JP2008102078A - Method and device for manufacturing radioactive molybdenum and radioactive molybdenum manufactured by this method and this device - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide an efficient manufacturing method using no uranium for a material in a method for manufacturing radioactive molybdenum<SP>99</SP>Mo as the parent nuclide of radioactive technetium (<SP>99m</SP>Tc), a radioactive diagnostic reagent. <P>SOLUTION: The efficient manufacture of<SP>99</SP>Mo is conducted by generating<SP>99</SP>Mo through the<SP>98</SP>Mo(n, γ) reaction by irradiating an Mo water solution where an Mo compound is dissolved in water with neutrons in an irradiation capsule placed in the core of a nuclear reactor and recovering the Mo water solution sequentially or batch by batch. <P>COPYRIGHT: (C)2008,JPO&INPIT

Description

TECHNICAL FIELD The present invention relates to a method and apparatus for efficiently producing radioactive molybdenum ⁹⁹ Mo, which is a parent nuclide of radioactive technetium ( ^99m Tc) which is a radiodiagnostic agent, and radioactive molybdenum produced by the method and apparatus.

Radiotechnetium ( ^99m Tc), which is widely used all over the world for the diagnosis of cancer, visceral diseases, or functional tests of internal organs, has a short life span (half-life) of 6.0 hours. A certain radioactive molybdenum ⁹⁹ Mo is manufactured, and ^99m Tc is extracted from the ⁹⁹ Mo (half-life: 66 hours) and used for medical diagnosis.

The ⁹⁹ Mo is manufactured by using highly enriched uranium enriched by about 95% of ²³⁵ U as a raw material and irradiating it with a neutron in a nuclear reactor to cause fission reaction and extracting ⁹⁹ Mo in the fission product. Yes. This method of using enriched uranium has been promoted around the world by the International Atomic Energy Agency (IAEA) to switch to a technology that uses low-enriched uranium with a uranium ( ^235U ) enrichment of 20% or less, particularly from the viewpoint of non-proliferation. The technology is being developed all over the world. However, when low-enriched uranium with a uranium enrichment of 20% or less is used as a raw material for ⁹⁹ Mo production, a large amount of radioactive waste is generated along with the fission reaction, especially about 25 times the amount of plutonium produced. New problems have been raised. Therefore, the fission method itself using uranium as a raw material for ⁹⁹ Mo production has been reviewed.

^The method of using uranium as a raw material for ⁹⁹ Mo production has the above-mentioned problems. On the other hand, as a method not using uranium as a raw material for ⁹⁹ Mo production, a solid material of natural Mo compound or Mo compound enriched with ⁹⁸ Mo is used. The production of ⁹⁹ Mo by the (n, γ) method in which neutrons are irradiated in a nuclear reactor has been put into practical use. In this case, molybdenum oxide (MoO ₃ ), which is a natural isotope Mo compound, is irradiated with neutrons in a nuclear reactor in either a powder or pellet form, resulting in a nuclear reaction of ⁹⁸ Mo (n, γ) ⁹⁹ Mo. (This nuclear reaction is hereinafter referred to as (n, γ) reaction or (n, γ) method). This method can only produce ⁹⁹ Mo, which has a very low specific activity compared to the fission method using uranium as a raw material. However, unlike the uranium method, it does not generate radioactive waste associated with fission and can be produced at low cost. It has been studied for a long time as a method having advantages, and is currently put into practical use as a gel method ^99m Tc generator. However, the gel method ^99m Tc generator of the (n, γ) method has problems in terms of reproducibility and quality, especially in production, and has not been widely used. Since the specific activity of ⁹⁹ Mo produced by the (n, γ) method is low, the conventional technique for recovering ^99m Tc with a small column type could not be put into practical use. According to the following Patent Document 1 and Patent Document 2, ^99m Tc can be recovered from the (n, γ) method ⁹⁹ Mo having a low specific activity, so that the Mo compound is used as a raw material (n, γ). There is an expectation for practical application of a method for producing ⁹⁹ Mo by this method.
JP-A-8-309182 Japanese Patent Laid-Open No. 10-30027

As described above, the solid Mo compound irradiated with neutrons in a nuclear reactor (n, gamma) to produce a ⁹⁹ Mo in the reaction, then the utility of the method for extracting the ^99m Tc was found. The present invention relates to a method for continuously increasing the production of ⁹⁹ Mo at a low cost by changing the Mo compound irradiated in a nuclear reactor from a solid state to an aqueous solution state.

⁹⁹ Mo by the (n, γ) method so far is generally a solid material processed into powder or pellets of molybdenum oxide (MoO ₃ ), and it is sealed in a sealed container, and the material irradiation equipment of the reactor In the reactor, it is collected after being irradiated with neutrons for a certain period of time (generally 5-7 days), then the recovered sealed container is opened and the contents in it ( ⁹⁹ Mo is generated and mixed in MoO ₃₎ ) Is reacted with an alkaline solution such as caustic soda or aqueous ammonia and dissolved. However, the adjustment and quality control of molybdenum oxide as a raw material is complicated, and it is necessary to continuously irradiate the same irradiator during irradiation for a certain period of time, so it is not possible to replace the irradiator containing the raw material There were problems such as low production capacity of ⁹⁹ Mo.

A conventional facility for irradiating a solid MoO ₃ raw material requires a huge cost for installation, has a low production capacity, and uses a new container each time an irradiation container (made of metal) filled with the MoO ₃ raw material is irradiated. In addition, after use (after irradiation), the container itself is activated and becomes radioactively contaminated waste, which increases the amount of ⁹⁹ Mo produced and increases the radioactively contaminated waste.

The present invention first uses a Mo aqueous solution in which a Mo compound containing ⁹⁸ Mo in a natural isotope ratio is dissolved in water, or a Mo aqueous solution in which a Mo compound in which ⁹⁸ Mo is concentrated to a natural isotope ratio or more is dissolved in water. Irradiating neutrons in the reactor to activate ⁹⁸ Mo to produce ⁹⁹ Mo in the Mo aqueous solution and recovering the Mo aqueous solution to obtain ⁹⁹ Mo, or circulating or circulating the Mo aqueous solution. the ⁹⁸ Mo to obtain a ⁹⁹ Mo by collecting continuous or batchwise Mo solution to produce a ⁹⁹ Mo in Mo solution by activation Te, a method for producing a radioactive molybdenum, wherein more.

The present invention secondly irradiates a Mo compound containing ⁹⁸ Mo with a natural isotope ratio or a Mo compound enriched with ⁹⁸ Mo more than the natural isotope ratio, and an aqueous Mo solution in which they are dissolved in water in a nuclear reactor. ⁹⁹ Mo is produced by irradiating an aqueous Mo solution characterized by ammonium molybdate as the Mo compound with neutrons in a nuclear reactor to produce ⁹⁹ Mo. Is the method.

The present invention thirdly irradiates a Mo compound containing ⁹⁸ Mo with a natural isotope ratio or a Mo compound enriched with ⁹⁸ Mo above the natural isotope ratio, or an aqueous Mo solution in which they are dissolved in water in a nuclear reactor. In the first or second method for producing ⁹⁹ Mo, hydrogen and oxygen gases produced by radiolysis of water when an aqueous solution is irradiated in a nuclear reactor are extracted continuously or periodically, A function of purging and discarding hydrogen and oxygen in the extraction gas with an inert gas, or a function of recombining hydrogen and oxygen in the extraction gas with a catalyst and recovering them back to water, generated by radiolysis of these waters This is a method for producing radioactive molybdenum, characterized in that ⁹⁹ Mo is produced by irradiating an aqueous Mo solution characterized by having a function of removing and recovering hydrogen and oxygen with neutrons in a nuclear reactor.

Fourthly, the present invention relates to a Mo aqueous solution in which a natural Mo compound containing ⁹⁸ Mo in a natural isotope ratio is dissolved in water, or a Mo aqueous solution in which a Mo compound in which ⁹⁸ Mo is concentrated to a natural isotope ratio or more is dissolved in water. In order to irradiate neutrons in a nuclear reactor, the aqueous Mo solution is circulated in the nuclear reactor to activate ⁹⁸ Mo, thereby generating ⁹⁹ Mo in the aqueous Mo solution, and then the aqueous Mo solution continuously or batchwise. ⁹⁹ Mo is obtained by recovering ⁹⁹ Mo In the ⁹⁹ Mo manufacturing method, a circulation type irradiation capsule is installed in the reactor core, and ⁹⁹ Mo is produced and recovered continuously or batchwise by circulating Mo aqueous solution in the capsule. This is an apparatus for producing a Mo aqueous solution liquid-containing type radioactive molybdenum having a function capable of being produced.

Fifth, the present invention relates to a Mo aqueous solution in which a natural Mo compound containing ⁹⁸ Mo in a natural isotope ratio is dissolved in water, or a Mo aqueous solution in which a Mo compound in which ⁹⁸ Mo is concentrated to a natural isotope ratio or more is dissolved in water. In the Mo aqueous solution flow-through type ⁹⁹ Mo manufacturing apparatus having a function capable of generating and recovering ⁹⁹ Mo continuously or batchwise by circulating Mo aqueous solution in a flow-type irradiation capsule installed in the core, a certain amount of Equipment for injecting Mo aqueous solution continuously or batchwise, equipment for recovering produced ⁹⁹ Mo continuously or batchwise, extraction and removal of gaseous hydrogen and oxygen generated by radiolysis reaction of water generated in irradiation capsule Equipment that is equipped with a catalyst that has the function of returning the extracted gaseous hydrogen and oxygen to water through a recombination reaction, and removing heat from the irradiation capsule. Heat exchanger circulation of Mo solution who attached facilities for the generated ⁹⁹ Mo continuously or batchwise extraction to recover equipment, equipment for measuring the produced amount and the recovery amount of ⁹⁹ Mo, and further produced was collected ⁹⁹ Mo and the coexisting daughter nuclide ^99m Tc to shield radiation such as gamma rays generated from the radiation, an equipment for producing ⁹⁹ Mo, and a facility for recovering it are injected with an aqueous Mo solution. It is an apparatus for producing radioactive molybdenum for passing and collecting liquids.

Sixth, the present invention relates to a Mo aqueous solution in which a natural Mo compound containing ⁹⁸ Mo in a natural isotope ratio is dissolved in water, or a Mo aqueous solution in which a Mo compound in which ⁹⁸ Mo is concentrated to a natural isotope ratio or more is dissolved in water. In order to irradiate neutrons in a nuclear reactor, the aqueous Mo solution is circulated in the nuclear reactor to activate ⁹⁸ Mo, thereby generating ⁹⁹ Mo in the aqueous Mo solution, and then the aqueous Mo solution continuously or batchwise. ⁹⁹ Mo is obtained by recovering ⁹⁹ Mo In the ⁹⁹ Mo manufacturing method, a circulation type irradiation capsule is installed in the reactor core, and ⁹⁹ Mo is produced and recovered continuously or batchwise by circulating Mo aqueous solution in the capsule. It is a radioactive molybdenum manufactured by a ⁹⁹ Mo manufacturing apparatus of Mo aqueous solution passage type which has a function which can be performed.

According to the present invention, a conventional method using the irradiation equipment to be much called low cost irradiated Kyapuseru compared to costly irradiation equipment, by a method of passing liquid continuously or batchwise Mo solution therein, ⁹⁹ The production capacity of Mo can be increased and continuously produced at low cost.

According to the present invention, by installing a liquid-flow type irradiation capsule capable of injecting and collecting a solution from the outside, the intended ⁹⁹ Mo can be produced simply by injecting an aqueous Mo solution continuously or batchwise from the outside, There is no generation of radioactively contaminated waste as in the case of the irradiation container of the conventional method that is generated with the ⁹⁹ Mo production. In addition, the generated aqueous Mo solution containing ⁹⁹ Mo does not require a treatment operation after recovery, and can be shipped by simply collecting it in an exclusive container such as a glass vial and packing it. The entire process from recovery of the target ⁹⁹ Mo can be simplified compared to the conventional method.

As described above, according to the present invention, the equipment cost is low, there is no generation of radioactive contaminated waste associated with the manufacturing, the entire manufacturing process is simple, and ⁹⁹ Mo manufacturing cost is low for those reasons. It has the features such as.

In the case of the conventional solid irradiation method, MoO ₃ powder or processed into a pellet is used, but ⁹⁹ Mo is produced in large quantities after neutron irradiation. The shape is desirable. The reason for this is that if the powder contains a large amount of radioactive ⁹⁹ Mo at the stage of melting it, the powder may be scattered or spilled, which may contaminate the work area with radioactive material ( ⁹⁹ Mo). Because there is. Now, adjusting MoO ₃ as a raw material into a pellet form involves a complicated operation in the pelletization, and it is difficult to manage and maintain the quality because impurities are easily mixed in the pelletization operation. On the other hand, in the case of the Mo aqueous solution that is the raw material of the present invention, it is possible to adjust the Mo compound (ammonium molybdate) to be used simply by dissolving it in high purity water by keeping the quality of the Mo compound (ammonium molybdate) high. Even if there are impurities in the Mo aqueous solution, it can be adsorbed and removed simply by passing it through an alumina column or the like. Therefore, in the case of the Mo aqueous solution irradiation method, the irradiation material can be easily adjusted and high quality compared to the solid MoO ₃ irradiation method. Easy to maintain.

Next, in the case of the solid irradiation method, when the MoO ₃ irradiator is in powder form, it is first sealed with a quartz tube and then further sealed in a metal (generally aluminum-based metal) irradiation container. . When the MoO ₃ irradiated body is in the form of pellets, it is sealed and sealed directly in a metal irradiation container. Moreover, since these irradiation containers are activated by neutron irradiation, they become radioactively contaminated waste. On the other hand, if the Mo solution irradiation method of the present invention is the only operation that injected into irradiated Kyapuseru through the pipe a predetermined amount of Mo solution continuously or batchwise pump, ⁹⁹ Mo for irradiation vessel is unnecessary No radioactively contaminated waste from production.

The ⁹⁹ Mo production capacity in the case of the solid irradiation method is, for example, the material test reactor JMTR possessed by the Japan Atomic Energy Agency, 220 Ci ( ⁹⁹ Mo) / week when the existing equipment is remodeled, and even when it is further expanded There is a trial calculation that the total cost is 570 Ci ( ⁹⁹ Mo) / week, and the cost of remodeling and installation is about 700 to 1.5 billion yen. On the other hand, in the case of the capsule for solution irradiation of the present invention, 277 mL of a 28% aqueous solution of ammonium molybdate is placed in a 700 mm high zone (effective internal volume: 1.66 L) where the capsule size is 55 mmφ and the neutron is irradiated. / day there is almost the same one system 569Ci ⁽⁹⁹ Mo) / week of production capacity and solid irradiation method after the above-mentioned facility expansion by simply passed through the column at a rate of, yet 200 million per the equipment installation cost one system Since it is estimated to be about a circle, the superiority of the present invention can be seen in terms of ⁹⁹ Mo production capacity and equipment cost compared to the conventional method.

Next, when compared with the ⁹⁹ Mo manufacturing process, in the case of the conventional solid-state irradiation method, the irradiation vessel is sent into the reactor with the material irradiation equipment of the reactor and irradiated with neutrons for a fixed time (generally 5 to 7 days). After that, the sealed container is recovered, and the contents ( ⁹⁹ Mo is generated and mixed in MoO ₃ ) are then reacted with an alkaline solution such as caustic soda or aqueous ammonia and dissolved. Therefore, the process to make it ready for shipment as ⁹⁹ Mo products is complicated, such as the fact that the irradiation body cannot be replaced in the middle, and the MoO ₃ irradiation body containing ⁹⁹ Mo needs to be opened and dissolved in another facility. It is. On the other hand, in the case of the Mo aqueous solution irradiation method of the present invention, the Mo aqueous solution containing ⁹⁹ Mo can be recovered simply by operating the pump of the ⁹⁹ Mo recovery facility, and can be shipped simply by separating and packing in that state. Therefore, the entire process from raw material charging to ⁹⁹ Mo product recovery is simple.

In addition, the efficient manufacturing method of a socially useful radioactive substance by the solution irradiation method of the present invention can also be used for manufacturing other radioactive substances. As an example, for the case of radioactive rhenium available for cancer therapy ⁽¹⁸⁸ Re) is shorter its service life ⁽¹⁸⁸ Re half life: 17.5 hours), producing radioactive tungsten ¹⁸⁸ W is the parent nuclide of ¹⁸⁸ Re Then, ¹⁸⁸ Re is extracted from the ¹⁸⁸ W and used for treatment. In this case, according to the present invention, a W aqueous solution in which a W compound containing a natural isotope ratio of ¹⁸⁶ W is dissolved in water or a W aqueous solution in which a W compound in which ¹⁸⁶ W is concentrated to a natural isotope ratio or more is dissolved in water is used. Then, ¹⁸⁸ W is generated in the aqueous W solution by irradiating neutrons in the nuclear reactor and performing two-step (n, γ) reaction of ¹⁸⁶ W (n, γ) ¹⁸⁷ W → ¹⁸⁷ W (n, γ) ¹⁸⁸ W ¹⁸⁸ W is obtained by recovering the W aqueous solution, or ¹⁸⁶ W is activated by circulating or circulating the W aqueous solution to generate ¹⁸⁸ W in the aqueous W solution, continuously or batchwise. The target ¹⁸⁸ W can be efficiently produced by the method of obtaining ¹⁸⁸ W by collecting

One embodiment of the present invention is shown in FIG. The solution irradiation capsule 4 is installed in the fuel portion (core) of the nuclear reactor. The capsule is connected to an external Mo aqueous solution injection facility (6, 7, 8) and a generated ⁹⁹ Mo recovery vessel 11 by a pipe 9 for introducing an Mo aqueous solution and a pipe 10 for recovering. An aqueous ammonium molybdate solution is prepared in advance and placed in a tank of the Mo aqueous solution supply system 6. The aqueous Mo solution is injected by a pump 7 and injected into an irradiation capsule via a pipe 9. By injecting this Mo aqueous solution continuously or batchwise, the time for neutron irradiation in the capsule can be adjusted. Irradiation time of the Mo aqueous solution is required for 5 to 7 days, but the Mo aqueous solution in the capsule is hydrogen and oxygen gas generated by the external valve operation and the circulation pump 8 to circulate the system and by the radiolysis of the heat exchanger 13 and water. Is removed by the extraction gas processing system 14, it is possible to remove the gas generated by radiation decomposition of heat and water accumulated in the capsule due to radiation irradiation in the core.

⁹⁹ Mo can be recovered by recovering a certain amount of Mo aqueous solution that has been irradiated with a certain amount of neutrons in a ⁹⁹ Mo recovery vessel 11. Since high-activity ⁹⁹ Mo is collected in the container 11, radiation such as γ rays emitted from the container 11 must be shielded with lead or the like to reduce the radiation exposure of the operator. ^{Since the 99} Mo recovery operation can be performed only by operating the pumps 8 and 15, it can be automated. In addition, hydrogen and oxygen produced by water radiolysis of Mo aqueous solution in the capacity of 1.66 L in the capsule are small as 0.18 NL and 0.09 NL per day respectively. The air is extracted and removed by the extraction gas processing system 14 during circulation and recovery. This hydrogen and oxygen gas is purged with an inert gas such as nitrogen gas or helium gas and exhausted to the outside of the system, or hydrogen and oxygen are recombined using a catalyst to return to the water state. Is returned to the aqueous Mo solution.

^The aqueous Mo solution recovered in the ⁹⁹ Mo recovery container 11 is transferred to the ⁹⁹ Mo sorting device 17, and the solution is directly collected into a ⁹⁹ Mo shipping container such as a glass vial. This ⁹⁹ Mo shipping container can be shipped as a ⁹⁹ Mo product by packing it in a transport container with radiation shielding. In the case of Mo aqueous solution irradiation method, ⁹⁹ Mo recovery and ⁹⁹ Mo product shipment can be done in a short time, so it is possible to minimize the loss due to the natural decay of ⁹⁹ Mo (half life: 66 hours) with a short life. become.

The present invention enables efficient production of ^99m Tc parent nuclide ⁹⁹ Mo, which is used in medical diagnosis on a daily basis in large quantities in the world including Japan. Most of ⁹⁹ Mo is currently produced by a method using highly enriched uranium as a raw material. However, since the conventional fission method using uranium as a raw material has the problems described in the column 0003, there is a movement to switch to a manufacturing method of (n, γ) method that does not currently use uranium as a raw material. The present invention is to be the (n, gamma) in the case of mass production of ⁹⁹ Mo in method, it enables major social contribution.

1 shows an Mo aqueous solution passing type ⁹⁹ Mo production apparatus according to an embodiment of the present invention.

Explanation of symbols

1 reactor 2 reactor core 3 reactor water 4 irradiated for Kyapuseru 5 shielded with glovebox 6 Mo solution replenishment system 7 solution recovery pipe 11 ⁹⁹ to solution introducing pipe 10 Kyapuseru to Mo solution infusion pump 8 Mo solution circulating pump 9 Kyapuseru Mo recovery container (with radiation shielding)
12 ⁹⁹ Mo recovery amount measuring device 13 Heat exchanger 14 Extraction gas processing system 15 Circulation pump 16 ⁹⁹ Mo fractionation device 17 ⁹⁹ Mo shipping container 18 Transport container (with radiation shield)
19 Mo aqueous solution injection and ⁹⁹ Mo recovery equipment

Claims (6)

Using a Mo aqueous solution in which a Mo compound containing ⁹⁸ Mo of a natural isotope ratio is dissolved in water or a Mo aqueous solution in which a Mo compound enriched with ⁹⁸ Mo to a natural isotope ratio or more is dissolved in water, Irradiates ⁹⁸ Mo to generate ⁹⁹ Mo in the Mo aqueous solution and recover the Mo aqueous solution to obtain ⁹⁹ Mo, or circulate or circulate the Mo aqueous solution to activate ⁹⁸ Mo. A method for producing radioactive molybdenum, characterized in that ⁹⁹ Mo is produced in an aqueous Mo solution and ⁹⁹ Mo is obtained by recovering the aqueous Mo solution continuously or batchwise. The method for producing radioactive molybdenum according to claim 1, wherein the Mo compound is ammonium molybdate. ⁹⁹ Mo is produced by irradiating a Mo compound containing ⁹⁸ Mo with a natural isotope ratio or a Mo compound enriched with ⁹⁸ Mo to a natural isotope ratio or an aqueous solution of Mo dissolved in water in a nuclear reactor. The method according to any one of claims 1 to 2, wherein hydrogen and oxygen gases generated by water radiolysis when irradiated with an aqueous solution in a nuclear reactor are extracted continuously or periodically, and the extracted gas A function of purging and discarding hydrogen and oxygen in an inert gas, or a function of recombining hydrogen and oxygen in an extraction gas with a catalyst and returning them to water, hydrogen generated by radiolysis of these waters and A method for producing radioactive molybdenum, characterized in that ⁹⁹ Mo is produced by irradiating an aqueous Mo solution characterized by having an oxygen removal and recovery function with neutrons in a nuclear reactor. Neutrons in a nuclear reactor for Mo aqueous solution in which natural Mo compound containing ⁹⁸ Mo of natural isotope ratio is dissolved in water, or Mo aqueous solution in which ⁹⁸ Mo is concentrated to a natural isotope ratio or higher is dissolved in water. The Mo aqueous solution is circulated in the reactor for irradiation to generate ⁹⁹ Mo by activating ⁹⁸ Mo, and then ⁹⁹ Mo is recovered continuously or batchwise to recover ⁹⁹ Mo. In the ⁹⁹ Mo manufacturing method, a circulation type irradiation capsule is installed in the core of the nuclear reactor, and ⁹⁹ Mo can be generated and recovered continuously or batchwise by circulating an aqueous Mo solution in the capsule. An apparatus for producing an aqueous Mo solution liquid-permeable type radioactive molybdenum. Distribution type installed in the core of Mo aqueous solution in which natural Mo compound containing ⁹⁸ Mo of natural isotope ratio is dissolved in water, or Mo aqueous solution in which ⁹⁸ Mo is concentrated to a natural isotope ratio or more is dissolved in water In an aqueous Mo solution flow-through type ⁹⁹ Mo production system that has the function of generating and recovering ⁹⁹ Mo continuously or batchwise by circulating the Mo aqueous solution in the irradiation capsule, a certain amount of Mo aqueous solution is continuously or batched. Equipment for continuous injection, equipment for recovering the produced ⁹⁹ Mo continuously or batchwise, equipment for extracting and removing hydrogen and oxygen of the gas generated by the radiolysis reaction of water produced in the irradiation capsule, the extracted gas Equipment filled with a catalyst that has the function of returning hydrogen and oxygen to water through a recombination reaction, and a heat exchanger for heat removal in the irradiation capsule Circulation equipment Mo solution who attached, resulting ⁹⁹ Mo continuously or batchwise extraction to recover equipment, daughter equipment, which further generated to recover the ⁹⁹ Mo and coexistence of measuring the produced amount and the recovery amount of ⁹⁹ Mo In order to inject, pass, and recover Mo aqueous solution, which consists of facilities for shielding radiation such as γ rays generated from ^99m Tc of nuclides, facilities for manufacturing these ⁹⁹ Mo, and facilities for recovery Radioactive molybdenum production equipment. Neutrons in a nuclear reactor for Mo aqueous solution in which natural Mo compound containing ⁹⁸ Mo of natural isotope ratio is dissolved in water, or Mo aqueous solution in which ⁹⁸ Mo is concentrated to a natural isotope ratio or higher is dissolved in water. The Mo aqueous solution is circulated in the reactor for irradiation to generate ⁹⁹ Mo by activating ⁹⁸ Mo, and then ⁹⁹ Mo is recovered continuously or batchwise to recover ⁹⁹ Mo. In the ⁹⁹ Mo manufacturing method, a flow-type irradiation capsule is installed in the reactor core, and the aqueous Mo solution is passed through the capsule to allow ⁹⁹ Mo to be produced and recovered continuously or batchwise. A radioactive molybdenum produced by a liquid type ⁹⁹ Mo production apparatus.