JP2008247840A - Production method for medical nuclide-containing solution and production apparatus for medical nuclide-containing solution - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide a medical nuclide production method producing a medical radioactive nuclide without using a large scale apparatus. <P>SOLUTION: A production method of a medical nuclide-containing solution, producing a medical nuclide-containing physiologic saline solution 71 is provided, wherein, by flowing deuterium to a coagulative structure in contact with a material to be applied with nuclide conversion, the coagulative structure provided with a nuclide-converted material obtained by generating nuclear reaction on a material to be applied with a nuclide-converted material is dipped in a physiologic saline solution as a sample pole 76 of one electrode, a predetermined voltage is applied between electrodes 74 and 76 to extract nuclide-converted materials into the physiologic saline solution, and the physiologic saline solution after extraction is adopted as the medical nuclide-containing solution. <P>COPYRIGHT: (C)2009,JPO&INPIT

Description

  The present invention relates to a medical nuclide-containing solution manufacturing method and a medical nuclide-containing solution manufacturing apparatus that are suitable for use in a diagnostic method (PET or the like) for performing diagnosis by administering a drug containing radiation to a subject. is there.

A PET (Positron Emission Tomography) test is known as a medical diagnostic method for detecting lesions such as cancer cells (see Patent Document 1 below).
In the PET examination, a radiopharmaceutical is administered to a subject, and the size and shape of a lesion are measured by detecting radiation emitted from the subject. The drug used for this PET examination is required to contain a radionuclide. This radionuclide is currently obtained using a large accelerator.

JP 2006-87540 A (paragraph [0002])

However, since there are few hospitals that can have large facilities that accommodate large accelerators, it is difficult to install them in many hospitals.
In addition, radionuclides used for medical purposes have a relatively short half-life. For example, its half-life is 20.39 minutes at ¹¹ C, 9.965 minutes at ¹³ N, 2.037 minutes at ¹⁵ O, and 109.8 minutes at ¹⁸ F. Therefore, it is necessary to administer the radionuclide to the subject immediately after production, but since there are not many hospitals equipped with facilities capable of producing the radionuclide as described above, it is extremely inconvenient.

  This invention is made | formed in view of such a situation, Comprising: The medical nuclide manufacturing method and medical nuclide manufacturing apparatus which can manufacture a medical radionuclide without using a large-scale installation are provided. For the purpose.

In order to solve the above problems, the medical nuclide-containing solution manufacturing method and the medical nuclide-containing solution manufacturing apparatus of the present invention employ the following means.
That is, the medical nuclide-containing solution production method according to the present invention is a medical nuclide-containing solution production method for producing a medical nuclide-containing solution containing a medical nuclide, and is an agglomeration system in which a substance that performs nuclide conversion is contacted Immerse the aggregated structure containing the nuclide-converted substance that has caused a nuclear reaction in the substance to which the nuclide conversion substance is applied by flowing deuterium into the structure as one electrode, and between the electrodes The nuclide-converted substance is extracted into the electrolyte by applying a predetermined voltage to the electrolyte, and the extracted electrolyte is used as a medical nuclide-containing solution.

The substance after the nuclide conversion generated by the agglomeration-type nuclear reaction is used as one electrode, and the electrolytic solution containing the substance after the nuclide conversion is made into a medical nuclide-containing solution by electrolytic extraction in the electrolyte. Thus, since the medical nuclide containing solution can be manufactured with a simple apparatus, the enlargement of an apparatus is not caused.
Examples of the agglomerated structure include palladium (Pd) or an alloy of Pd, other metals that store hydrogen (such as Ti), or alloys thereof.

  Furthermore, in the method for producing a medical nuclide-containing solution of the present invention, the electrolytic solution is physiological saline.

  By using physiological saline as the electrolytic solution, the solution after electrolytic extraction can be used as it is as a raw material for drugs such as PET. Thereby, since it can administer rapidly with respect to a subject, even if it is a nuclide with a short half life, it can be used for a diagnosis.

  The medical nuclide-containing solution production apparatus of the present invention is a medical nuclide-containing solution production apparatus for producing a medical nuclide-containing solution containing a medical nuclide, the container containing an electrolytic solution, and the inside of the electrolytic solution The nuclide conversion substance is provided by flowing deuterium through an agglomerated structure having a pair of electrodes immersed in the electrode and a power source for applying a predetermined voltage between the electrodes and contacting the substance to be subjected to nuclide conversion. An agglomerated structure having a nuclide-converted substance that causes a nuclear reaction in the substance to be applied is used as one of the electrodes, and the nuclide-converted substance is placed in the electrolyte by applying a predetermined voltage between the electrodes. And extracting the electrolyte solution after extraction into a medical nuclide-containing solution.

The substance after the nuclide conversion generated by the agglomeration-type nuclear reaction is used as one electrode, and the electrolytic solution containing the substance after the nuclide conversion is made into a medical nuclide-containing solution by electrolytic extraction in the electrolyte. Thus, since the medical nuclide containing solution can be manufactured with a simple apparatus, the enlargement of an apparatus is not caused.
Examples of the agglomerated structure include palladium (Pd) or an alloy of Pd, other metals that store hydrogen (such as Ti), or alloys thereof.

  Furthermore, in the medical nuclide-containing solution manufacturing apparatus of the present invention, the electrolytic solution is physiological saline.

  By using physiological saline as the electrolytic solution, the solution after electrolytic extraction can be used as it is as a raw material for drugs such as PET. Thereby, since it can administer rapidly with respect to a subject, even if it is a nuclide with a short half life, it can be used for a diagnosis.

  Furthermore, in the medical nuclide containing solution manufacturing apparatus of this invention, the 2nd radiation which measures the 1st radiation measurement part which measures the radiation dose radiated | emitted from the said container, and the radiation dose radiated | emitted from the syringe which attracts | sucks the said solution A measurement unit; and a determination unit that determines whether the electrolyte solution sucked into the syringe has a desired radiation dose based on detection results from the first radiation measurement unit and the second radiation measurement unit It is characterized by having.

  The radiation dose emitted from the container is measured by the first radiation measurement unit, and the radiation dose emitted from the syringe is measured by the second radiation measurement unit. Then, when the electrolyte solution is sucked with the syringe, the radiation dose measured by the first radiation measurement unit decreases, and the radiation dose measured by the second radiation measurement unit increases. Based on the detection result, it is determined whether or not an electrolyte containing a desired amount of radiation has been sucked into the syringe. Thereby, the medicine containing the radiation dose required for diagnosis such as PET can be obtained with good reproducibility.

  The syringe of the present invention is a syringe containing a medical nuclide-containing solution containing a medical nuclide, and the nuclide is flowed by flowing deuterium into an aggregated structure in contact with a substance to be subjected to nuclide conversion. The agglomerated structure comprising the nuclide-converted substance that has caused a nuclear reaction in the substance to which the conversion substance is applied is immersed in an electrolytic solution as one electrode, and a predetermined voltage is applied between the electrodes to thereby convert the nuclide-converted structure. A substance is extracted into the electrolytic solution, and the extracted electrolytic solution is stored as a medical nuclide-containing solution.

  The substance after the nuclide conversion generated by the agglomeration-type nuclear reaction is used as one electrode, and the electrolytic solution containing the substance after the nuclide conversion is made into a medical nuclide-containing solution by electrolytic extraction in the electrolyte. By sucking the medical nuclide-containing solution, the medical nuclide-containing solution is accommodated in the syringe. As described above, since the medical nuclide-containing solution can be quickly accommodated in the syringe after the production of the medical nuclide, and can be easily transported as a syringe, the administration to the subject is simple and quick. Will be done.

  According to the present invention, since the nuclide-converted substance can be contained in the electrolytic solution (physiological saline) by electrolytic extraction, a medical radionuclide can be produced without using a large-scale facility. Therefore, it can also be installed in hospitals where it is difficult to introduce large equipment.

[First Embodiment]
Hereinafter, a first embodiment of the present invention will be described with reference to the drawings.
First, after explaining the manufacturing method of the agglomeration-type structure provided with the medical nuclide by the agglutination type nuclear reaction, the medical nuclide containing solution manufacturing method and the apparatus related to the present invention will be explained.

A method of performing nuclide conversion by bringing a substance that performs a nuclide reaction into contact with an aggregate structure made of a solid such as palladium, flowing deuterium to the aggregate structure, and causing an agglomerate reaction. As shown in the literature, various reports have been made.
(1) JP 2002-202392 A (2) Y. Iwamura, T. Itoh
et al., Observation of Nuclear Transmutation Reactions Induced by D2 Gas Permeation
Through Pd Complexes, Proc. 11th Int. Conf. Cold Fusion, 31 October-5
November 2004 (Marseilles, France), pp. 339-350
(3) Yasuhiro Iwamura, Takehiko Ito, Mitsuru Sakano, Makoto Kuribayashi: Observation of element conversion on Pd multilayers by deuterium permeation, "Solid physics", vol. 39, No. 4, (2004), pp. 203-210
(4) Y. Iwamura, T. Itoh
and M. Sakano, Proc 8th Int. Conf. Cold
fusion (Italian Physical Society, Bologna, Italy, 2000), pp. 141-146
(5) Y. Iwamura, M. Sakano
and T. Itoh, Elemental Anarysis
of Pd Complexes: Effects of D2 Gas Permeation, Jpn.
J. Appl. Phys. 41, 4642-4648 (2002)

An outline of an apparatus 10 for realizing such an agglomerated nuclear reaction is shown in FIG.
This device 10 is made of, for example, a substantially plate-like structure (aggregated structure) 11 made of palladium (Pd) or an alloy of Pd, or other metal (such as Ti) that absorbs hydrogen, or an alloy thereof. It has. A substance 14 that performs nuclide conversion is brought into contact with one surface 11A of the structure 11. This one surface 11A side is made into the area | region 12 where the pressure of deuterium is high, for example by pressurization or electrolysis. The other surface 11B side of the structure 11 is a region 13 where the pressure of deuterium is low, for example, by evacuation. As a result, a deuterium stream 15 is generated in the structure 11, and the nuclide conversion is performed by the reaction between the deuterium and the substance 14 that performs the nuclide conversion.
Here, as shown in FIG. 2, the structure 11 is preferably a material having a relatively low work function, that is, a material that easily emits electrons (for example, a material having a work function of less than 3 eV) on the surface of the Pd substrate 23. ) And Pd are formed, and a Pd layer 21 is laminated on the surface of the mixed layer 22.

  FIG. 3 shows a nuclide conversion device 30 that further embodies the device 10 shown in FIG. The nuclide conversion device 30 includes an occlusion chamber 31 that can be kept airtight inside, a discharge chamber 34 that can be kept airtight inside the occlusion chamber 31 via a multilayer structure 32, and a variable leak valve 33. Is generated from a deuterium cylinder 35 for supplying deuterium into the storage chamber 31 via a discharge chamber, a discharge chamber vacuum gauge 36 for detecting the degree of vacuum in the discharge chamber 34, and a multilayer structure (aggregated structure) 32, for example. A mass analyzer 37 that evaluates the amount of deuterium permeating through the multilayer structure 32 by detecting a gaseous reaction product and measuring the amount of deuterium in the discharge chamber 34. A turbo molecular pump 38 that is always kept in a vacuum state, and a rotary pump 39 for roughing the inside of the discharge chamber 34 and the turbo molecular pump 38 are provided.

  Furthermore, the nuclide conversion device 30 includes, for example, an electrostatic analyzer 40 that detects photoelectrons and ions emitted from atoms on the surface of the multilayer structure 32 excited by irradiation with X-rays, electron beams, particle beams, and the like. An X-ray gun 41 for XPS (X-ray Photo-electron Spectrometry) that irradiates X-rays on the surface of the multilayer structure 32 exposed to deuterium in the storage chamber 31. A pressure gauge 42 for detecting the pressure in the storage chamber 31 into which deuterium has been introduced, an X-ray detector comprising a high-purity germanium detector 44 having a beryllium window 43, and a vacuum in the storage chamber 31, for example. A storage chamber vacuum gauge 45 for detecting the degree of pressure, a vacuum valve 46 for holding the storage chamber 31 in a vacuum state before introduction of deuterium, a turbo molecular pump 47 for putting the storage chamber 31 in a vacuum state, and a storage chamber 31 and T It is constituted by a rotary pump 48 for roughing the inside of turbomolecular pump 47.

  Then, the multilayer structure 32 is set so that the deuterium pressure is relatively high on the storage chamber 31 side of the multilayer structure 32 and the release chamber 34 side of the multilayer structure 32 is relatively low. By forming a pressure difference of deuterium on both sides, a flow of deuterium is created from the storage chamber 31 side to the discharge chamber 34 side. For example, as shown in FIG. 4, the multilayer structure 32 includes a mixed layer 22 of a substance having a relatively low work function (for example, a substance having a work function of less than 3 eV) and Pd on the surface of the Pd substrate 23. The Pd layer 21 is laminated on the surface of the mixed layer 22, and a substance 52 that performs nuclide conversion is added (contacted) on the surface of the Pd layer 21.

  The nuclide conversion apparatus 30 according to the present embodiment has the above-described configuration. Next, a method for performing nuclide conversion using the nuclide conversion apparatus 30 will be described with reference to the accompanying drawings.

First, for example, a Pd substrate 23 shown in FIG. 2 (for example, 25 mm long × 25 mm wide × 0.1 mm thick, purity 99.5% or more) is degreased by ultrasonic cleaning in acetone for a predetermined time. Then, in vacuum (for example, 1.33 × 10 ⁻⁵ Pa or less), annealing, that is, heat treatment is performed at a temperature of 900 ° C. for a predetermined time (for example, 10 hours) (step S01). Next, for example, the Pd substrate 23 annealed at room temperature is etched with heavy aqua regia for a predetermined time (for example, 100 seconds) to remove impurities on the surface (step S02).

Next, using a sputtering method using an argon ion beam, a film forming process is performed on the Pd substrate 23 after the etching process, thereby forming the structure 11. Here, for example, the thickness of the Pd layer 21 shown in FIG. 2 is set to 400 · 10 ⁻¹⁰ m, and the mixed layer 22 of the substance having a low work function and Pd has a thickness of, for example, as shown in FIG. and CaO layer 57 is 100 · 10 ^-10 m, for example having a thickness of 100 · 10 ^-10 m and a Pd layer 56 was formed by alternately stacking, a thickness of the mixed layer 22 1000 · 10 ^-10 m It was. Then, the Pd layer 21 was formed at 400 · 10 ⁻¹⁰ m on the surface of the mixed layer 22 to form the structure 11 (step S03).

  Next, a substance to be subjected to nuclide conversion is added to the film formation surface of the structure 11 by electrolysis of a dilute solution containing the substance to be subjected to nuclide conversion. For example, like the electrodeposition apparatus 60 shown in FIG. 6, the above-mentioned dilute solution is used as the electrolytic solution 62, the platinum anode 63 is connected to the anode of the power supply 61, and the structure 11 is connected to the cathode. Then, electrolysis is carried out for 10 seconds, and a substance 52 that generates a reaction on the surface of the structure 11 and performs nuclide conversion is added to form the multilayer structure 32 (step S04).

Then, the substance 52 that performs nuclide conversion of the multilayer structure 32 is directed to the storage chamber 31 side, and the storage chamber 31 and the discharge chamber 34 are respectively closed in an airtight state with the multilayer structure 32 interposed therebetween. The chamber 34 is evacuated by a rotary pump 39 and a turbo molecular pump 38. Then, the variable leak valve 33 is closed, the vacuum valve 46 is opened, and the storage chamber 31 is evacuated by the rotary pump 48 and the turbo molecular pump 47 (step S05). Next, after the degree of vacuum of the storage chamber 31 is sufficiently stabilized (for example, in a state of 1 × 10 ⁻⁵ Pa or less), the elements present on the surface of the multilayer structure 32 on the storage chamber 31 side are analyzed by XPS. (Step S06). That is, the surface of the multilayer structure 32 is irradiated with X-rays from the X-ray gun 41, and the energy of photoelectrons emitted from the atoms on the surface of the multilayer structure 32 excited by the X-ray irradiation is electrostatically discharged. Detected by the analyzer 40. Thereby, the element which exists on the surface by the side of the storage chamber 31 of the multilayer structure 32 is identified.

Next, after heating the multilayer structure 32 at a temperature of, for example, 70 ° C. with a heating device (not shown), the vacuum valve 46 is closed to evacuate the storage chamber 31, and the variable leak valve 33 is opened. Deuterium gas is introduced into the storage chamber 31 at a predetermined gas pressure, and nuclide conversion is started. Here, the predetermined gas pressure when introducing the deuterium gas is, for example, 1.01325 × 10 ⁵ Pa (so-called 1 atm). Then, a gaseous reaction product (for example, mass number A = 1 to 140) is measured by the mass analyzer 37 in the discharge chamber 34, and the weight released through the multilayer structure 32 into the discharge chamber 34 is measured. Evaluate the diffusion behavior of hydrogen. Further, X-rays are measured by the high purity germanium detector 44 on the storage chamber 31 side of the multilayer structure 32 (step S07). The amount of deuterium that has permeated through the multilayer structure 32 and released into the discharge chamber 34 is, for example, the degree of vacuum in the discharge chamber 34 detected by the discharge chamber vacuum gauge 36, the exhaust speed of the turbo molecular pump 38, and the like. Calculate based on

A predetermined time, for example, several tens of hours after the introduction of the deuterium gas into the storage chamber 31 is started, the temperature of the multilayer structure 32 is returned to room temperature. Then, the variable leak valve 33 is closed to stop the introduction of deuterium gas into the storage chamber 31, and the vacuum valve 46 is opened to evacuate the storage chamber 31 to complete the nuclide conversion. After the degree of vacuum absorption chamber 31 is sufficiently stable (e.g., the following conditions 1 × 10 ^-5 Pa) to analyze the elements present on the surface of the storage chamber 31 side of the multilayer structure 32 by XPS The product is measured (step S08).

  And the process of step S06-step S07 mentioned above is repeated, and the time change of nuclide conversion reaction is measured (step S09). Then, the multilayer structure 32 is taken out from the nuclide conversion device 30, and the nuclide conversion is finished (step S10).

As a medical nuclide obtained by the above nuclide conversion method, the following nuclear reactions are mentioned, for example.
³ He + 2α → ¹¹ C
³ He + 3α → ¹⁵ O
¹⁰ B + 2α → ¹⁸ F
¹⁴ N + 2α → ¹⁸ F
Here, α is a He nucleus (atomic number 2, mass number 4). That is, α corresponds to two deuterium D necessary for the reaction.

Next, the manufacturing method and manufacturing apparatus of the medical nuclide containing solution which are this invention are demonstrated.
FIG. 7 shows a schematic view of an apparatus for producing a medical nuclide-containing solution.
The medical nuclide-containing solution manufacturing apparatus 70 includes a container 72 that contains a physiological saline (electrolyte) 71, a platinum electrode 74 that is a cathode, a sample electrode 76 that is an anode, and a predetermined gap between the electrodes 74 and 76. And a direct current power supply 78 for applying a voltage of.
As the sample electrode 76, a multilayer structure 32 (see FIG. 4) including a material after nuclide conversion by the above-described nuclide conversion method is used.
When the nuclide-converted substance is a halogen element, the platinum electrode serves as the anode and the sample electrode serves as the cathode. In this way, the sample electrode is determined as the cathode or the anode in consideration of the material after the nuclide conversion.

When a predetermined voltage is applied between the electrodes 74 and 76 by the DC power supply 78, the nuclide-converted substance that is in contact with the surface of the multilayer structure 32 that is the sample electrode 76 (a depth of about 100 mm from the surface) is the physiological saline 71. It is electrolytically extracted inside. FIG. 8 shows a state where the substance 80 after the nuclide conversion is extracted from the sample electrode 76 into the physiological saline 71.
The physiological saline (medical nuclide-containing solution) containing the nuclide-converted substance thus electrolytically extracted is administered to the subject as a drug and used for the PET examination.

According to this embodiment, the following effects can be obtained.
Since the medical nuclide-containing solution can be produced with a simple device, the size of the device is not increased. Therefore, it can also be installed in hospitals where it is difficult to introduce large equipment.
In addition, by using physiological saline as the electrolytic solution, the solution after electrolytic extraction can be used as it is as a raw material for drugs such as PET. Thereby, since it can administer rapidly with respect to a subject, even if it is a nuclide with a short half life, it can be used for a diagnosis. On the other hand, a method of obtaining a substance after nuclide conversion by dissolving the multilayer structure 32 with a strong acid is also conceivable. However, since a purification process is required to obtain a drug, rapid administration becomes difficult.

[Second Embodiment]
Next, a second embodiment of the present invention will be described with reference to FIG.
FIG. 9 shows a medical nuclide-containing solution manufacturing apparatus 90 according to the present embodiment.
The medical nuclide solution manufacturing apparatus 90 includes a container 92 having a platinum electrode 94 having a cathode on one side and a sample electrode 96 having an anode on the other side.
A physiological saline (electrolytic solution) 91 is accommodated in the container 92. The internal volume of the container 92 is 1 cc or less. Although not shown in the figure, a syringe 97 can be attached and fixed to the container 92 at the top.
A DC power source (not shown) is connected between the electrodes 94 and 96. The distance between the electrodes 94 and 96 is preferably 1 mm or less.
Whether the sample electrode 96 is used as an anode or a cathode according to the substance after the nuclide conversion is the same as that in the first embodiment, and is omitted.
The point that a predetermined voltage is applied between the electrodes 94 and 96 and the substance after the nuclide conversion is electrolytically extracted from the sample electrode 96 is the same as that in the first embodiment, and is therefore omitted.

  In the present embodiment, the physiological saline 71 after electrolytic extraction is directly sucked by the syringe 97 and is administered to the subject using the syringe 97.

According to this embodiment, the following effects can be obtained.
By making the distance between the electrodes 94 and 96 provided in the container 92 close to 1 mm or less and setting the internal volume of the container 92 to 1 cc or less, a solution containing a high-concentration nuclide-converted substance can be obtained.
Moreover, the medical nuclide-containing solution can be quickly accommodated in the syringe 97 after the nuclide-converted substance is electrolytically extracted to obtain a medical nuclide-containing solution. In addition, since it can be easily carried as the syringe 97, administration to the subject can be performed easily and quickly.

[Third Embodiment]
Next, a third embodiment of the present invention will be described with reference to FIG.
In the present embodiment, when a medical nuclide-containing solution is sucked by a syringe as in the second embodiment, it is determined whether or not a solution containing a desired radiation dose is sucked.
The medical nuclide-containing solution measuring apparatus 100 shown in FIG. 10 can be provided in the medical nuclide-containing solution manufacturing apparatus 90 of the second embodiment. The medical nuclide-containing solution measuring apparatus 100 is installed on a first radiation measuring unit 104 installed on a lead (Pb) base 102 and a lead plate 106 on the first radiation measuring unit 104. The second radiation measurement unit 108 and a lead plate 110 provided on the second radiation measurement unit 108 are provided.
As the first radiation measurement unit 104 and the second radiation measurement unit 108, a NaI scintillator, a germanium detector, or the like can be used. It is preferable to adjust the sensitivity so that 511 keV can be detected.
The first radiation measurement unit 104 measures the amount of radiation emitted from the container 90. The second radiation measurement unit 108 measures the amount of radiation emitted from the syringe 97.
By shielding the radiation by the lead base 102 and the lead plates 106 and 110, the radiation detected by the first radiation measurement unit 104 and the second radiation measurement unit 108 does not interfere, and the detection accuracy is improved. Can be done.
The detection results of the first radiation measurement unit 104 and the second radiation measurement unit 108 are transmitted to a determination unit (not shown). In this determination unit, based on the detection results from the first radiation measurement unit 104 and the second radiation measurement unit 108, it is determined whether or not the physiological saline 91 sucked into the syringe 97 has a desired radiation dose.

The medical nuclide containing solution measuring device 100 of this embodiment is used as follows.
When the physiological saline 91 is aspirated with the syringe 97, the radiation dose measured by the first radiation measurement unit 104 decreases and the radiation dose measured by the second radiation measurement unit 108 increases. Based on the detection result, the determination unit determines whether or not the physiological saline 91 containing a desired amount of radiation has been sucked into the syringe.
Thus, according to this embodiment, since it can be determined whether the radiation dose contained in the physiological saline 91 sucked into the syringe 97 by the determination unit is appropriate, it is required for diagnosis such as PET. Can be obtained with good reproducibility.

In each of the above-described embodiments, a method of separately manufacturing the multilayer structure 32 including the nuclide-converted substance, installing the multilayer structure 32 as a sample electrode, and electrolytically extracting the substance after the nuclide conversion (so-called so-called). Although the batch type) has been described, the following continuous method can also be adopted.
A multi-layer structure is installed on one electrode, and nuclide conversion is performed on a substance that undergoes nuclide conversion by electrolysis. Then, after discharging and washing the solution used for electrolysis, physiological saline is accommodated and the polarity of the electrode is switched. And the above-mentioned electrolytic extraction is performed by applying a predetermined voltage between electrodes. Thus, it is good also as performing nuclide conversion and electrolytic extraction continuously using the same container. In addition, the nuclide conversion method by electrolysis can use the method disclosed by 2nd Embodiment after paragraph [0071] of Unexamined-Japanese-Patent No. 2002-202392.

It is the schematic explaining the principle of the nuclide conversion method used as a premise of this invention. It is sectional drawing which shows the structure used with the nuclide conversion method of FIG. It is a block diagram of the nuclide conversion apparatus which implement | achieves the nuclide conversion method. It is sectional drawing which shows the multilayer structure used with the nuclide conversion apparatus shown in FIG. (A) is a cross-sectional block diagram of a mixed layer, (b) is a cross-sectional view of a structure including a mixed layer. It is a schematic block diagram of the apparatus which adds the substance which performs nuclide conversion to a structure. It is the schematic which showed the medical nuclide containing solution manufacturing apparatus concerning 1st Embodiment of this invention. It is the schematic diagram which showed the state from which the substance after nuclide conversion is extracted from the sample pole in the physiological saline. It is the schematic which showed the medical nuclide containing solution manufacturing apparatus concerning 2nd Embodiment of this invention. It is the schematic which showed 3rd Embodiment of this invention and showed the medical nuclide containing solution manufacturing apparatus provided with the medical nuclide containing solution measuring device.

Explanation of symbols

70,90 Medical nuclide-containing solution manufacturing equipment 71,91 Saline (electrolyte)
72, 92 Container 76, 96 Sample electrode (one electrode)
78 DC power supply
97 Syringe

Claims (6)

A method for producing a medical nuclide-containing solution for producing a medical nuclide-containing solution containing a medical nuclide,
An agglomerated structure provided with a material after nuclide conversion that has caused a nuclear reaction in the material to which the nuclide conversion material is caused by flowing deuterium to the agglomerated structure contacted with the material to be subjected to nuclide conversion Immerse in the electrolyte as the electrode of
Extracting the nuclide-converted substance into the electrolyte by applying a predetermined voltage between the electrodes,
A method for producing a medical nuclide-containing solution, wherein the extracted electrolyte solution is a medical nuclide-containing solution.   The method for producing a medical nuclide-containing solution according to claim 1, wherein the electrolytic solution is physiological saline. A medical nuclide-containing solution production apparatus for producing a medical nuclide-containing solution containing a medical nuclide,
A container containing an electrolyte solution;
A pair of electrodes immersed in the electrolyte;
A power source for applying a predetermined voltage between these electrodes,
An agglomerated structure provided with a material after nuclide conversion that has caused a nuclear reaction in the material to which the nuclide conversion material is caused by flowing deuterium to the agglomerated structure contacted with the material to be subjected to nuclide conversion Said electrode,
Extracting the nuclide-converted substance into the electrolyte by applying a predetermined voltage between the electrodes,
An apparatus for producing a medical nuclide-containing solution, wherein the extracted electrolyte solution is a medical nuclide-containing solution.   4. The medical nuclide-containing solution manufacturing apparatus according to claim 3, wherein the electrolytic solution is physiological saline. A first radiation measurement unit for measuring a radiation amount emitted from the container;
A second radiation measurement unit for measuring the amount of radiation emitted from the syringe for aspirating the solution;
A determination unit that determines whether the electrolyte solution sucked into the syringe has a desired radiation dose based on detection results from the first radiation measurement unit and the second radiation measurement unit;
The medical nuclide containing solution manufacturing apparatus of Claim 3 or 4 characterized by the above-mentioned. A syringe containing a medical nuclide-containing solution containing a medical nuclide,
An agglomerated structure provided with a material after nuclide conversion that has caused a nuclear reaction in the material to which the nuclide conversion material is caused by flowing deuterium to the agglomerated structure contacted with the material to be subjected to nuclide conversion Immerse in the electrolyte as the electrode of
Extracting the nuclide-converted substance into the electrolyte by applying a predetermined voltage between the electrodes,
A syringe containing the extracted electrolyte as a medical nuclide-containing solution.

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