阅读说明：本技术 生产稳定同位素的方法 (Method for producing stable isotopes ) 是由 李佼珊 于 2021-08-02 设计创作，主要内容包括：本发明实施例公开了一种生产稳定同位素的方法,包括：辐照步骤：将用于生产稳定同位素的原料置于辐照装置内部进行辐照,以形成所述稳定同位素。与现有技术中利用物理方法或化学方法提取已有稳定同位素的方法相比,本发明的技术方案具有分离方便、无需级联、能耗低、短时间内更易于得到高丰度的稳定同位素产品的优点。(The embodiment of the invention discloses a method for producing stable isotopes, which comprises the following steps: an irradiation step: and placing raw materials for producing stable isotopes in an irradiation device for irradiation so as to form the stable isotopes. Compared with the method for extracting the existing stable isotope by using a physical method or a chemical method in the prior art, the technical scheme of the invention has the advantages of convenient separation, no need of cascade, low energy consumption and capability of obtaining high-abundance stable isotope products more easily in a short time.)

1. A method of producing a stable isotope, comprising:

an irradiation step: and placing raw materials for producing stable isotopes in an irradiation device for irradiation so as to form the stable isotopes.

2. The method of claim 1, further comprising, prior to the irradiating step:

raw material determination: the raw material is determined according to the type of the stable isotope, the type of the particle provided by the irradiation device, the particle energy and the nuclear reaction capable of generating the stable isotope.

3. The method of claim 2, further comprising, after the feedstock determining step and before the irradiating step:

an irradiation condition determining step: and determining the particle energy in the irradiation process according to a plurality of nuclear reactions of the raw material under different particle energy conditions and the nuclear reaction cross section of each nuclear reaction.

4. The method of claim 3, wherein the irradiating step is further followed by:

a separation step: separating the stable isotope from the irradiated mixture comprising the starting material and the stable isotope.

5. The method according to claim 4, characterized in that in the separation step, the method of separating the stable isotope from the mixture is determined according to the physical state of the raw material and the stable isotope.

6. The method of claim 5, wherein, when the starting material and the stable isotope are both in the solid state,

the separating step comprises: dissolving the mixture in an acid or alkali solution to form a solution; separating the stable isotope from the solution.

7. The method of claim 6, wherein said separating said stable isotope from said solution comprises:

separating the stable isotope from the solution using at least one of precipitation, ion exchange and extraction chromatography.

8. The method according to claim 5, wherein when one of the starting material and the stable isotope is in a gaseous state and the other is in a solid state,

the separating step comprises: separating the stable isotope directly from the starting material.

9. The method of claim 5, wherein, when the starting material and the stable isotope are both in a gaseous state,

the separating step comprises: separating the stable isotope from the mixture using a gas separation process.

10. The method of claim 5, wherein the target form of the feedstock irradiated in the irradiation device is determined based on the stable isotope separation method.

11. The method of claim 10, wherein when the target form is a solid target, the method further comprises, after the feedstock material determining step and before the irradiating step:

preparing a target: forming the feedstock into a solid target;

the irradiating step further comprises: and placing the solid target piece inside the irradiation device for irradiation.

12. The method of claim 11, wherein the irradiation device is a reactor,

the target preparation step comprises: providing a target cylinder; placing the feedstock into the target cylinder to form the solid target.

13. The method of claim 12, wherein the feedstock is in a solid state,

the target preparation step further comprises: and curing and molding the raw materials, and then placing the raw materials into the target cylinder to prepare the solid target piece.

14. The method of claim 12, wherein the feedstock is in a gaseous state,

the target preparation step further comprises: and filling the raw materials into the target cylinder, and sealing the target cylinder to obtain the solid target.

15. The method of claim 11, wherein the irradiation device is an accelerator, the feedstock is in a solid state,

the target preparation step comprises: providing a target holder; bonding the feedstock to the backing plate to form the solid target.

16. The method of claim 10, wherein when the target is in the form of a gas target,

the irradiating step further comprises: placing the feedstock inside a gas target of the irradiation device.

Technical Field

The invention relates to the technical field of isotopes, in particular to a method for producing stable isotopes.

Background

Isotopes are nuclides with the same atomic number and different mass numbers, occupy the same position in a periodic table of elements, have almost the same chemical properties, but have different mass spectrum properties, nuclear properties and physical properties, and are classified into stable isotopes and radioactive isotopes. Compared with radioactive isotopes, the stable isotopes have the advantages of safety, no pollution and easy control, and are widely applied to the research and production fields of national defense, energy, medicine, nutrition, metabolism, food, agriculture, ecology, geology and the like.

Methods for producing stable isotopes generally fall into two categories: one is a physical method such as a thermal diffusion method, a gas centrifugation method, a gas dynamic method, an electromagnetic method, a laser method, a particle cyclotron resonance method, or the like; the second method is a chemical method, such as a rectification method, a chemical exchange method, a solvent extraction method, an ion exchange method and the like.

Disclosure of Invention

The present application provides a novel method for producing stable isotopes, comprising:

an irradiation step: and placing raw materials for producing stable isotopes in an irradiation device for irradiation so as to form the stable isotopes.

Drawings

Other objects and advantages of the present invention will become apparent from the following description of the invention which refers to the accompanying drawings, and may assist in a comprehensive understanding of the invention.

FIG. 1 is a flow diagram of a method for producing a stable isotope according to one embodiment of the present invention;

FIG. 2 illustrates reactor irradiation⁹A Be nuclear reaction excitation function;

FIG. 3 illustrates accelerator accelerating T-kernel bombardment⁹A Be nuclear reaction excitation function;

FIG. 4 shows accelerator d-Nuclear bombardment⁹A Be nuclear reaction excitation function;

FIG. 5 illustrates reactor irradiation¹⁶An O-nuclear reaction excitation function;

FIG. 6 illustrates reactor irradiation¹⁹F, nuclear reaction excitation function;

FIG. 7 illustrates reactor irradiation²³A Na nuclear reaction excitation function;

FIG. 8 illustrates reactor irradiation²⁷An Al nuclear reaction excitation function;

FIG. 9 illustrates reactor irradiation³¹A P-nuclear reaction excitation function;

FIG. 10 illustrates reactor irradiation⁸⁶A Kr nuclear reaction excitation function;

FIG. 11 illustrates reactor irradiation⁸⁷Sr nuclear reaction excitation function;

FIG. 12 illustrates reactor irradiation¹⁸⁵A Re nuclear reaction excitation function;

FIG. 13 illustrates reactor irradiation⁹Be production⁶The Li productivity and the product abundance;

FIG. 14 illustrates reactor irradiation⁹Be production⁷The Li productivity and the product abundance;

FIG. 15 shows accelerator irradiation⁹Be production⁷The Li productivity and the product abundance;

FIG. 16 shows accelerator irradiation⁹Be production¹⁰B, capacity and product abundance;

FIG. 17 illustrates reactor irradiation¹⁶Production of O¹³C productivity and product abundance;

FIG. 18 illustrates reactor irradiation¹⁹F production¹⁶O productivity and product abundance;

FIG. 19 illustrates reactor irradiation¹⁹F production¹⁹O productivity and product abundance;

FIG. 20 illustrates reactor irradiation²³Na production²²Ne productivity and product abundance;

FIG. 21 illustrates reactor irradiation³¹P production²⁸The productivity and the product abundance of Si;

FIG. 22 illustrates reactor irradiation²⁷Production of Al²⁸The productivity and the product abundance of Si;

FIG. 23 illustrates reactor irradiation⁸⁶Kr production⁸⁷The productivity and product abundance of Rb;

FIG. 24 illustrates reactor irradiation⁸⁷Production of Sr⁸⁷The productivity and product abundance of Rb;

FIG. 25 illustrates reactor irradiation¹⁸⁵Production of Re¹⁸⁴Capacity of W and product abundance.

Detailed Description

In order to make the objects, technical solutions and advantages of the present invention more apparent, the technical solutions of the present invention will be described clearly and completely with reference to the accompanying drawings of the embodiments of the present invention. It should be apparent that the described embodiment is one embodiment of the invention, and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the invention without any inventive step, are within the scope of protection of the invention.

Among the existing stable isotope production methods, some production methods have high heat consumption and low separation coefficient in the production process; or high energy consumption and low yield; or the cascade is more, and the stable isotope product with high abundance can be obtained only after a long time. In view of the above drawbacks, the person skilled in the art generally improves the prior art by optimizing the separation conditions, optimizing the cascade.

In the prior art, nuclear reactions are generally used to produce radioisotopes. In particular, artificial radioisotopes are typically produced by irradiating a suitable target material for an appropriate time in a neutron or charged particle beam in a reactor or accelerator.

However, as described above, the conventional methods for producing stable isotopes extract stable isotopes that are already present in nature, and do not produce stable isotopes by nuclear reaction.

The applicant believes that the nuclear reaction has not been used to produce stable isotopes in the prior art for several reasons:

1. the stable isotope exists in nature in a certain abundance, and the high-abundance stable isotope product can be obtained by directly utilizing the existing physical method or chemical method for enrichment.

2. The production of stable isotopes by nuclear reactions has not been envisaged by the skilled person.

However, the inventors of the present application have found that the production of stable isotopes by nuclear reactions is economically advantageous. Accordingly, embodiments of the present application provide a method of producing a stable isotope, comprising: an irradiation step: and placing raw materials for producing stable isotopes in an irradiation device for irradiation so as to form the stable isotopes.

It will be readily understood by those skilled in the art that the source material is irradiated inside the irradiation device and at least one nuclear reaction occurs, one of the products of the nuclear reaction being the stable isotope described above.

In the examples of the present application, the starting material may be determined according to the stable isotope to be produced. In some embodiments, determining the starting material based on the stable isotope to be produced may include: the raw material is determined according to the kind of stable isotope to be produced, the kind of particles provided by the irradiation apparatus, the particle energy, and the nuclear reaction capable of generating the stable isotope.

In the embodiment of the present application, the irradiation device may be a reactor or an accelerator. The raw materials can be made into a solid target piece which is placed in an irradiation device for irradiation; or the raw material is placed in a gas target of an irradiation device for irradiation.

It will be readily understood by those skilled in the art that the reactors referred to herein may be research pilot reactors, fast reactors, fusion reactors, etc., and the accelerators may be linear accelerators, cyclotrons, synchrotrons, etc. The preparation of stable isotopes using accelerators or reactors can be determined by the type and energy of the particles and the nuclear reactions that occur to form stable isotope products.

In some embodiments, the method may further comprise, prior to the irradiating step, a feedstock determination step: and determining the type of the raw material according to the type of the stable isotope.

Fig. 1 is a flow diagram of a method of producing a stable isotope according to one embodiment of the present invention. Referring to fig. 1, a method of producing a stable isotope according to some embodiments of the present application may include:

raw material determination step S1: and determining the type of the raw material according to the type of the stable isotope. Specifically, the raw material determining step S1 may include determining the raw material according to the kind of the stable isotope, the kind of the particle provided by the irradiation apparatus, the particle energy, and the nuclear reaction that can generate the stable isotope.

Irradiation step S3: and placing raw materials for producing stable isotopes in an irradiation device for irradiation so as to form the stable isotopes.

To produce stable isotopes⁶For example, Li is simply explained as the raw material determining step S1. Determining production⁶Li as a raw material, can be first found and⁶li-adjacent nuclides, e.g. finding a ratio⁶Li 1-2 more protons, and further confirmed that these species can be generated⁶Nuclear reaction of Li; according to the nuclear reaction excitation function, and by combining the particle types and particle energies provided by the existing irradiation device, the nuclear reaction which can be realized by the existing irradiation device is determined, and finally, the raw material is further determined according to the nuclear reaction.

Alternatively, if a suitable material cannot be found through the above process, for example, the irradiation apparatus cannot satisfy the nuclear reaction conditions, it is possible to find a material capable of performing the nuclear reactionIs reacted to generate⁶All nuclear reactions of Li are determined among the nuclear reactions that can occur in the irradiation apparatus according to the irradiation conditions (e.g., the kind of particles, the energy of particles) that can be provided by the irradiation apparatus, and further, the raw materials required for the nuclear reactions to occur are determined.

For the⁶In the case of Li, the nuclear reaction for which the irradiation apparatus can satisfy the reaction conditions is finally determined to beThereby determining the raw materials as⁹Be。

After the raw material of the nuclear reaction is determined, the particle energy during irradiation may be determined according to a plurality of nuclear reactions of the raw material occurring under different particle energy conditions and a nuclear reaction cross section of each of the nuclear reactions.

Referring to fig. 1, in some embodiments of the present application, after the feedstock determining step S1 and before the irradiating step S3, the method further comprises:

irradiation condition determination step S2: and determining the particle energy in the irradiation process according to a plurality of nuclear reactions of the raw material under different particle energy conditions and the nuclear reaction cross section of each nuclear reaction.

FIGS. 2-12 illustrate accelerator or reactor production, respectively⁶Li、⁷Li、¹⁰B、¹³C、¹⁶O、¹⁸O、²²Ne、²⁸Si、⁸⁷Rb、¹⁸⁴Nuclear reaction excitation function of W. According to the nuclear reaction excitation function, the nuclear reaction and the nuclear reaction cross section thereof which can occur when different particle energies are determined, so that the particle energy in the irradiation process can be determined to reduce the generation of impurities in the stable isotope product.

To produce stable isotopes⁶The irradiation condition determination step S2 is briefly explained by taking Li as an example.

As shown in figure 2, the reactor irradiation is carried out within the neutron energy range of 0-20 MeV⁹The nuclear reaction of Be can occur as⁹Be(n，2n)⁸Be、⁹Be(n，γ)¹⁰Be、⁹Be(n,p)⁹Li、⁹Be(n,d)⁸Li、⁹Be(n,T)⁷Li、⁹Be(n,α)⁶He、If the neutron energy is 20MeV, the nuclear reaction can occur to obtain⁶Li products contain⁷Li、⁸Li、⁹Isotopes such as Li are reduced⁶Abundance of Li products. And the neutron energy is 3MeV, nuclear reactionHas the largest nuclear reaction section and only has side reaction⁹Be(n,2n)⁸Be and⁹Be(n,γ)¹⁰be generation with by-product generation⁸Be and¹⁰be, other isotope that does not produce Li, can obtain 100% abundance⁶A Li isotope product.

In some embodiments of the present application, theoretical calculation and analysis of the yield of stable isotope products may be performed according to the nuclear reaction excitation function, and the irradiation conditions of stable isotope products may be determined according to the relationship between the yield and the variation of the particle fluence rate and irradiation time.

With continued reference to fig. 1, in some embodiments of the present application, after the irradiating step S3, the method further comprises:

separation step S4: separating the stable isotope from the irradiated mixture comprising the starting material and the stable isotope. I.e. the stable isotope product is separated from the mixture formed in the target after irradiation.

It will be readily appreciated by those skilled in the art that in some embodiments, the starting material will all form stable isotopes upon irradiation, and in such embodiments, the method does not require a separation step S4 after irradiation step S3. While in some embodiments the starting material is irradiated to form other by-products and/or to present residual starting material in addition to the desired stable isotope (i.e., stable isotope product), in such embodiments the method requires a separation step S4 after irradiation step S3.

In some embodiments, in the separation step S4, a method of separating the stable isotope from the mixture may be determined according to physical states of the raw material and the stable isotope. Those skilled in the art will readily appreciate that the physical state herein is either solid, gaseous or liquid.

In some embodiments, when the starting material and the stable isotope are both in the solid state, the separating step S4 includes: dissolving the mixture (i.e., the mixture formed within the target after irradiation) in an acid or base solution to form a solution; and separating the stable isotope from the solution.

In some embodiments, the separating the stable isotope from the solution comprises: separating the stable isotope from the solution using at least one of precipitation, ion exchange and extraction chromatography.

Specifically, for the ion exchange method, if the stable isotope product exists in a solution in a cation form, cation exchange resin or inorganic ion exchanger can be selected to separate the stable isotope; if the product is present in solution in the form of anions, anion exchange resins or inorganic ion exchangers can be selected for separating the stable isotopes. When the separation is carried out by using the exchange resin or the exchanger, the separation condition is determined by the static adsorption coefficient of the exchange resin or the exchanger to the product ions in the solution in different media.

For extraction chromatography, solvent extraction or extraction chromatography can be selected for separation according to the ionic form of the stable isotope product in the solution and the complex stability constant of the organic compound. In such a separation mode, the separation conditions are determined by the distribution ratio and separation coefficient of the extractant to the product ions in different aqueous phases or the distribution coefficient of the extraction chromatographic packing to the product ions in different media.

In some embodiments, when one of the starting material and the stable isotope is in a gaseous state and the other is in a solid state, the separating step S4 includes: separating the stable isotope directly from the starting material. For example, when the starting material is in a solid state and the stable isotope is in a gaseous state, and no other gaseous by-products are present, the gaseous stable isotope can be directly collected. Alternatively, when the raw material is in a gaseous state and the stable isotope is in a solid state, the solid substance may be directly separated from the raw material, and then the stable isotope product may be directly collected or further separated from the solid substance.

In some embodiments, when the starting material and the stable isotope are both in the gaseous state, the separating step S4 includes: separating the stable isotope from the mixture using a gas separation process. For example, different gases having different boiling points may be used to separate the gases, etc. Gas separation methods are well known to those skilled in the art and will not be described herein.

As mentioned above, the irradiation of the raw material inside the irradiation device may be achieved using a gas target or a solid target. In some embodiments, the target form of the feedstock irradiated within the irradiation device may be determined based on the stable isotope separation method. Target formats are divided into solid targets and gas targets.

For example, in irradiation with reactors²³Na production²²Ne in the embodiment, the target material may be²³Na is put into a target cylinder to prepare a solid target, or the target can be put into a target cylinder²³Placing Na in irradiation bottle (i.e. gas target) which can be extracted on-line during irradiation²²Ne products. If necessary, on-line extraction²²Ne product, and a gas target can be selected. If necessary, firstly²²Ne is separated from the target material and extracted, and then a solid target material can be selected.

In some embodiments, when the target is in the form of a solid target, the method further comprises, after the feedstock determining step S1 and before the irradiating step S3:

preparing a target: forming the feedstock into a solid target;

the irradiating step S3 further includes: and placing the solid target piece inside the irradiation device for irradiation.

The method of making solid targets is different for reactors and accelerators.

In particular, in some embodiments, when the irradiation device is a reactor, the solid target generally comprises a target cylinder and a target core (i.e., a target material). The target preparation step comprises: providing a target cylinder; and placing the raw material serving as a target material into the target cylinder to prepare the solid target piece. When the starting material is in a solid state, the target preparation step further comprises: and curing and molding the raw materials, and then placing the raw materials into the target cylinder to prepare the solid target piece. The solid raw material can be solidified and molded by using a simple substance or a compound form thereof through tabletting or tabletting sintering and the like. When the starting material is in a gaseous state, the target preparation step further comprises: and filling the raw materials into the target cylinder, and sealing the target cylinder to obtain the solid target.

In other embodiments, when the irradiation device is an accelerator, the solid target generally comprises a target holder and a target material. The target preparation step comprises: providing a target holder; bonding the feedstock to the backing plate to form the solid target. Copper with good heat conductivity is usually used as a target holder, and the target holder are combined together by sintering, electromagnetic sputtering, vacuum plating or electroplating and the like to prepare a target piece.

Those skilled in the art will appreciate that the solid targets of the reactor and accelerator are of different forms, and that for reactors, the solid targets may be used for solid feed materials as well as for gaseous feed materials; whereas for accelerators, solid targets can only be used for solid raw materials.

In some embodiments, when the target is in the form of a gas target, the irradiating step further comprises: placing the feedstock inside a gas target of the irradiation device.

For gaseous feed materials, the gaseous feed material may be charged into the gas target. For solid feedstock, it may be placed directly within a gas target. For a reactor, the gas target is an irradiation bottle; whereas for accelerators, the gas target is a gas target system.

It is readily understood by those skilled in the art that the methods of the present application are applicable to the production of all stable isotopes. To produce stable isotopes⁶Li、⁷Li、¹⁰B、¹³C、¹⁶O、¹⁸O、²²Ne、²⁸Si、⁸⁷Rb、¹⁸⁴W is an example, describing the method of the present application.

1. Determination of raw materials

Determination of production of stable isotopes in the manner described above⁶Li、⁷Li、¹⁰B、¹³C、¹⁶O、¹⁸O、²²Ne、²⁸Si、⁸⁷Rb、¹⁸⁴The target materials of W are respectively⁹Be、⁹Be、⁹Be、¹⁶O、¹⁹F、¹⁹F、²³Na、²⁷Al or³¹P (hereinafter with³¹P is an example),⁸⁶Kr or⁸⁷Sr (hereinafter expressed in⁸⁷Sr is as an example),¹⁸⁵Re。

2. Making targets

Will be provided with⁹Be、³¹P、⁸⁷Sr、¹⁸⁵The solid target material such as Re is made into a solid target piece through powder tabletting sintering, electromagnetic sputtering, vacuum plating or electroplating and the like; will be provided with²³Na、¹⁶O、¹⁹F, and the like, placing the target materials in an irradiation bottle to prepare a gas target.

3. Determination of irradiation conditions

In the foregoing manner, the particle energy during irradiation is determined from the nuclear reaction excitation function.

Table 1 shows the irradiation apparatus, the particle species and the particle energy for different stable isotopes determined from the nuclear reaction excitation function after the raw material is determined.

TABLE 1 irradiation apparatus, particle types and particle energies for different stable isotopes

3. Irradiation of target

The target is placed in an accelerator or a reactor for irradiation.

4. Separating and purifying

For the⁹Be、³¹P、⁸⁷Sr、¹⁸⁵Dissolving the mixture in solid target such as Re with acid solution or alkali solution after irradiation, and separating by precipitation, ion exchange, or extraction chromatography⁶Li、⁷Li、¹⁰B、²⁸Si、⁸⁷Rb、¹⁸⁴Separating and purifying stable isotope products such as W and the like from the target; for the²³Na gas target, after irradiation gas transfer, can be directly obtained²²A Ne product; for the¹⁶O gas target, transferring gas after irradiation, and treating with alkali solution¹³C, extracting; to for¹⁹F gas target, after irradiation gas transfer, if H₂ ¹⁶O、H₂ ¹⁸The product form of O is extracted, and then the product form can be directly separated by using a gas separation method¹⁶O、¹⁸O is extracted to obtain H₂ ¹⁶O、H₂ ¹⁸O products; if with C¹⁶O₂、C¹⁸O₂The product form can be extracted with alkali solution¹⁶O、¹⁸And (4) extracting the O.

Production of stable isotopes⁶Li、⁷Li、¹⁰B、¹³C、¹⁶O、¹⁸O、²²Ne、²⁸Si、⁸⁷Rb、¹⁸⁴Details of the operation of W are given in examples 1-10. The irradiation conditions of the examples can be seen in table 1.

Example 1

Prepared by powder tabletting and sintering⁹Be target, after being irradiated in reactor, is dissolved in hydrochloric acid. The dissolved solution contains Li, Be and other elements, and is extracted and separated by 80% tributyl phosphate-kerosene⁹After Be, the raffinate was passed through a Dowex50w X1 cation exchange resin column and eluted with nitric acid⁶Li, to obtain⁶And (3) Li products.

Example 2

Is prepared by metal inlaying or powder tabletting and sintering⁹Be target is put in accelerator or reactor respectively and dissolved by hydrochloric acid. The solution contains Li, Be and other elements, and 80% tributyl phosphate-coalOil extraction separation⁹After Be, the raffinate was passed through a Dowex50w X1 cation exchange resin column and eluted with nitric acid⁷Li, to obtain⁷And (3) Li products.

Example 3

Made by damascene⁹Be target, after being irradiated by accelerator, is dissolved by nitric acid. The solution contains Li, Be, B, etc., and is eluted with NaOH after passing through AG1-X8 anion exchange resin chromatographic column¹⁰B, obtaining¹⁰And B, product.

Example 4

Mixing natural oxygen (natural oxygen is oxygen existing in nature, and the content is 99.757%¹⁶O、0.038％¹⁷O、0.205％¹⁸O) is filled into an irradiation bottle, after being placed in a reactor for irradiation,¹⁶o generation¹³C，¹³After C is separated from oxygen, the¹³Oxidation of C to form¹³CO₂And carried into a 2.5mol/LNaOH absorption cell, to which saturated Ba (OH) is added₂Formation of Ba from the solution¹³CO₃Precipitating, filtering, washing and drying to obtain Ba¹³CO₃And (5) producing the product.

Example 5

Filling natural fluorine (natural abundance of 100%) into an irradiation bottle, and irradiating in a reactor to obtain the final product¹⁶O，¹⁶After separation of O from natural fluorine, separating¹⁶Oxidation of O to H in a hydrogen atmosphere₂ ¹⁶O to obtain H₂ ¹⁶And (4) O products.

Example 6

Filling natural fluorine into an irradiation bottle, and placing the irradiation bottle in a reactor for irradiation to form¹⁸O，¹⁸After separation of O from natural fluorine, separating¹⁸Oxidation of O to H in a hydrogen atmosphere₂ ¹⁸O to obtain H₂ ¹⁸And (4) O products.

Example 7

Will be prepared by powder tabletting and sintering²³Placing the Na target in an irradiation bottle, placing the irradiation bottle in a reactor for irradiation, and transferring the gas in the irradiation bottle to a storage bottle to obtain the Na target²²Ne products.

Example 8

Will be prepared by powder tabletting and sintering³¹And P target pieces are placed in a reactor for irradiation, and then the target pieces are dissolved by sodium hydroxide. The dissolved solution contains P, Si, S and other elements, and is eluted with nitric acid and ethanol after passing through cellulose ion exchange column²⁸Si to obtain²⁸And (4) Si product.

Example 9

Prepared by powder tabletting and sintering⁸⁷The Sr target piece is placed in a reactor for irradiation, and hydrochloric acid is used for dissolving the target piece. The dissolved solution contains Sr, Rb, etc., and is eluted with ammonium nitrate after passing through zirconium phosphate inorganic ion exchange column⁸⁷Rb, to obtain⁸⁷Rb products.

Example 10

Prepared by powder tabletting and sintering¹⁸⁵And the Re target is placed in a reactor for irradiation, and then hydrofluoric acid and nitric acid are used for dissolving the target. The dissolved solution contains elements such as Re, W, Ta, Os, etc., and is eluted with 20% HF-30% hydrochloric acid mixture after passing through Dowex1x8 anion exchange resin chromatographic column¹⁸⁴W, can obtain¹⁸⁴And (5) preparing a W product.

Production by means of examples 1 to 10⁶Li、⁷Li、¹⁰B、¹³C、¹⁶O、¹⁸O、²²Ne、²⁸Si、⁸⁷Rb、¹⁸⁴The productivity and abundance of stable isotope products such as W are shown in FIGS. 13 to 25.

As can be seen from the view in figure 13,⁹the natural abundance of Be is 100%, the neutron energy of the reactor is 3MeV, and the neutron fluence rate is 10¹⁷n·cm^-2·s^-11 ton of⁹The Be target material is irradiated for 1 day and cooled for 1 day to generate 0.6033kg⁶Li; due to the fact that⁹Be only subjected to nuclear reaction during irradiationProduction of⁶Li without other Li isotopes, thus obtaining an abundance of 100%⁶365 batches of Li isotope products are produced every year,⁶The annual Li production capacity is 220.2 kg.

As can be seen from FIG. 14, the reactor has a neutron energy of 14MeV and a neutron fluence rate of 10¹⁷n·cm^-2·s^-11 ton of⁹The Be target material is irradiated for 1 day and cooled for 1 day to generate 0.1358kg⁷Li; irradiation with 14MeV fast neutrons⁹Be target production⁷Li, with side reactionsGenerating⁶Li, will decrease⁷The abundance of Li products is 65.86 percent⁷365 batches of Li isotope products are produced every year,⁷The annual capacity of Li is 49.57 kg. As can be seen from FIG. 15, the T-beam current intensity is 1 ton at 1000 μ A⁹The Be target material is irradiated for 1 day and cooled for 1 day to generate 0.002872kg⁷Li; irradiation with accelerators⁹Be target production⁷Nuclear reaction of Li only⁹Be(T,αn)⁷Li production⁷Li, without generating other Li isotopes, can be obtained in an abundance of 100%⁷365 batches of Li isotope products are produced every year,⁷The annual Li production capacity is 1.048 kg.

As can be seen from FIG. 16, the beam current intensity of the d-nuclear beam is 1 ton at 1000 μ A⁹The Be target material is irradiated for 1 day and cooled for 1 day to generate 0.01148kg¹⁰B; accelerating d-nucleus bombardment by using accelerator⁹Be production¹⁰B, side reactions take place simultaneously⁹Be(d,γ)¹¹B, the abundance can be obtained to be 99.99 percent¹⁰B isotope product, 365 batches of,¹⁰The yield in B year is 4.190 kg.

As can be seen from FIG. 17, the reactor has a neutron energy of 4.6MeV and a neutron fluence rate of 10¹⁷n·cm^-2·s^-11 ton of¹⁶The O target material is irradiated for 1 day and cooled for 1 day to generate 4.363kg¹³C; irradiation of radiation¹⁶O-target production¹³In the C process, no other C isotope is produced, and the abundance of the obtained C isotope is 100 percent¹³A C isotope product; if natural O is used as the target material, in the 4.6MeV neutron irradiation process,¹⁷O、¹⁸o does not produce C isotope, and the abundance of O is 100 percent¹³365 batches of C isotope products are produced every year,¹³The yield of the rice in C year is 1592 kg.

As can be seen from FIG. 18, the reactor has a neutron energy of 5.7MeV and a neutron fluence rate of 10¹⁷n·cm^-2·s^-11 ton of¹⁹F, the target material is irradiated for 1 day and cooled for 1 day to generate 1.526kg¹⁶O; irradiation of radiation¹⁹F target production¹⁶In the O process, side reactions occur Generating¹⁹O, but¹⁹The half-life of O is only 26.91s, and the abundance of O is 100 percent after the irradiation is finished and the cooling is carried out for 1 day¹⁶365 batches of O isotope products are produced every year,¹⁶The O-year capacity is 557 kg.

As can be seen from FIG. 19, the reactor has a neutron energy of 14MeV and a neutron fluence rate of 10¹⁷n·cm^-2·s^-11 ton of¹⁹F target material is irradiated for 1 day and cooled for 1 day to generate 1.009kg¹⁸O; fast neutron irradiation¹⁹F target production¹⁸O, side reaction occurs Andthe abundance ratio of 74.91 percent can be obtained¹⁸365 batches of O isotope products are produced every year,¹⁸The O-year capacity is 368.3 kg.

As can be seen from FIG. 20, the reactor has a neutron energy of 14MeV and a neutron fluence rate of 10¹⁷n·cm^-2·s^-11 ton of²³The Na target material is irradiated for 1 day and cooled for 1 day to generate 2.982kg²²Ne; irradiation with 14MeV fast neutrons²³Na target production²²Ne, side reaction occurs ²³Na(n,T)²¹Ne andthe abundance ratio of 72.32 percent can be obtained²²Ne isotope product, 365 batches of Ne isotope product are produced every year,²²The Ne annual capacity is 1089 kg.

As can be seen from FIG. 21, the reactor has a neutron energy of 6.5MeV and a neutron fluence rate of 10¹⁷n·cm^-2·s^-11 ton of³¹The P target material is irradiated for 30 days and cooled for 1 day to generate 10.57kg²⁸Si; irradiation of radiation³¹P target production²⁸Si can generate side reactionAnd³¹P(n,d)³⁰generation of Si separately³¹Si and³⁰si, but the side reaction section is very low, and the abundance ratio of the obtained Si is 99.76 percent²⁸The Si isotope product is produced in 12 batches each year,²⁸The annual Si production capacity is 126.8 kg. As can be seen from FIG. 22, the reactor thermal neutron fluence rate is 10¹⁵n·cm^-2·s^-11 ton of²⁷The Al target material is irradiated for 365 days and cooled for 1 day to generate 7.056kg²⁸Si,; using reactor thermal neutron irradiation²⁷Al target production²⁸In the case of Si, since no other nuclear reaction occurs, an abundance of 100% can be obtained²⁸1 batch of Si isotope product is produced every year,²⁸The annual Si yield is 7.056 kg.

As can be seen from FIG. 23, the reactor thermal neutron fluence rate is 10¹⁵n·cm^-2·s^-11 ton of⁸⁶The irradiation of the Kr target material for 365 days and the cooling for 1 day only generate 0.04713kg⁸⁷Rb; using reactor thermal neutron irradiation⁸⁶Kr target production⁸⁷No other nuclear reaction occurs in the Rb process, and the obtained abundance is 100 percent⁸⁷1 batch per year of Rb isotope product,⁸⁷The annual capacity of Rb is 0.04713 kg. As can be seen from FIG. 24, the reactor has a neutron energy of 7MeV and a neutron fluence rate of 10¹⁷n·cm^-2·s^-11 ton of⁸⁷Sr targetThe material is irradiated for 365 days and cooled for 1 day to generate 18.91kg⁸⁷Rb; and irradiating by using 7MeV fast neutrons⁸⁷Sr can not generate other isotopes of Rb, and the abundance of Sr is 100 percent⁸⁷1 batch per year of Rb isotope product,⁸⁷The annual capacity of Rb is 18.91 kg.

As can be seen from FIG. 25, the reactor has a neutron energy of 10MeV and a neutron fluence rate of 10¹⁷n·cm^-2·s^-11 ton of¹⁸⁵The Re target material is irradiated for 7 days and cooled for 180 days to generate 73.52kg¹⁸⁴W; irradiation of radiation¹⁸⁵Production of Re targets¹⁸⁴W can generate side reaction¹⁸⁵Re(n,p)¹⁸⁵W and¹⁸⁵Re(n,T)¹⁸³w is generated separately¹⁸⁵W and¹⁸³w, low side reaction section and 98.06% abundance¹⁸⁴50 batches of W isotope product is produced every year,¹⁸⁴The annual capacity of W is 3676 kg.

It follows that production by means of reactors or accelerators⁶Li、⁷Li、¹⁰B、¹³C、¹⁶O、¹⁸O、²²Ne、²⁸Si、⁸⁷Rb、¹⁸⁴Stable isotopes such as W and the like can obtain high-abundance stable isotope products, and the large-scale production is easy to realize. In addition, the target material can be recovered and then manufactured into a target piece to be irradiated continuously to produce stable isotope products, so that the production cost of the stable isotope is reduced, and the method has extremely high economic value.

And, produced by accelerators or reactors⁶Li、⁷Li、¹⁰B、¹³C、¹⁶O、¹⁸O、²²Ne、²⁸Si、⁸⁷Rb、¹⁸⁴The impurity elements generated in the stable isotope processes such as W and the like are B, B, Li, impurity-free elements, Ne, F/Mg, S/impurity-free elements, impurity-free elements/Kr and Ta/Os respectively, even if the impurity elements are generated, the impurity elements are not the same as the product, and the impurity elements have few types, thereby being convenient for the separation and purification of the product and being easy to obtain the stable isotope product.

In addition, 14MeV neutrons of fusion reactor or 14MeV neutrons can be utilized for moderating, and can be simultaneously irradiated for production⁶Li、⁷Li、¹³C、¹⁶O、¹⁸O、²²Ne、²⁸Si、⁸⁷Rb、¹⁸⁴Stable isotope of W, etc. produced by irradiating 1 ton target material for 1 day⁶Li、⁷Li、¹³C、¹⁶O、¹⁸O、²²Ne、²⁸Si、⁸⁷Rb、¹⁸⁴The production capacity of stable isotopes such as W and the like is 0.06033kg, 0.1358kg, 4.363kg, 1,526kg, 1.009kg, 2.983kg, 0.3725kg, 0.05283kg and 1.087kg respectively, and the abundance of the product is 100%, 65.86%, 100%, 74.91%, 72.32%, 99.68%, 100% and 99.95% respectively.

Therefore, compared with the method for producing stable isotopes in the prior art, the method for producing stable isotopes by using the nuclear reaction has the advantages of convenience in separation, no need of cascade connection, low energy consumption and easiness in obtaining high-abundance stable isotope products in a short time.

It should also be noted that, in the case of the embodiments of the present invention, features of the embodiments and examples may be combined with each other to obtain a new embodiment without conflict.

The above description is only an embodiment of the present invention, but the scope of the present invention is not limited thereto, and the scope of the present invention is subject to the scope of the claims.