for producing a radionuclide using an accelerator, comprising: drying the target container to reduce a liquid component, and then irradiating a beam from the accelerator.
  • the target material dissolved in the liquid or mixed with the liquid and introduced into the target container can be dried in the target container to precipitate a solid component.
  • the thickness of the solid component deposited in the target container can be set to 0.1 to 5 mm on the trajectory of the beam incident from the accelerator.
  • the drying can be performed by at least one of heating, introduction of a drying gas, and exhaust.
  • the temperature in the target container at the time of drying can be set to 100 ° C. or higher.
  • the gas used for the drying can be helium, hydrogen, or carbon monoxide.
  • the gas used for the drying is introduced into the target container so as to pass through the target material which is dissolved in the liquid or mixed with the liquid and introduced into the target container and accumulated below the target container. be able to.
  • the liquid can be introduced into the target container, the target material can be dissolved again in the liquid or mixed with the liquid, and taken out of the target container.
  • the liquid taken out from the target container can be collected without being discarded.
  • the target material may be molybdenum 100
  • the beam may be a 40-9 MeV proton beam
  • the radionuclide produced may be technetium 99m and / or molybdenum 99.
  • the target material introduced into the target container can be molybdenum oxide dissolved in ammonia water.
  • hydrogen peroxide water can be added to the ammonia water.
  • the temperature during the drying can be set to 200 to 650 ° C.
  • the liquid can be ammonia water and / or hydrogen peroxide water.
  • the present invention when the target material that has been irradiated with the beam from the accelerator is taken out of the target container, Introducing liquid into the target container;
  • the present invention provides a method for producing a radionuclide using an accelerator, wherein the target substance is dissolved in the liquid or mixed with the liquid and taken out of the target container.
  • a target container Means for introducing a target substance dissolved or mixed with the liquid into the target container; Drying means for reducing liquid components by drying in the target container; Means for irradiating the target container with a beam from an accelerator; An apparatus for producing a radionuclide using an accelerator is provided.
  • the drying means can dry the target material dissolved in the liquid or mixed with the liquid and introduced into the target container to precipitate a solid component in the target container.
  • the drying means may include at least one of a heating means, a gas supply means, and an exhaust means.
  • the target container seals the target container and includes a metal thin film for allowing the beam to pass therethrough, and the metal thin film can be cooled.
  • the apparatus may further comprise means for dissolving the target substance in the liquid again or mixing it with the liquid and taking it out of the target container.
  • the means for collecting may include a filter provided in the middle of the piping.
  • the present invention is also a radionuclide production apparatus in which a target material that has been irradiated with a beam from an accelerator is extracted from the target container.
  • a radionuclide production apparatus using an accelerator comprising means for introducing a liquid into the target container, dissolving the target material in the liquid or mixing it with the liquid, and taking it out of the target container. To do.
  • the present invention makes it possible to produce Tc-99m using molybdenum as a target, which has not been reported previously. Furthermore, since all the processes required for manufacturing can be performed remotely, there is no occupational exposure to those involved in the work, and manufacturing in consideration of health and safety is possible.
  • the target material can be quickly taken out from the target container, and can be repeatedly produced in one target container, and even a radionuclide having a short half-life can be taken out without causing a problem. .
  • Pipeline diagram showing the configuration of the first embodiment of the present invention Sectional drawing which shows the target container used in 1st Embodiment
  • Flow chart showing the processing procedure of the first embodiment Sectional drawing which follows the IV-IV line
  • a charged particle (here, proton) beam from an accelerator irradiation port 108 which is means for irradiating a beam from an accelerator (not shown) is irradiated, for example, vertically.
  • a target solution in the Mo tank 112 is pushed out to a pipe 114 to Syringe S1, which is a means for introducing into the target container 110, and a drying means for drying the target container 110 to an extent that does not affect the irradiation of the proton beam and reducing the liquid component to precipitate the solid component.
  • Heater H1 an inert gas for drying (also serving as a pressure source for liquid transportation), for example, helium gas is supplied Because helium (He) tank 116, a flow control meter 118 and vacuum pump (for example, a vacuum pump) for vaporization and exhaust promotion P and a mixed solvent for storing the a recovery solvent for example H 2 O 2 + NH 4 OH ( (H 2 O 2 + NH 4 OH) tank 122 and after completion of the proton beam irradiation, the recovery solvent in the H 2 O 2 + NH 4 OH tank 122 is pushed out to the pipe 114 with a syringe (not shown) or the like, and the target container 110 is arranged in the middle of a valve V3 that is a means for introducing into the inside of the 110, a three-way switching valve V7 that selects helium gas flow paths V7-a and V7-b, and a closed circuit, and a pipe 126 from the target container 110.
  • a valve V3
  • a solution trap 124 to permit the overflow solution from the target vessel 110, for example, silicon from the H 2 O 2 + NH 4 OH tank 122
  • a recovery solvent introduced by a method (not shown) or the like is introduced into the target container 110 from the solution trap 124 and the pipe 126, and the valve V6 as a means for cleaning the target container 110, and the target container 110 from the inside.
  • the valve V1 which is a means for taking out the liquid and collecting it without discarding, is disposed in the middle of the recovery pipe 129 so as not to block the solid content of the recovered substance inside the downstream pipe.
  • a filter 130, a Tc-containing Mo recovery tank 132, valves V1 to V8, and pipes 114, 126, 128, and 129 are provided.
  • the valves other than the valve V7 are one-way open / close valves.
  • the target container 110 is isolated by the irradiation port 110 ⁇ / b> A side and the metal thin film 110 ⁇ / b> B, introduces a target solution and irradiates charged particles, and heats and cools the target chamber 110 ⁇ / b> C.
  • a heating / cooling unit 110D provided with a heater H1, and a vacuum diaphragm 110E for flowing a fluid (here, helium gas) for cooling the metal thin film 110B to the irradiation port 110A side of the metal thin film 110B.
  • a cooling chamber 110F partitioned by the metal thin film 110B.
  • 110G is a port to which a pipe 114 and a recovery pipe 129 are connected
  • 110H is a port to which a pipe 126 having a solution trap 124 is connected
  • 110I is provided with valves V4 and V5.
  • a port to which the pipe 128 is connected 110J is a cooling He gas inlet port
  • 110K is a cooling He gas outlet port
  • 110L is a cooling water inlet port
  • 110M is a cooling water outlet port.
  • the target chamber 110C is manufactured to have a cylindrical shape with an inner diameter of 10 to 20 mm and a depth of 20 to 100 mm, for example, and the material can be selected from aluminum, gold, or platinum.
  • Aluminum is preferable as an inexpensive material, but gold or platinum can be selected in consideration of corrosion resistance.
  • the material of the metal thin film 110B that irradiates the target material with the beam from the accelerator is the same, and the thickness thereof is, for example, 10 to 500 ⁇ m, particularly 10 to 100 ⁇ m, depending on the energy of the beam. preferable.
  • a portion of the flange 110N that requires airtightness is provided with an O-ring 110P made of stainless steel or heat-resistant silicon, and the metal thin film 110B maintains airtightness by the pressing force of the flange 110N.
  • O-ring 110P made of stainless steel or heat-resistant silicon
  • the metal thin film 110B maintains airtightness by the pressing force of the flange 110N.
  • the target solution described above is introduced from the bottom or side surface of the target container 110.
  • a pump or a syringe can be used.
  • the amount of solution introduced is determined in advance so that the thickness of the deposited molybdenum compound on the beam trajectory is 0.1 to 5 mm.
  • it is incident as an example.
  • the proton beam energy is 18 MeV
  • the area density of molybdenum is assumed to be about 450 mg / cm 2 or more.
  • the required area density strongly depends on the incident energy, there is no limitation.
  • heating is performed by providing a heating element, for example, a heater H1, fixed to the outer periphery of the target container 110, for example, the bottom.
  • the set temperature at this time is set to be about 100 to 700 ° C. in the target container 110, but more preferably 200 to 650 ° C.
  • gas is sent into the target container to promote the release of evaporated water.
  • precipitation of ammonium molybdate occurs, but the compound decomposes into molybdenum oxide, ammonia gas, and water by further heating.
  • ammonia gas and water are released together with the introduced gas to the outside of the target container.
  • only molybdenum oxide crystals exist on the bottom surface of the target container.
  • helium gas As the introduced gas, which is caused by not giving a nuclear reaction product when remaining in the target container.
  • the target substance introduced as a liquid inside the target container is prepared as a solid by drying and solidifying, whereby efficient irradiation becomes possible.
  • the degree of drying and solidification is at least that which allows the influence of absorption of beam energy by the residual liquid to be allowed.
  • the upper part of the target container is sealed with a metal thin film 110B and cooled with helium gas or the like. As a result, it becomes possible to deposit an excessive sublimate on the thin film, thereby preventing loss of raw materials.
  • the target container may be a sealed system or an open system. If it is an open system, it becomes possible to prevent the pressure rise resulting from the heat_generation
  • the target container 110 is provided with a plurality of inlets and outlets, (1) When the solution is injected, the upper hole becomes an exhaust port, so that the pressure does not increase. In addition, (2) at the time of heating and drying, since it is connected to the vacuum pump P of the negative pressure system from the upper hole, it is heated, but it is rather lower than the atmospheric pressure. (3) During irradiation, the temperature rises due to the heat generated by the beam, but the pressure balance is made the same as the atmospheric pressure by providing an expansion chamber that increases or decreases the accommodation volume according to the increase or decrease of the internal pressure in the path following the upper hole. Can keep. Therefore, there is no problem with the soundness of the metal thin film 110B, and at least damage due to pressure does not occur.
  • ammonia water is introduced into the target container and the irradiated molybdenum oxide is dissolved again for about 5 to 10 minutes. If ammonia water + hydrogen peroxide solution mixed solution is introduced instead of introducing ammonia water, molybdenum oxide is more easily dissolved. In order to promote dissolution, warming and mixing by introducing gas are performed.
  • ammonia water is used at a concentration of 10 to 30% by weight
  • hydrogen peroxide water is used at a concentration of 10 to 30% by weight.
  • the amount of the liquid depends on the shape of the target container, but is 20 to 20% of the volume.
  • a liquid volume corresponding to 80% is introduced. As the number of solutions increases, the efficiency with which Tc-99m and Mo-99 that may adhere to a wide range of the target container wall surface can be dissolved and recovered increases.
  • the molybdenum oxide redissolved solution in which Tc-99m or Mo-99 is dissolved is transferred to the outside of the target container by pumping helium gas or the like.
  • molybdenum oxide or the like that could not be dissolved in the above-described process may block the recovery pipe. Therefore, by providing a filter 130 immediately after the target container and excluding them, stable solution transfer is possible.
  • the filter 130 provided in the middle of the pipe can be a commercially available product having a hole diameter of 0.22 ⁇ m or more, and the hole diameter is not limited unless the pipe is blocked.
  • quartz, polypropylene or Teflon registered trademark
  • the recovered solution can then be purified using, for example, an ion exchange resin to obtain the target Tc-99m.
  • an ion exchange resin to obtain the target Tc-99m.
  • the liquid after passing through the ion exchange resin is collected and used for the next production. Since the composition of the collected liquid is the same component as the liquid prepared before irradiation, it can be used as it is for the next production without requiring special purification.
  • a target solution (ammonia molybdenum oxide) is introduced from the port 110G into the target chamber 110C via the valve V2 ⁇ V1 (step 100). At this time, the valve V4 is opened as an exhaust path.
  • the target container 110 is heated by the heater H1 provided in the target container, and the solution is dried (step 110).
  • helium gas is introduced through the valve V7-a and the pipe 114 while controlling the flow rate with the flow controller 118, and the drying of the target chamber is promoted, and the port 110I is exhausted through the valve V5 ⁇ the vacuum pump P. .
  • helium gas can be introduced from the port 110H.
  • the target material mixed with the liquid and introduced into the target container and accumulated below the target container 10 is collected in the port 110G. It is preferable because clogging can be prevented by flowing back to the pipe 114 and solidifying in the middle of the pipe 114.
  • the temperature in the target container 110 at the time of drying is set to 100 to 700 ° C., but is particularly preferably 250 ° C. or higher, which is a temperature at which ammonia can be removed as vapor in addition to moisture.
  • the preparation is completed by cooling the target container temperature to about room temperature (step 130). At this time, cooling water may be forced to flow from the port 110L to the port 110M. After preparation is complete, all routes are blocked.
  • the proton beam passes through the metal thin film 110B and is irradiated toward the bottom of the target chamber 110C (step 140). Irradiation is performed so that the proton beam energy on the target is in the range of 9 to 40 MeV, but in the production of technetium-99m, 15 to 22 MeV is particularly desirable.
  • the valve V8 is opened to prevent damage to the target container, particularly the metal thin film 110B, in order to suppress an increase in pressure inside the target container due to heat generated during irradiation.
  • helium gas is allowed to flow from the port 110J to the port 110K to cool the vacuum partition 110E and the metal thin film 110B, while cooling water is also allowed to flow from the port 110L to the port 110M. Cool the bottom of the.
  • the valve V8 is closed, and helium gas is supplied from the port 110H to the target container 110 via the valve V7-b ⁇ the pipe 126 ⁇ the solution trap 124, and the target solution is supplied to the port 110G. Then, the recovery pipe 129 and the filter 130 are passed through the valve V1 and recovered in the Tc-containing Mo recovery tank 132 (step 160).
  • the next manufacturing does not require any special operations other than those shown here, [1. This is achieved by performing [Preparation of Target].
  • the solution recovered in the Tc-containing Mo recovery tank 132 can be reused.
  • the solution that enters the target container is a combination of molybdenum + ammonia water + hydrogen peroxide water, and steps for each component.
  • the fluctuation is within the expected range, and the fluctuation is offset by preparation and collection. Sometimes used ones can be reused as they are (no need for washing etc.).
  • FIG. 4 sectional view taken along line IV-IV in FIG. 5
  • FIG. 5 side view seen from the direction of arrow V
  • the metal thin film 110B is provided obliquely with respect to the beam trajectory.
  • the second embodiment is different from the first embodiment in that a target container 110 ′ that is irradiated with a proton beam from the horizontal direction toward the metal thin film 110B is used.
  • 4 shows a cross section on the line IV-IV shown in FIG.
  • the shape of the inside of the target container is a cylindrical shape in the first embodiment, but in the second embodiment, it is formed in a conical shape with a flat apex for ease of processing. Since other configurations and operations are the same as those in the first embodiment, the same reference numerals are used for corresponding portions, and descriptions thereof are omitted.
  • the target material is introduced and recovered by a combination of helium gas and an exhaust device (vacuum pump P).
  • vacuum pump P vacuum pump
  • the means for introducing and discharging the target material is not limited to this.
  • General liquid transporting means such as other pumps and syringes may be used.
  • liquid transporting means may be installed at a place away from the target containers 110 and 110 'to perform liquid feeding.
  • molybdenum 99 and technetium 99m are manufactured from molybdenum 100.
  • the type of target material and the production nuclide, the type of solvent used simultaneously, and the type of beam are not limited.
  • the radionuclide to be produced is Z A Product
  • the target material is Z-1 A Target (A is the atomic weight, Z is the atomic number)
  • a proton beam is used.
  • Z-1 A Target (p, x) Z A Product Consider the case of manufacturing using a nuclear reaction.
  • Z-1 A Target alone, oxide, hydroxide, fluoride, chloride, bromide, iodide, hydrochloride, nitrate, nitrite, sulfate, sulfide, hydride, and their hydration Things are available.
  • any solvent can be used as long as it can be suspended in the mobile phase without being dissolved.
  • Mo simple metal fine powder
  • organic solvents such as alcohol and acetone
  • the expression “dissolved in a liquid” includes mixing in the liquid and coexistence of both.
  • ammonia water concentration and the molybdenum oxide concentration are not limited. Furthermore, hydrogen peroxide water may be added as necessary to improve solubility. The hydrogen peroxide concentration at this time does not matter.
  • the temperature in the target container at the time of drying is preferably 100 ° C. or higher, and more preferably 200 to 650 ° C. capable of evaporating ammonia, but is not limited thereto.
  • the thickness of the generated crystal is preferably 0.1 to 5 mm on the incident beam trajectory, but is not limited to this.
  • the gas used during drying is also helium, hydrogen or carbon monoxide, but is not limited thereto.
  • pressurization and pressure feeding with a pressure body suction with a syringe, or the like can be used.
  • a heating device and a gas supply device may be used in combination.
  • the number of target containers is not limited to one, and a plurality of target containers may be used so that they can be continuously manufactured by irradiation with beams in order.
  • the irradiation beam is not limited to the proton beam.
  • the target substance is not limited to a solid, and may be in solution.
  • the present invention is applicable to the manufacture of radiopharmaceuticals used for diagnostic imaging in the fields of radiology and nuclear medicine.

Abstract

Selon l'invention, un radionucléide tel que le technétium 99m et le molybdène 99, qui est en forte demande en tant que substance radioactive, peut être produit à distance et de manière répétitive dans une cuve cible unique par l'introduction d'une substance cible qui a été dissoute dans un liquide ou mélangée avec un liquide dans la cuve cible, le séchage de la substance cible dans la cuve cible pour réduire le volume d'un composant liquide, puis l'irradiation de la substance cible avec un faisceau émis depuis un accélérateur.
PCT/JP2010/066433 2010-09-22 2010-09-22 Processus et dispositif pour la production d'un radionucléide à l'aide d'un accélérateur WO2012039036A1 (fr)

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PCT/JP2010/066433 WO2012039036A1 (fr) 2010-09-22 2010-09-22 Processus et dispositif pour la production d'un radionucléide à l'aide d'un accélérateur
JP2012534854A JP5322071B2 (ja) 2010-09-22 2010-09-22 加速器による放射性核種の製造方法及び装置
EP10857530.9A EP2620949A4 (fr) 2010-09-22 2010-09-22 Processus et dispositif pour la production d'un radionucléide à l'aide d'un accélérateur

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JP2014115229A (ja) * 2012-12-11 2014-06-26 Sumitomo Heavy Ind Ltd 放射性同位元素精製装置
JP2016145714A (ja) * 2015-02-06 2016-08-12 国立研究開発法人量子科学技術研究開発機構 移動式放射性核種製造用照射装置
JP2018095967A (ja) * 2012-04-27 2018-06-21 トライアンフＴｒｉｕｍｆ テクネチウム−９９ｍのサイクロトロン生産のためのプロセス、システム、及び装置
WO2019189022A1 (fr) * 2018-03-27 2019-10-03 国立研究開発法人量子科学技術研究開発機構 Dispositif et procédé de fabrication de nucléides radioactifs à l'aide d'un accélérateur, et récipient de fabrication de nucléides radioactifs
JP7396949B2 (ja) 2020-03-30 2023-12-12 日本メジフィジックス株式会社 ターゲット装置及び放射性核種の製造装置

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CN110706840B (zh) * 2019-10-18 2021-01-05 中国科学院合肥物质科学研究院 一种基于加速器驱动的99Mo次临界生产装置及方法

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JP7190200B2 (ja) 2018-03-27 2022-12-15 国立研究開発法人量子科学技術研究開発機構 加速器を用いた放射性核種の製造装置、製造方法、および放射性核種製造用容器
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