阅读说明：本技术 氟化挥发技术分离铀和镎的方法 (Method for separating uranium and neptunium by fluorination volatilization technology ) 是由 孙理鑫 牛永生 胡聪伟 窦强 李晴暖 于 2021-09-08 设计创作，主要内容包括：本发明提供了一种氟化挥发技术分离铀和镎的方法,包括以下步骤：①去除反应器中的空气和水,反应器装有混合物A或者混合物B；混合物A包括含铀和含镎元素的物质,混合物B包括含铀元素的物质、含镎元素的物质以及熔盐；含铀元素的物质包含铀单质和/或铀的化合物；含镎元素的物质为镎单质和/或镎的化合物；②回收含铀元素的反应产物；③将回收铀元素后的剩余产物冷却至350-600℃,通入氟气和惰性气体的混合气体,回收含镎元素的反应产物；步骤②中反应温度高于步骤③的温度。本发明的方法具有反应速度快,铀和镎的转化率大,铀和镎的分离效率高；副反应少,分离选择性好,易于连续化优点。(The invention provides a method for separating uranium and neptunium by a fluorination volatilization technology, which comprises the following steps: removing air and water in a reactor, wherein the reactor is filled with a mixture A or a mixture B; mixture A comprises a uranium-containing substance and a neptunium-containing substance, and mixture B comprises a uranium-containing substance, a neptunium-containing substance and a molten salt; the uranium-containing substance comprises elemental uranium and/or a compound of uranium; the substance containing the neptunium element is a neptunium simple substance and/or a neptunium compound; recovering reaction products containing uranium elements; thirdly, cooling the residual product after recycling the uranium element to 350-600 ℃, introducing mixed gas of fluorine gas and inert gas, and recycling the reaction product containing the neptunium element; the reaction temperature in the second step is higher than that in the third step. The method has the advantages of high reaction speed, high conversion rate of uranium and neptunium, and high separation efficiency of uranium and neptunium; less side reaction, high separation selectivity and easy continuous process.)

1. A method for separating uranium and neptunium by a fluorination volatilization technology is characterized by comprising the following steps:

(1) removing air and water in a reactor, wherein the reactor is filled with a mixture A or a mixture B; the mixture A comprises a substance containing uranium and a substance containing neptunium, and the mixture B comprises the substance containing uranium, the substance containing neptunium and a molten salt;

the uranium-containing material comprises elemental uranium and/or a compound of uranium; the substance containing the neptunium element is a neptunium simple substance and/or a neptunium compound;

(2) recovering reaction products containing uranium elements;

(3) cooling the residual product obtained after recovering the uranium element in the step (2) to 350-600 ℃, introducing a mixed gas of fluorine gas and inert gas, reacting, and recovering a reaction product containing neptunium element;

the reaction temperature in the step (2) is higher than that in the step (3).

2. The method for separating uranium and neptunium by the fluo-volatilization technology according to claim 1, characterized in that the content of uranium element in the mixture A or the mixture B is greater than or equal to 1 ppm;

and/or the uranium containing material further comprises a nuclear fission product and/or a metal alloy.

3. A process for the separation of uranium and neptunium by fluo-volatilization technique according to claim 1, wherein in step (1), the uranium compound is one or more of fluoride, oxide and nitride, preferably one or more of uranium tetrafluoride, uranyl fluoride, uranium trioxide, triuranium octoxide, uranium dioxide, uranium nitride, etc., such as uranium tetrafluoride or uranium dioxide;

and/or the neptunium compound is one or more of neptunium oxide, neptunium fluoride and neptunium chloride;

preferably, the compound of the neptunium and the neptunium element in the neptunium simple substance are²³⁷Np。

4. The method for separating uranium and neptunium by the fluo-volatilization technology as claimed in claim 1, wherein in the step (1), the molten salt is a eutectic salt in the mixture B;

the co-molten salt is preferably a fluorine-containing co-molten salt; more preferably KF-ZrF₄Eutectic salt, NaF-ZrF₄Eutectic salt and LiF-BeF₂One or more of a eutectic salt;

the KF-ZrF₄KF and ZrF in eutectic salt₄Is preferably 58: 42;

the NaF-ZrF₄NaF and ZrF in eutectic salt₄Is preferably 58: 42;

the LiF-BeF₂LiF and BeF in eutectic salt₂Is preferably 67: 33.

5. the process for separating uranium and neptunium by the fluo-volatilization technique according to claim 1, characterized in that in step (2), the recovery of the reaction product containing uranium is carried out according to the following steps: heating the reactor, introducing mixed gas of nitrogen trifluoride and inert gas, reacting, and collecting a reaction product containing uranium elements;

in the process of recovering the reaction product containing uranium, preferably, the heating process is heating from room temperature to 450-700 ℃, for example, heating from room temperature to 450 ℃, 500 ℃, 650 ℃ or 700 ℃;

in the process of recycling the reaction product containing uranium, the reactor is heated to the reaction temperature, and then heat preservation is preferably carried out;

in the process of recovering the reaction product containing uranium, preferably, the heat preservation time is 1h to 4h, for example, 1h, 2h or 3 h;

in the process of recovering the reaction product containing uranium, preferably, the volume fraction of nitrogen trifluoride in the mixed gas of nitrogen trifluoride and inert gas is 5% to 100%, more preferably 10% to 30%, for example, 20%, 25% or 30%;

in the process of recovering the reaction product containing uranium, the aeration flow rate of the mixed gas is preferably 0.1L/min to 5L/min, more preferably 0.2L/min to 3L/min, more preferably 0.3L/min to 3L/min, more preferably 0.5L/min to 3L/min;

in the process of recovering the reaction product containing uranium, preferably, UF in the reaction product₆Stopping the reaction when the concentration is lower than the lower detection limit; the detection mode is that the outlet gas of the reactor is detected on line by a Fourier infrared spectrometer;

in the process of recycling the reaction product containing uranium, preferably, the reaction time is 30min to 120min, and then, the reaction is stopped;

in the process of recovering the reaction product containing uranium, preferably, the mixed gas of nitrogen trifluoride and inert gas is continuously introduced;

in the process of recovering the reaction product containing uranium, the method for collecting the reaction product containing uranium is preferably a condensation method, an adsorption method or a solution absorption method;

wherein the condensation method is to condense by using a cold trap, preferably a multi-stage cold trap, more preferably a secondary cold trap;

in the process of recovering the reaction product containing uranium by adopting a condensation method, the condensation temperature is preferably-5 ℃ to-100 ℃, and more preferably-40 ℃ to-60 ℃;

wherein the adsorption method comprises the steps of adsorbing through an adsorption column with an adsorbent;

in the adsorption method, the adsorption column is preferably a multi-stage adsorption column, more preferably a two-stage adsorption column;

in the adsorption method, the adsorption temperature is preferably 0 ℃ to 200 ℃;

in the process of recovering the reaction product containing uranium by using an adsorption method, the adsorbent used is preferably sodium fluoride, and the adsorption temperature is preferably 90-110 ℃, and more preferably 100-110 ℃.

6. The method for separating uranium and neptunium by the fluorination volatilization technology as claimed in claim 1, wherein in the step (3), the cooling is performed to 350-600 ℃, for example, to 350 ℃, 400 ℃, 450 ℃, 500 ℃, 550 ℃ or 600 ℃;

preferably, the heat preservation is performed after the cooling to 350-.

7. The process according to claim 1, wherein in the step (3), the volume fraction of the fluorine gas in the mixed gas of fluorine gas and inert gas is 5% to 100%, preferably 10% to 30%, for example 15%, 20%, 30%, 40%, 50%, 60%, 70%, 80% or 90%.

8. The method for separating uranium and neptunium by fluo-volatilization technique according to claim 1, wherein in step (3), the aeration flow rate of the mixed gas is 0.1L/min to 5L/min, preferably 0.2L/min to 3L/min, preferably 0.3L/min to 3L/min, preferably 0.5L/min to 3L/min.

9. The process for separating uranium and neptunium by the fluo-volatilization technique according to claim 1, wherein in step (3), the reaction time is 60min to 120min, for example 70min, 80min or 90 min.

10. The process for separating uranium and neptunium by volatilization by fluorination according to claim 1, characterized in that the process for recovering the reaction product containing neptunium element in step (3) is preferably a condensation process, an adsorption process or a solution absorption process;

wherein the condensation method is to condense by using a cold trap, preferably a multi-stage cold trap, more preferably a secondary cold trap;

in the process of recovering the reaction product containing neptunium element by condensation, the condensation temperature is preferably-5 ℃ to-100 ℃, more preferably-40 ℃ to-60 ℃;

wherein the adsorption method comprises the steps of adsorbing through an adsorption column with an adsorbent;

in the adsorption method, the adsorption column is preferably a multi-stage adsorption column, more preferably a two-stage adsorption column;

in the adsorption method, the adsorption temperature is preferably 0 ℃ to 200 ℃;

in the solution absorption method, the absorption liquid adopted is preferably a nitric acid solution, and the concentration of the nitric acid solution is preferably 0.1-1 mol/L; more preferably 0.5 to 1 mol/L.

Technical Field

The invention relates to a method for separating uranium and neptunium by fluorination and volatilization.

Background

Nuclear energy, as an efficient, clean and economical energy source, plays an important role in meeting the long-term demand of human energy and coping with the environmental greenhouse effect, and nuclear energy power generation is the most important aspect of nuclear energy and flat utilization. Along with the development and people's right of the power stack²³⁷Np is a deep knowledge of minor actinides with strong toxicity and long service life,²³⁷the limitation of the content of Np in uranium products is of great concern. Because the operating environment of the uranium conversion process has no special protection conditions, strict control is needed to be carried out on the post-treatment uranium products²³⁷The content of Np. On the other hand, in the case of a liquid,²³⁷np heat radiation products²³⁸Pu is an important alpha-emitting source, so that²³⁸The isotope battery prepared by Pu has higher specific power and long service life, is an ideal fuel of a radioactive isotope power supply and a heat source required for developing space activities, and has very important application value in aerospace industry and medical health industry.

At present, commercial post-treatment plants adopt a water-method Purex process to carry out post-treatment on spent fuel. However, it is difficult to quantitatively drive neptunium into a certain stream in the Purex process, unlike uranium plutonium. The chemical form of neptunium is complex, the extraction behaviors of neptunium with different valence states are different, and complex chemical reactions of mutual conversion exist between neptunium and neptunium. Therefore, the trend of the neptunium is dispersed in the Purex process, and the separation and recovery of the neptunium have a plurality of difficulties. In conclusion, the water-method post-treatment represented by the Purex process is still the main method, and the industrial operation of the Purex process accumulates abundant experience and makes important contribution to the development of nuclear energy. However, the method has long and complicated flow and poor economy, and is not suitable for processing spent fuel with high fuel consumption and short cooling time.

Chinese patent document CN201210548013.3 discloses a method for separating neptunium from uranium products by using a TEVA-utava extraction chromatographic column, which can separate uranium from neptunium, but the extraction method is complicated in operation, has high requirements for an extraction agent, and cannot achieve continuous production.

Compared with the water method post-treatment technology, the dry method post-treatment technology of another important technology of the post-treatment of the spent fuel has the advantages of radiation resistance, low critical risk, diffusion prevention, less radioactive waste, more suitability for treating various forms of irradiated fuels with high fuel consumption and short cooling period and the like. At present, no precedent for separating uranium from neptunium by adopting a dry post-processing technology exists in the prior art.

Disclosure of Invention

The invention aims to solve the technical problem of providing a method for separating uranium and neptunium by a fluorination volatilization technology to overcome the defects of complex operation, high requirement on an extracting agent and incapability of realizing continuity in the prior art for separating the uranium and the neptunium, and realizing efficient separation of the uranium and the neptunium. The method has the advantages of high reaction speed, high conversion rate of uranium and neptunium, and high separation efficiency of uranium and neptunium; the side reaction is less, and the separation selectivity is good; easy to be continuous.

The inventor of the present application finds that, in the initial research period, when the uranium and the neptunium are separated by using a fluorination and volatilization method, the neptunium content in the obtained uranium product is high, and the neptunium content in the uranium product cannot be strictly controlled.

Through continuous exploration and experiments of the inventor and creative work, the inventor finds that the technical problem of the invention can be effectively solved by adopting a specific heating mode, firstly recovering the reaction product containing uranium and then recovering the reaction product containing neptunium. The technical difficulties of the invention are mainly reflected as follows:

when the reaction temperature is high and the selected fluorinating agent is relatively active, the uranium and the neptunium which react with the fluorinating agent can be subjected to fluorination volatilization reaction, so that the uranium and the neptunium cannot be separated; when the reaction temperature is lower than 750 ℃, most of the fluorinating agents (except fluorine gas) used in the experiment do not react with the neptunium, and the neptunium cannot be recovered. The oxidizing properties of the various fluorinating agents are different, and at different temperatures, the fluorinating agents are different from neptunium and uranium and are difficult to predict. Therefore, the difficulty and key point in separating uranium from neptunium is to select a proper fluorinating agent and a proper fluorination temperature.

The invention solves the technical problems through the following technical scheme:

the invention provides a method for separating uranium and neptunium by a fluorination and volatilization technology, which comprises the following steps:

(1) removing air and water in a reactor, wherein the reactor is filled with a mixture A or a mixture B; the mixture A comprises a substance containing uranium and a substance containing neptunium, and the mixture B comprises the substance containing uranium, the substance containing neptunium and a molten salt;

wherein the uranium-containing material comprises elemental uranium and/or a compound of uranium; the substance containing the neptunium element is a neptunium simple substance and/or a neptunium compound;

(2) recovering reaction products containing uranium elements;

(3) cooling the residual product obtained after recovering the uranium element in the step (2) to 350-600 ℃, introducing a mixed gas of fluorine gas and inert gas, reacting, and recovering a reaction product containing neptunium element;

wherein the reaction temperature in the step (2) is higher than that in the step (3).

In step (1), the air and water in the reactor may be removed by a conventional method in the art, and preferably, the air and water in the reactor are removed by an inert gas.

In step (1), the ratio of the uranium-containing substance to the neptunium-containing substance in the mixture a or the mixture B may be arbitrary.

In step (1), the ratio of the uranium-containing substance, the neptunium-containing substance, and the molten salt in the mixture B may be any ratio.

In the step (1), the content of uranium in the mixture a or the mixture B is preferably 1ppm or more.

In step (1), the uranium-containing material preferably further contains a nuclear fission product and/or a metal alloy.

Wherein the nuclear fission product is a nuclear fission product conventional in the art.

Wherein the metal alloy is one or more of metal alloys conventional in the art, such as uranium zirconium alloy, nickel-based alloy, aluminum alloy, and the like.

In step (1), the uranium compound generally refers to a uranium-containing compound, preferably one or more of uranium-containing fluoride, uranium-containing oxide and uranium-containing nitride, more preferably one or more of uranium tetrafluoride, uranyl fluoride, uranium trioxide, triuranium octoxide, uranium dioxide, uranium nitride and the like, such as uranium tetrafluoride or uranium dioxide.

In step (1), the neptunium compound generally refers to a neptunium-containing compound, preferably one or more of neptunium oxide, neptunium fluoride, neptunium chloride and the like.

In step (1), the compound of neptunium and the neptunium element in the simple substance of neptunium are preferably 237 Np.

In step (1), in the mixture B, the molten salt is preferably a eutectic salt.

Wherein, the co-molten salt can be fluorine-containing co-molten salt which is conventional in the field; preferably KF-ZrF₄Eutectic salt, NaF-ZrF₄Eutectic salt and LiF-BeF₂One or more of eutectic salts.

The KF-ZrF₄KF and ZrF in eutectic salt₄Is preferably 58: 42.

the NaF-ZrF₄NaF and ZrF in eutectic salt₄Is preferably 58: 42.

the LiF-BeF₂LiF and BeF in eutectic salt₂Is preferably 67: 33.

in step (2), the method for recovering the reaction product containing uranium may be conventional in the art, and preferably comprises the following steps: and heating the reactor, and introducing mixed gas of nitrogen trifluoride and inert gas to carry out reaction.

The heating process is preferably from room temperature to 450-700 ℃, such as from room temperature to 450 ℃, 500 ℃, 650 ℃ or 700 ℃.

Wherein, after heating the reactor to the reaction temperature, the temperature is preferably maintained. The incubation time is preferably 1h to 4h, for example 1h, 2h or 3 h.

It will be appreciated by those skilled in the art that in step (2), the temperature of the reaction is the incubation temperature.

Wherein, in carrying out the reaction, the amount of nitrogen trifluoride used in the mixed gas of nitrogen trifluoride and an inert gas is preferably in excess in stoichiometric ratio with respect to the uranium element content in the reactor.

Wherein, in the mixed gas of nitrogen trifluoride and inert gas, the volume fraction of nitrogen trifluoride is preferably 5% to 100%, more preferably 10% to 30%, for example 20%, 25% or 30%.

Wherein, the aeration flow rate of the mixed gas is preferably 0.1L/min-5L/min, more preferably 0.2L/min-3L/min, more preferably 0.3L/min-3L/min, more preferably 0.5L/min-3L/min.

It will be understood by those skilled in the art that in step (2), the uranium-containing reaction product contains UF₆。

Wherein said UF is present in said reaction product as is conventional in the art₆The reaction was stopped at a concentration below the lower detection limit.

Preferably, the detection mode is to detect the outlet gas of the reactor on line by a Fourier infrared spectrometer.

Preferably, the reaction time is 30min-120min, after which the reaction is stopped.

Wherein the stopping of the reaction is preferably carried out by stopping the introduction of the mixed gas of the nitrogen trifluoride and the inert gas. It will be understood by those skilled in the art that the time for continuously feeding the mixed gas of nitrogen trifluoride and inert gas is generally the same as the reaction time.

Preferably, the mixed gas of nitrogen trifluoride and inert gas is introduced continuously.

In step (3), the cooling is performed to 350-600 ℃, for example, to 350 ℃, 400 ℃, 450 ℃, 500 ℃, 550 ℃ or 600 ℃.

In the step (3), after the cooling to 350-. The incubation time is preferably 1h to 4h, for example 1h, 2h or 3 h.

It will be appreciated by those skilled in the art that in step (3), the temperature of the reaction is the incubation temperature.

In the step (3), in carrying out the reaction, the amount of the fluorine gas in the mixed gas of the fluorine gas and the inert gas is preferably in excess in a stoichiometric ratio with respect to the content of the neptunium element in the reactor.

In the mixed gas of the fluorine gas and the inert gas in the step (3), the volume fraction of the fluorine gas is preferably 5% to 100%, more preferably 10% to 30%, for example, 15%, 20%, 30%, 40%, 50%, 60%, 70%, 80%, or 90%.

In the step (3), the aeration flow rate of the mixed gas is preferably 0.1L/min to 5L/min, more preferably 0.2L/min to 3L/min, more preferably 0.3L/min to 3L/min, and more preferably 0.5L/min to 3L/min.

It will be understood by those skilled in the art that in step (3), the neptunium-containing reaction product contains NpF₆。

In the step (3), preferably, the reaction time is 60min to 120min, for example, the reaction time may be 70min, 80min or 90 min; after that, the reaction was stopped.

In the step (3), stopping the reaction is generally achieved by stopping the supply of the mixed gas of the fluorine gas and the inert gas. It will be understood by those skilled in the art that the respective times of continuously feeding the mixed gas of fluorine gas and inert gas are generally in accordance with the reaction times.

Preferably, the mixed gas of the fluorine gas and the inert gas is continuously introduced.

The recovery of the reaction product containing uranium in step (2) or the recovery of the reaction product containing neptunium in step (3) can be carried out in a manner conventional in the art, preferably by condensation, adsorption or solution absorption.

The condensation process is typically carried out by using a cold trap. The cold trap may be a cold trap conventional in the art, preferably a multi-stage cold trap, more preferably a two-stage cold trap. The temperature of the condensation is preferably-5 ℃ to-100 ℃, more preferably-40 ℃ to-60 ℃.

The adsorption method generally performs adsorption through an adsorption column having an adsorbent.

The adsorption column may be a conventional adsorption column in the art, preferably a multi-stage adsorption column, and more preferably a two-stage adsorption column.

Wherein the temperature of the adsorption is preferably 0 ℃ to 200 ℃.

In the step (2), the adsorbent used for recovering the reaction product containing uranium elements is preferably sodium fluoride, and the temperature of the adsorption is preferably 90-110 ℃, more preferably 100-110 ℃.

In the step (3), the absorption liquid used for recovering the reaction product containing neptunium element is preferably a nitric acid solution, and the concentration of the nitric acid is preferably 0.1-1 mol/L; more preferably 0.5 to 1 mol/L.

In the present invention, the room temperature is a room temperature well known to those skilled in the art, that is, 5 ℃ to 40 ℃.

In the present invention, the inert gas involved may be any one or more of inert gases conventional in the art, such as helium, neon and argon.

On the basis of the common knowledge in the field, the above preferred conditions can be combined randomly to obtain the preferred embodiments of the invention.

The reagents and starting materials used in the present invention are commercially available.

The positive progress effects of the invention are as follows:

the method of the invention has the following advantages:

1) the nitrogen trifluoride has low chemical toxicity and stable property at normal temperature, so the safety in production, transportation, storage and use is higher.

2) The method has the advantages that the high-efficiency separation of uranium and neptunium can be realized by using different fluorinating agents for step-by-step fluorination reaction, the reaction speed is high, the conversion rate of uranium and neptunium is high, and the separation efficiency is high; the side reaction is less, and the separation selectivity is good; easy to be continuous, etc.

Detailed Description

The invention is further illustrated by the following examples, which are not intended to limit the scope of the invention. The experimental methods without specifying specific conditions in the following examples were selected according to the conventional methods and conditions, or according to the commercial instructions.

Conversion of simple substance Np, UF in the examples₄Conversion and UF₆And NpF₆The separation coefficient of (a) is calculated as follows:

in the following examples, Np is elemental neptunium²³⁷Np。

Example 1UF₄And separation of uranium and neptunium in a mixture of elementary substances Np

(1) Mixing 5.0g of UF₄And 1mg of the neptunium simple substance are placed in a reactor, the reactor cover is covered, and the atmosphere in the reactor is replaced by high-purity argon.

(2) Heating the reactor to raise the temperature from room temperature to 450 ℃, keeping the temperature for 2h, and introducing a nitrogen trifluoride and argon gas mixed gas (NF) into the reactor through a mass flow meter₃The volume fraction of (1) is 20 percent), the flow rate is 0.3L/min, and a Fourier infrared spectrometer is adopted to monitor the gas at the outlet of the reactor; UF recovery using two stages of NaF adsorption columns₆The temperature of the product and the adsorption column is 100 ℃; UF in reactor outlet gas after 60min₆When the concentration is lower than the lower limit of infrared detection, the introduction of the nitrogen trifluoride mixed gas is stopped.

(3) Stopping heating the reactor to reduce the temperature to 350 ℃, preserving the temperature for 1h, and introducing a fluorine gas and argon gas mixed gas (F) into the reactor through a mass flow meter₂20% by volume) and a flow rate of 0.3L/min; NpF is recovered by adopting two-stage nitric acid absorption liquid with the concentration of 1mol/L₆A product; and stopping introducing the fluorine gas mixture after 60 min.

Effect data: open and reverseThe reactor has almost no raw material residue, the conversion rate of Np simple substance and UF₄Conversion of about 100%, UF in adsorption column₆And NpF in the absorption liquid₆The product is detected and analyzed by ICP-MS, and the separation coefficient of the product and the product is 10³。

Example 2UO₂And separation of uranium and neptunium in a mixture of elementary substances Np

(1) 3.0g of UO₂And 1mg of the neptunium simple substance are placed in a reactor, the reactor cover is covered, and the atmosphere in the reactor is replaced by high-purity argon.

(2) Heating the reactor to raise the temperature from room temperature to 500 ℃, then preserving the heat for 1h, and introducing a nitrogen trifluoride and argon gas mixed gas (NF) into the reactor through a mass flow meter₃The volume fraction of the gas is 30 percent), the flow rate is 0.2L/min, and a Fourier infrared spectrometer is adopted to monitor the gas at the outlet of the reactor; UF recovery with two-stage cold traps₆The condensation temperature of the product is-40 ℃; UF in reactor outlet gas after 120min₆When the concentration is lower than the lower limit of infrared detection, the introduction of the nitrogen trifluoride mixed gas is stopped.

(3) Stopping heating the reactor to reduce the temperature to 350 ℃, preserving the temperature for 1h, and introducing a fluorine gas and argon gas mixed gas (F) into the reactor through a mass flow meter₂30 percent by volume) and the flow rate is 0.2L/min; with additional two stages of cold trap recovery NpF₆The temperature of the product and the cold trap is-60 ℃; and stopping introducing the fluorine gas mixture after 60 min.

Effect data: opening the reactor almost without feedstock residue, Np conversion and UO₂Conversion of about 100%, UF in cold trap₆And NpF₆The product is detected and analyzed by ICP-MS, and the separation coefficient of the product and the product is 10⁴。

Example 3LiF-BeF₂Separation of uranium and neptunium in molten salt system

(1) 100g LiF-BeF₂Molten salt (where UF₄Mass 5.0g, Np mass 0.5 mg; LiF and BeF in eutectic salt₂In a molar ratio of 67: 33) the reactor was placed in a reactor, and the reactor was covered with a lid, and the atmosphere in the reactor was replaced with high-purity argon gas.

(2) Heating the reactor to raise the temperature from room temperature to 700 ℃, then preserving the heat for 3h,introducing a mixed gas (NF) of nitrogen trifluoride and argon into the reactor through a mass flow meter₃The volume fraction of (1) is 10 percent), the flow rate is 0.5L/min, and a Fourier infrared spectrometer is adopted to monitor the gas at the outlet of the reactor; UF recovery using two stages of NaF adsorption columns₆The temperature of the product and the adsorption column is 100 ℃; UF in reactor outlet gas after 60min₆When the concentration is lower than the lower limit of infrared detection, the introduction of the nitrogen trifluoride mixed gas is stopped.

(3) Stopping heating the reactor to reduce the temperature to 600 ℃, preserving the temperature for 2h, and introducing a fluorine gas and argon gas mixed gas (F) into the reactor through a mass flow meter₂Volume fraction of (1)% of (3)%), flow rate of 0.5L/min, and recovery of NpF by two-stage cold trap₆The condensation temperature of the product is-50 ℃; and stopping introducing the nitrogen trifluoride mixed gas after 90 min.

Effect data: opening the reactor, LiF-BeF₂ICP-MS detection and analysis are carried out on the molten salt, the content of the Np element in the molten salt after reaction is 1ppm, the content of the uranium element is 20ppm, the Np conversion rate and UF₄Conversion rate is above 99%, UF in adsorption column₆Product and cold trap NpF₆The product is detected and analyzed by ICP-MS, and the separation coefficient of the product and the product is 10⁴。

Example 4KF-ZrF₄Separation of uranium and neptunium in molten salt system

(1) 1000g of KF-ZrF₄Molten salt (where UF₄The mass is 10.0g, and the mass of Np is 1 mg; KF and ZrF in eutectic salt₄Is 58: 42) the reactor was placed in a reactor, and the reactor was covered with a lid, and the atmosphere in the reactor was replaced with high-purity argon gas.

(2) Heating the reactor to raise the temperature from room temperature to 650 ℃, keeping the temperature for 2h, and introducing a nitrogen trifluoride and argon gas mixed gas (NF) into the reactor through a mass flow meter₃The volume fraction of (1) is 10 percent), the flow rate is 2.0L/min, and a Fourier infrared spectrometer is adopted to monitor the gas at the outlet of the reactor; UF recovery with two-stage cold traps₆The condensation temperature of the product is-60 ℃; UF in reactor outlet gas after 60min₆When the concentration is lower than the lower limit of infrared detection, the introduction of the nitrogen trifluoride mixed gas is stopped.

(3) Stopping heating the reactor to reduce the temperatureKeeping the temperature for 1h after the temperature reaches 550 ℃, and introducing a fluorine gas and argon gas mixed gas (F) into the reactor through a mass flow meter₂10 percent of volume fraction), the flow rate is 1.0L/min, and NpF is recovered by adopting two-stage nitric acid absorption liquid with the concentration of 1mol/L₆And (4) stopping introducing the fluorine gas mixture after 120 min.

Effect data: opening the reactor, KF-ZrF₄ICP-MS detection and analysis are carried out on the molten salt, the content of the Np element in the molten salt after reaction is 1ppm, the content of the uranium element in the molten salt is 10ppm, the Np conversion rate and UF₄Conversion rate is above 99%, UF in cold trap₆NpF in product and absorption liquid₆The product is detected and analyzed by ICP-MS, and the separation coefficient of the product and the product is 10³。

While specific embodiments of the invention have been described above, it will be appreciated by those skilled in the art that these are by way of example only, and that the scope of the invention is defined by the appended claims. Various changes and modifications to these embodiments may be made by those skilled in the art without departing from the spirit and scope of the invention, and these changes and modifications are within the scope of the invention.