CN113512653A - Method for extracting plutonium-238 from irradiated neptunium target - Google Patents

Method for extracting plutonium-238 from irradiated neptunium target Download PDF

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CN113512653A
CN113512653A CN202110667946.3A CN202110667946A CN113512653A CN 113512653 A CN113512653 A CN 113512653A CN 202110667946 A CN202110667946 A CN 202110667946A CN 113512653 A CN113512653 A CN 113512653A
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蒋德祥
何辉
李峰峰
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China Institute of Atomic of Energy
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    • C—CHEMISTRY; METALLURGY
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    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
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    • C22B60/04—Obtaining plutonium
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Abstract

The present disclosure relates to a method for extracting plutonium-238 from an irradiated neptunium target, using an organic solvent containing triisopentyl phosphate as an extractant to extract plutonium-238 from a dissolution solution of the irradiated neptunium target. The method disclosed by the invention adopts an organic solvent containing triisopentyl phosphate with strong irradiation resistance as an extracting agent, and extracts plutonium from a dissolving liquid of an irradiation neptunium target according to different extraction behaviors of the neptunium and the plutonium with different valence states, so that the separation of the plutonium from the neptunium and a split sheet is realized, and the purpose of purifying the plutonium is further achieved.

Description

Method for extracting plutonium-238 from irradiated neptunium target
Technical Field
The application relates to the field of extraction and purification of nuclear materials, in particular to a method for extracting plutonium-238 from an irradiated neptunium target.
Background
238Pu is a non-fission alpha emitter with a half-life of 87.7 years, the specific power of the Pu is as high as 0.5W/g, only gamma radiation with extremely weak energy is emitted, a thicker protective layer is not needed, and the Pu-Er-La-doped carbon nano tube is suitable for preparing a long-life miniature power supply. To be provided with238Isotope batteries (RTGs) prepared from Pu play an important role in aerospace industry and medical and health industry. Thus, it is possible to provide238Pu production is gaining importance. At present, the number of the current day,238pu is produced mainly by preparation237Np target and the Np target are obtained after neutron irradiation in a reactorAnd (5) obtaining the product.
The neptunium target is composed of237Np is formed in aluminum powder as dispersoid, and aluminum metal is used as outer shell. Fraction of neptunium target after suitable neutron irradiation in the reactor237Np generation238Pu. After the neptunium target is dissolved by nitric acid, the dissolving liquid contains neptunium, plutonium, nitrate radical and a small amount of lobe element ions. Solvent extraction has also been applied to238In Pu extraction technology, common extraction method is used for extracting irradiated neptunium targets238Pu, such as tertiary amine extraction scheme and TBP extraction scheme. The extraction agent commonly used in the tertiary amine extraction process is TLA (trilaurylamine), the process is characterized by using three different diluents, namely solgil 100 (mainly hexylbenzene), a mixture of decalin and dodecane and an octanol-dodecane mixture, and the process has the advantage that HNO (hydrogen sulfide) is required to be added during the separation of Np-Pu (N-methyl pyrrolidone)3-H2SO4Reducing the Np-Pu in the solution to limit238Loss of Pu. While238Specific activity of Pu 6.34X 1011Bq/g of about239280 times Pu. As can be seen from the above analysis, the TLA process has multiple extraction systems and introduces H2SO4Increasing the corrosion to the equipment and simultaneously having poor irradiation resistance. In the TBP extraction process, TBP is easy to be radiated and decomposed under strong radiation to generate radiolysis products, so that interface dirt is easy to form, and the extraction process is influenced.
Therefore, there is a need in the art to find a new method for extracting neptunium from irradiated neptunium target238Pu's method in order to obtain high purity238Pu simultaneously, the negative influence in the extraction process is reduced to the maximum extent.
Disclosure of Invention
The object of the present disclosure is a method for extracting plutonium-238 from an irradiated neptunium target, in order to obtain a plutonium-238 of high purity while further reducing the production of radiolysis products.
In order to achieve the above object, the present disclosure provides a method of extracting plutonium-238 from an irradiated neptunium target, which method extracts plutonium-238 from the irradiated neptunium target dissolution liquid using an organic solvent containing triisopentyl phosphate as an extractant.
Optionally, the concentration of the phosphate isopentyl ester in the extractant is 0.15-2 mol/L; preferably 0.8 to 1.5 mol/L.
Optionally, the extractant further comprises a diluent selected from at least one of kerosene, n-dodecane, methylbenzene and benzene; preferably, the diluent is selected from kerosene or n-dodecane.
Optionally, the method comprises the steps of:
s1, dissolving the irradiated neptunium target to obtain a first feed liquid; performing first extraction on the first feed liquid by using the extractant to obtain a first water phase containing plutonium-238;
s2, adjusting the valence state of the plutonium-238 in the first aqueous phase to obtain a second feed liquid; performing second extraction on the second feed liquid by using the extracting agent to obtain a first organic phase; carrying out first back extraction on the first organic phase to obtain a second aqueous phase;
s3, adjusting the valence state of the plutonium-238 in the second aqueous phase to obtain a third feed liquid; performing third extraction on the third feed liquid by using the extracting agent to obtain a second organic phase; and carrying out second back extraction on the second organic phase to obtain a third aqueous phase.
Optionally, in step S1, the valence state of neptunium-237 in the first feed liquid is one of tetravalent, pentavalent and hexavalent, and the valence state of plutonium-238 is one of trivalent, tetravalent and hexavalent; in step S2, the valence state of plutonium-238 in the second feed liquid is trivalent or tetravalent, preferably tetravalent; in step S3, the valence of plutonium-238 in the third feed liquid is trivalent or tetravalent, preferably tetravalent.
Optionally, in step S1, the first feed liquid is an acidic solution of neptunium plutonium; preferably neptunium plutonium in nitric acid.
Optionally, the concentration of plutonium-238 in said third aqueous phase is not lower than 5g/L and the concentration of neptunium-237 is not higher than 10-3g/L。
Optionally, in step S1, the conditions of the first extraction include: extracting and washing by using nitric acid, wherein the number of extraction stages is not less than 6; wherein the concentration of the nitric acid in the extraction process is 1-4mol/L, and the concentration of the nitric acid in the washing process is 1-4 mol/L; in step S2, the conditions of the second extraction include: extracting and washing by using nitric acid, wherein the number of extraction stages is not less than 5; wherein the concentration of the nitric acid in the extraction process is 1-5mol/L, and the concentration of the nitric acid in the washing process is 1-5 mol/L; in step S3, the conditions of the third extraction include: extracting and washing by using nitric acid, wherein the number of extraction stages is not less than 5; wherein the concentration of the nitric acid in the extraction process is 1-5mol/L, and the concentration of the nitric acid in the washing process is 1-5 mol/L.
Optionally, in step S2, the conditions of the first stripping include: the back extraction stage number is not lower than 5 stages, the concentration of nitric acid is 0.3-2mol/L, and the used back extractant is selected from at least one of ferrous sulfamate, hydroxylamine and dimethylhydroxylamine; in step S3, the conditions of the second stripping include: the back extraction stage number is not less than 5 stages, the concentration of nitric acid is 0.3-2mol/L, and the used back extraction agent is at least one of ferrous sulfamate, hydroxylamine and dimethylhydroxylamine.
Alternatively, in step S1, the irradiated neptunium target is dissolved using mercury catalytic dissolution techniques and catalytic indirect electrochemical techniques.
By the technical scheme, the method adopts the organic solvent containing the triisopentyl phosphate with strong irradiation resistance as the extracting agent, extracts the plutonium from the solution irradiating the neptunium target according to different extraction behaviors of the neptunium plutonium with different valence states, realizes the separation of the plutonium from the neptunium and a split sheet, and further achieves the purpose of purifying the plutonium.
Additional features and advantages of the disclosure will be set forth in the detailed description which follows.
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The accompanying drawings, which are included to provide a further understanding of the disclosure and are incorporated in and constitute a part of this specification, illustrate embodiments of the disclosure and together with the description serve to explain the disclosure without limiting the disclosure. In the drawings:
fig. 1 is a flow chart of a specific embodiment of the present disclosure.
Detailed Description
The following describes in detail specific embodiments of the present disclosure. It should be understood that the detailed description and specific examples, while indicating the present disclosure, are given by way of illustration and explanation only, not limitation.
The present disclosure provides a method for extracting plutonium-238 from an irradiated neptunium target using an organic solvent containing triisopentyl phosphate as an extractant to extract plutonium-238 from the irradiated neptunium target dissolution liquor.
According to the method, only an organic solvent containing triisopentyl phosphate with strong irradiation resistance is used as an extracting agent in the whole process, and plutonium is extracted from a dissolving solution irradiating a neptunium target according to different extraction behaviors of the neptunium plutonium with different valence states, so that the separation of the plutonium from the neptunium and a split sheet is realized, and the purpose of purifying the plutonium is further achieved.
According to the present disclosure, the concentration of tri-isoamyl phosphate in the extractant can be 0.15-2 mol/L; through a large number of experiments, the inventor finds that when the concentration of the tri-isoamyl phosphate in the extractant is 0.80-1.5mol/L, the extractant has the best extraction capability on plutonium in the irradiated neptunium target dissolving solution.
According to the present disclosure, the extractant may further include a diluent, which may be selected from at least one of kerosene, n-dodecane, methylbenzene, and benzene; preferably, the diluent is selected from kerosene or n-dodecane.
As a specific embodiment of the present disclosure, the method of the present disclosure includes the steps of:
s1, dissolving the irradiated neptunium target to obtain a first feed liquid; performing first extraction on the first feed liquid by using the extractant to obtain a first water phase containing plutonium-238;
s2, adjusting the valence state of the plutonium-238 in the first aqueous phase to obtain a second feed liquid; performing second extraction on the second feed liquid by using the extracting agent to obtain a first organic phase; carrying out first back extraction on the first organic phase to obtain a second aqueous phase;
s3, adjusting the valence state of the plutonium-238 in the second aqueous phase to obtain a third feed liquid; performing third extraction on the third feed liquid by using the extracting agent to obtain a second organic phase; and carrying out second back extraction on the second organic phase to obtain a third aqueous phase.
According to the present disclosure, in step S1, the valence state of neptunium-237 in the first feed liquid may be one of tetravalent, pentavalent and hexavalent, and the valence state of plutonium-238 may be one of trivalent, tetravalent and hexavalent; any combination of valence states in which neptunium-237 and plutonium-238 may exist may be, for example, Np (iv) -Pu (iii), Np (iv) -Pu (iv), Np (v) -Pu (iv), Np (vi) -Pu (vi), etc. In the present disclosure, in order to further purify and concentrate the plutonium-238 in the solution, in step S2, the valence state of the plutonium-238 in the second feed liquid is preferably trivalent or tetravalent, and more preferably tetravalent; in step S3, the valence of plutonium-238 in the third feed liquid is preferably trivalent or tetravalent, and more preferably tetravalent.
According to the present disclosure, in step S1, the first feed liquid is a dissolving liquid including various light water reactors irradiating neptunium targets, various fast reactors irradiating neptunium targets, various experimental reactors irradiating neptunium targets, etc., or any acidic solution containing neptunium plutonium, such as a nitric acid solution of neptunium plutonium or any other acidic solution. The concentration of the acid in the first feed liquid of the present disclosure is not particularly limited, and may be adjusted according to actual conditions.
With the process of the present disclosure, in the third aqueous phase obtained, the plutonium-238 concentration is preferably not lower than 5g/L, and the neptunium-237 concentration is preferably not higher than 10-3And g/L, wherein the concentration of the plutonium-238 in the water phase meets the purity required for preparing the plutonium-238 isotope battery and the requirement for precipitating plutonium oxalate.
The method disclosed by the invention uses an organic solvent containing triisopentyl phosphate as an extractant, and utilizes the difference of distribution coefficients of the neptunium-237 and the plutonium-238 to retain the plutonium-238 in an aqueous phase to obtain a first aqueous phase containing the plutonium-238, and adjust the valence state of the plutonium-238 to be trivalent to obtain a second feed liquid; and (3) carrying out two cycles of extraction and back extraction on the second feed liquid, specifically, using an organic solvent containing triisopentyl phosphate as an extractant, extracting the plutonium-238 into an organic phase, retaining the splinter elements in a water phase, collecting the organic phase, carrying out reduction back extraction, and carrying out back extraction on the plutonium-238 in the organic phase into the water phase so as to realize the concentration and purification of the plutonium-238.
In the extraction processes and stripping processes of the present disclosure, nitric acid is preferably selected for acidity adjustment in order to reduce corrosion on the plant.
According to the present disclosure, in step S1, the conditions of the first extraction may include: extracting and washing by using nitric acid, wherein the number of extraction stages is not less than 6; wherein the concentration of the nitric acid in the extraction process is 1-4mol/L, and the concentration of the nitric acid in the washing process is 1-4 mol/L; in step S2, the conditions of the second extraction may include: extracting and washing by using nitric acid, wherein the number of extraction stages is not less than 5; wherein the concentration of the nitric acid in the extraction process is 1-5mol/L, and the concentration of the nitric acid in the washing process is 1-5 mol/L; in step S3, the conditions of the third extraction may include: extracting and washing by using nitric acid, wherein the number of extraction stages is not less than 5; wherein the concentration of the nitric acid in the extraction process is 1-5mol/L, and the concentration of the nitric acid in the washing process is 1-5 mol/L.
According to the present disclosure, in step S2, the conditions of the first stripping may include: the back extraction stage number is not lower than 5 stages, the concentration of nitric acid is 0.3-2mol/L, and the used back extractant is selected from at least one of ferrous sulfamate, hydroxylamine and dimethylhydroxylamine; in step S3, the conditions of the second stripping may include: the back extraction stage number is not less than 5 stages, the concentration of nitric acid is 0.3-2mol/L, and the used back extraction agent is at least one of ferrous sulfamate, hydroxylamine and dimethylhydroxylamine.
The specific steps for dissolving the irradiated neptunium target in the present disclosure may be well known to those skilled in the art, and may be, for example, dissolved using mercury catalyzed dissolution techniques and catalyzed indirect electrochemical techniques. Specifically, the mercury catalytic dissolution technology is adopted to dissolve the aluminum matrix in the irradiated neptunium target into an aluminum nitrate form, and the catalytic indirect electrochemical technology is adopted to dissolve the neptunium plutonium oxide into a neptunium plutonium solution.
The present disclosure is further illustrated by the following examples. The raw materials used in the examples are all available from commercial sources.
Example 1
Dissolving the irradiated neptunium target to obtain a first feed liquid; the first feed liquid is subjected to a first extraction with an extractant to obtain a first aqueous phase containing plutonium-238. Wherein, the concentration of Np (IV) in the first feed liquid is 5g/L, the concentration of Pu (III) is 1g/L, the concentration of nitric acid is 3mol/L, Al3+The concentration is 1.2 mol/L; the extractant is triisopentyl phosphate-kerosene solution, and the concentration of the triisopentyl phosphate is 1.09 mol/L. The conditions of the first extraction include: triisopentyl phosphate-kerosene is used for extraction, nitric acid-hydrazine is used for washing, and the number of extraction stages is 10; the concentration of nitric acid in the extraction process is 3mol/L, the concentration of nitric acid in the washing process is 3mol/L, and the concentration of hydrazine is 0.1 mol/L.
Adjusting the valence state of the plutonium-238 in the first aqueous phase to be tetravalent to obtain a second feed liquid; performing second extraction on the second feed liquid by using an extracting agent to obtain a first organic phase; the first organic phase is subjected to a first back-extraction to obtain a second aqueous phase. Wherein the conditions of the second extraction comprise: triisopentyl phosphate-kerosene is used for extraction, nitric acid is used for washing, and the number of extraction stages is 8; the concentration of nitric acid in the extraction process is 3.5mol/L, and the concentration of nitric acid in the washing process is 2 mol/L; the conditions of the first stripping include: the back extraction stage number is 8 stages, the concentration of nitric acid is 0.3mol/L, and the used back extractant is ferrous sulfamate.
Adjusting the valence state of the plutonium-238 in the second aqueous phase to be tetravalent, and adjusting the acidity of the solution to obtain a third feed liquid; performing third extraction on the third feed liquid by using an extracting agent to obtain a second organic phase; and carrying out second back extraction on the second organic phase to obtain a third aqueous phase and a third organic phase. Wherein the conditions of the third extraction comprise: triisopentyl phosphate-kerosene is used for extraction, nitric acid is used for washing, and the number of extraction stages is 8; the concentration of nitric acid in the extraction process is 2mol/L, and the concentration of nitric acid in the washing process is 3 mol/L; the conditions of the second stripping include: the back extraction stage number is 8 stages, the concentration of nitric acid is 0.3mol/L, and the used back extractant is ferrous sulfamate.
The concentration of nitric acid in the third aqueous phase is measured to be 1.4mol/L, the concentration of Pu is measured to be 8g/L, and the concentration of Np is measured to be 5.78 multiplied by 10-6g/L. A third organic phaseThe concentration of the medium nitric acid is 0.1mol/L, and the concentration of Pu is 7.99 multiplied by 10-4g/L, Np concentration of 5.78X 10-6g/L。
Example 2
This example was the same as example 1 except that plutonium-238 was extracted: the concentration of the tri-isoamyl phosphate in the extractant of this example was 1.5 mol/L.
The concentration of nitric acid in the third aqueous phase is measured to be 1.4mol/L, the concentration of Pu is measured to be 8g/L, and the concentration of Np is measured to be 3.54 multiplied by 10-6g/L. The concentration of nitric acid in the third organic phase is 0.11mol/L, and the concentration of Pu is 8.32 multiplied by 10-4g/L, Np concentration of 5.78X 10-6g/L。
Example 3
This example was the same as example 1 except that plutonium-238 was extracted: the concentration of the tri-isoamyl phosphate in the extractant of this example was 0.3 mol/L.
The concentration of nitric acid in the third aqueous phase was determined to be 0.6mol/L, the concentration of Pu (III) was determined to be 1.3g/L, and the concentration of Np was determined to be 0.3 g/L. The concentration of nitric acid in the third organic phase is 0.08mol/L, and the concentration of Pu is 6.40 multiplied by 10-5g/L, the Np concentration is 0.1 g/L.
Comparative example 1
This comparative example was the same as example 1, except that: the extractant of this comparative example was a TBP (tributyl phosphate) solution having a TBP concentration of 1.09 mol/L.
The concentration of nitric acid in the third aqueous phase is measured to be 1.4mol/L, the concentration of Pu is measured to be 6.81g/L, and the concentration of Np is measured to be 7.86 multiplied by 10- 4g/L. The concentration of nitric acid in the third organic phase is 0.1mol/L, and the concentration of Pu is 7.89 multiplied by 10-4g/L, Np concentration 9.51X 10-6g/L。
As can be seen from examples 1-3 and comparative example 1 of the present disclosure: comparing example 1 with comparative example 1, when the concentrations of the effective components in the extractant are the same, the Pu concentration in the third aqueous phase obtained by extraction with the extractant containing triisopentyl phosphate used in the present disclosure is significantly increased, and the Np concentration is significantly reduced, which is probably because the organic solvent containing triisopentyl phosphate with strong radiation resistance is used as the extractant, so that the generation of radiolysis products in the extraction process is reduced; comparing example 1 with examples 2 and 3, when the concentration of triisopentyl phosphate was 1.09mol/L and 1.5mol/L, the extractant containing triisopentyl phosphate showed more remarkable extraction ability of plutonium in the irradiated neptunium target dissolution liquid.
Example 4
After irradiation of triisopentyl phosphate-kerosene of 1.09mol/L with an irradiation dose of 60kGy, an experiment was carried out by the same process as in example 1, the operation of the experiment was normal, and the operation was normally stopped after 36 hours of the operation of the experiment.
Comparative example 2
After 1.09mol/L TBP-kerosene is irradiated by 60kGy irradiation dose, an experiment is carried out by the same process as in example 1, after the experiment is operated for 2 hours, interface dirt is obviously generated in a mixer-settler, after the experiment is operated for 6 hours, a channel of the previous stage of a feed liquid feeding stage is blocked, and the experiment is forced to be terminated.
As can be seen by comparing example 4 with comparative example 2: after triisopentyl phosphate-kerosene and TBP-kerosene with the same concentration were irradiated with the same irradiation dose, the experiment using triisopentyl phosphate-kerosene as an extractant was still able to run normally, while the experiment using TBP-kerosene as an extractant was forced to stop due to the generation of interfacial contamination during the process. It can thus be seen that the present disclosure uses an organic solvent containing triisopentyl phosphate as an extractant to significantly reduce radiolysis products generated during the extraction of plutonium-238 from irradiated neptunium target dissolution.
The preferred embodiments of the present disclosure have been described in detail above, however, the present disclosure is not limited to the specific details of the above embodiments, and various simple modifications may be made to the technical solution of the present disclosure within the technical idea of the present disclosure, and these simple modifications all fall within the protection scope of the present disclosure.
It should be noted that the various features described in the above embodiments may be combined in any suitable manner without departing from the scope of the invention. In order to avoid unnecessary repetition, various possible combinations will not be separately described in this disclosure.
In addition, any combination of various embodiments of the present disclosure may be made, and the same should be considered as the disclosure of the present disclosure, as long as it does not depart from the spirit of the present disclosure.

Claims (10)

1. A method for extracting plutonium-238 from an irradiated neptunium target, characterized in that it extracts plutonium-238 from a dissolution liquid of said irradiated neptunium target using an organic solvent containing triisopentyl phosphate as an extractant.
2. The method of claim 1, wherein the concentration of the tri-isoamyl phosphate in the extractant is 0.15 to 2 mol/L; preferably 0.80 to 1.5 mol/L.
3. The process of claim 1, wherein the extractant further comprises a diluent selected from at least one of kerosene, n-dodecane, methylbenzene, and benzene; preferably, the diluent is selected from kerosene or n-dodecane.
4. The method of claim 1, wherein the method comprises the steps of:
s1, dissolving the irradiated neptunium target to obtain a first feed liquid; performing first extraction on the first feed liquid by using the extractant to obtain a first water phase containing plutonium-238;
s2, adjusting the valence state of the plutonium-238 in the first aqueous phase to obtain a second feed liquid; performing second extraction on the second feed liquid by using the extracting agent to obtain a first organic phase; carrying out first back extraction on the first organic phase to obtain a second aqueous phase;
s3, adjusting the valence state of the plutonium-238 in the second aqueous phase to obtain a third feed liquid; performing third extraction on the third feed liquid by using the extracting agent to obtain a second organic phase; and carrying out second back extraction on the second organic phase to obtain a third aqueous phase.
5. The method of claim 4, wherein,
in step S1, the valence state of the neptunium-237 in the first feed liquid is one of tetravalent, pentavalent and hexavalent, and the valence state of the plutonium-238 is one of trivalent, tetravalent and hexavalent;
in step S2, the valence state of plutonium-238 in the second feed liquid is trivalent or tetravalent, preferably tetravalent;
in step S3, the valence of plutonium-238 in the third feed liquid is trivalent or tetravalent, preferably tetravalent.
6. A method according to claim 4 in which, in step S1, the first liquor is an acidic solution of neptunium plutonium; preferably neptunium plutonium in nitric acid.
7. Method according to claim 4, in which the plutonium-238 concentration in the third aqueous phase is not lower than 5g/L and the neptunium-237 concentration is not higher than 10-3g/L。
8. The method of claim 4, wherein,
in step S1, the conditions of the first extraction include: extracting and washing by using nitric acid, wherein the number of extraction stages is not less than 6; wherein the concentration of the nitric acid in the extraction process is 1-4mol/L, and the concentration of the nitric acid in the washing process is 1-4 mol/L;
in step S2, the conditions of the second extraction include: extracting and washing by using nitric acid, wherein the number of extraction stages is not less than 5; wherein the concentration of the nitric acid in the extraction process is 1-5mol/L, and the concentration of the nitric acid in the washing process is 1-5 mol/L;
in step S3, the conditions of the third extraction include: extracting and washing by using nitric acid, wherein the number of extraction stages is not less than 5; wherein the concentration of the nitric acid in the extraction process is 1-5mol/L, and the concentration of the nitric acid in the washing process is 1-5 mol/L.
9. The method of claim 4, wherein,
in step S2, the conditions of the first stripping include: the back extraction stage number is not lower than 5 stages, the concentration of nitric acid is 0.3-2mol/L, and the used back extractant is selected from at least one of ferrous sulfamate, hydroxylamine and dimethylhydroxylamine;
in step S3, the conditions of the second stripping include: the back extraction stage number is not less than 5 stages, the concentration of nitric acid is 0.3-2mol/L, and the used back extraction agent is at least one of ferrous sulfamate, hydroxylamine and dimethylhydroxylamine.
10. The method according to claim 4, wherein in step S1, the irradiated Np target is dissolved using a mercury catalyzed dissolution technique and a catalyzed indirect electrochemical technique.
CN202110667946.3A 2021-06-16 2021-06-16 Method for extracting plutonium-238 from irradiated neptunium target Pending CN113512653A (en)

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