Device and method for separating activation products of americium, uranium, neptunium and plutonium

Abstract

The invention discloses a device and a method for separating activation products of americium, uranium, neptunium and plutonium, belongs to the technical field of separation of activation products, and solves the technical problems that synchronous separation and purification of americium, uranium, neptunium and plutonium cannot be realized and high-sensitivity and high-accuracy detection and analysis cannot be simultaneously met during separation of the activation products. The separation device comprises a liquid storage tank unit, a conveying pump, a color layer separation unit, a product collection unit, a waste liquid collector and a valve which are sequentially arranged from top to bottom. The waste liquid collector and the product collecting unit are positioned at the lowermost end. Liquid in the liquid storage tank unit enters the color layer separation unit through a conveying pump, and liquid flowing out of the color layer separation unit enters the product collection unit or the waste liquid collector. The separation method comprises the following steps: preparing a solution, preparing a chromatography adsorption column, adsorbing americium, uranium, neptunium and plutonium, washing, separating and purifying neptunium, leaching uranium, americium and plutonium, separating and purifying uranium, americium and plutonium, and desorbing. The method is used for separating activation products of americium, uranium, neptunium and plutonium

Description

Technical Field

[0001] This invention belongs to the field of activation product separation technology, specifically relating to a device and method for separating activation products americium-uranium-neptunium-plutonium. Background Technology

[0002] Activation product analysis can determine the neutron flux and neutron energy in the nuclear fuel fission process, and is used for neutron energy spectrum analysis of nuclear reactions. To achieve sustainable development of nuclear energy, improve the efficiency of nuclear fuel recycling, and realize a closed-loop nuclear fuel cycle, uranium-plutonium mixed fuel (MOX fuel) has become the mainstream fuel for fast reactors widely used internationally (Yang Qifa et al. Research and Development Progress of Fast Reactor MOX Fuel Technology. Atomic Energy Science and Technology. 2020, 54(Supplement): 246-250.). Uranium materials contain natural isotopes U-234 (abundance 0.00584%), U-235 (abundance 0.72%), and U-238 (abundance 99.27%). Plutonium materials contain various Pu isotopes (such as Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, etc.) and are formed by the β-transformation of Pu-241 with a half-life of 14.29 years. - Am-241 (half-life 432.2 years) is generated by decay.

[0003] In a neutron field, americium-uranium-plutonium primarily produces threshold-free (n, Americium isotopes exhibit (n, 2n) and threshold activation reactions, while at exceptionally high neutron energies, they produce activation reactions with even higher thresholds, such as (n, 3n). The (n, 2n) activation reaction of americium isotope Am-241... The products of the (n,2n) activation reactions are: Am-242g with a half-life of 16.0 hours, Am-242m with a half-life of 141 years, and Am-240 with a half-life of 50.8 hours, among which Am-241 (n,2n) has a reaction threshold of 6.66 MeV. The (n,2n) activation reaction of the uranium isotope U-238... The product of the activation reaction is U-239 (half-life 23.45 minutes), which quickly undergoes β-reactivation. -The decay produces Np-239 (half-life 2.35 days); the (n,2n) activation reaction of the uranium isotope U-238 produces U-237 (half-life 6.75 days), with a reaction threshold of 6.19 MeV. The (n,2n) activation reaction of the plutonium isotope Pu-238 produces Pu-237 (half-life 45.6 days), with a reaction threshold of 7.3 MeV. With advancements in nuclear detection technology, the detection of ultra-trace (n,3n) reaction activation products has become possible. The reaction thresholds for Am-241(n,3n) are 12.6 MeV, U-238(n,3n) is 12.0 MeV, U-235(n,3n) is 12.3 MeV, Pu-238(n,3n) is 13.0 MeV, and Pu-239(n,3n) is 12.8 MeV.

[0004] Because the activation products are produced in low quantities, especially (n,2n) and (n,3n) reaction products which are at trace and ultra-trace levels, radiochemical separation is required to remove interfering nuclides and prepare radiochemically pure nuclides to achieve accurate detection and analysis of the activation products. During uranium-plutonium fission, a large number of fission products are generated, including Nd-147, Ba-140, La-140, Te-132, I-132, I-131, Zr-95, Nb-95, Ce-141, Ce-144, Mo-99, Tc-99m, and Ru-103, whose activities are much greater than those of the activation products. In high-purity germanium traps... During energy dispersive spectroscopy measurements, these fission products emitted a large amount of... X-rays are a major factor interfering with the analysis of activation products of americium-uranium-neptunium-plutonium. Furthermore, there is varying degrees of interference between the target nuclei and the activation products themselves. For example, Np-239 causes spectral peak interference in the measurements of U-237, Am-241, and Am-242g; U-237 causes spectral peak interference in the measurements of Am-241 and Am-242g; and Np-239, U-237, Am-241, and Am-242g cause spectral peak interference in the measurements of Pu-237, etc.

[0005] Chinese invention patent CN106198165A discloses a rapid separation device and method for activated product americium gallium. This separation method achieves effective separation of activated product americium gallium from fission products, but does not mention the simultaneous separation and purification technology and method for activated products neptunium plutonium and activated product americium. Therefore, it cannot simultaneously meet the technical requirements of high sensitivity and high accuracy detection and analysis of activated products americium uranium neptunium plutonium. Summary of the Invention

[0006] To overcome the shortcomings of the separation of activated products, such as the inability to simultaneously separate and purify americium, uranium, neptunium, and plutonium, and to simultaneously meet the requirements of high sensitivity and high accuracy detection and analysis, this invention proposes a device and method for separating activated products americium, uranium, neptunium, and plutonium.

[0007] The technical solution adopted by this invention to solve its technical problem is: A separation device for activated products americium-uranium-neptunium-plutonium includes a storage tank unit, a chromatography separation unit, a waste liquid collector, a product collection unit, valves, a transfer pump, and pipelines; The liquid storage tank unit, color layer separation unit, waste liquid collector, valve and product collection unit are connected by pipelines; The storage tank unit includes a storage tank containing americium, uranium, neptunium, and plutonium radioactive solution, a washing liquid storage tank, a leaching liquid storage tank, a first-stage desorption liquid storage tank for uranium, a desorption liquid storage tank for americium and plutonium, a leaching liquid storage tank for neptunium, a first-stage leaching liquid storage tank for uranium, a second-stage leaching liquid storage tank for uranium, a third-stage leaching liquid storage tank for uranium, a second-stage desorption liquid storage tank for uranium, a first-stage leaching liquid storage tank for americium, a second-stage leaching liquid storage tank for americium, a first-stage leaching liquid storage tank for plutonium, a second-stage leaching liquid storage tank for plutonium, a first-stage desorption liquid storage tank for plutonium, a third-stage leaching liquid storage tank for plutonium, and a second-stage desorption liquid storage tank for plutonium. The color layer separation unit includes a TBP color layer adsorption column, a first DN color layer adsorption column, and a first P... 204 Or HDEHP or LN chromatography column, DAAP or UTEVA chromatography column, second P 204 Or HDEHP or LN chromatography column, TRU or RE chromatography column, or second DN chromatography column; The product collection unit includes a uranium product collector, a neptunium product collector, an americium product collector, and a plutonium product collector; The outlets of the americium-uranium-neptunium-plutonium radioactive solution storage tank, washing solution storage tank, rinsing solution storage tank, uranium first-stage desorption solution storage tank, americium-plutonium desorption solution storage tank, neptunium rinsing solution storage tank, neptunium desorption solution storage tank, uranium first-stage rinsing solution storage tank, uranium second-stage rinsing solution storage tank, uranium third-stage rinsing solution storage tank, uranium second-stage desorption solution storage tank, americium first-stage rinsing solution storage tank, americium second-stage rinsing solution storage tank, americium desorption solution storage tank, plutonium first-stage rinsing solution storage tank, plutonium second-stage rinsing solution storage tank, plutonium first-stage desorption solution storage tank, plutonium third-stage rinsing solution storage tank, and plutonium second-stage desorption solution storage tank are connected to multiple inlets of a transfer pump via valves. The outlet of the delivery pump is connected to the TBP chromatograph column, the first DN chromatograph column, the TRU or RE chromatograph column, and the first P chromatograph column via valves. 204Connect the feed inlet of either HDEHP or LN chromatography column, DAAP or UTEVA chromatography column, or second DN chromatography column. The outlet of the TBP chromatographic adsorption column is connected to the inlet of the uranium product collector and the waste liquid collector respectively through valves. The outlet of the first DN chromolayer adsorption column is connected to the bottom of the first-stage uranium eluent storage tank, the waste liquid collector, the inlet of the TRU or RE chromolayer adsorption column, and the bottom of the first-stage americium eluent storage tank via valves. The first P 204 The outlet of either HDEHP or LN chromatography adsorption column is connected to the bottom of the waste liquid collector, americium product collector, and plutonium first-stage rinsing solution storage tank via valves. The outlet of the DAAP or UTEVA chromatography adsorption column is connected to the waste liquid collector and the inlet of the second DN chromatography adsorption column respectively through valves. Second P 204 The discharge port of either the HDEHP or LN chromatography column is connected to the neptunium product collector. The discharge port of the TRU or RE chromatography column is connected to the second P via a valve. 204 Connect the feed inlet of the HDEHP or LN chromatography adsorption column to the waste liquid collector; The outlet of the second DN chromatographic adsorption column is connected to the waste liquid collector and the plutonium product collector via valves.

[0008] The piping uses silicone tubing; the valves are solenoid valves; and the transfer pump is a peristaltic pump. This allows for microcomputer control of the solenoid valves and peristaltic pump, enabling automatic control of the separation process and reducing the impact of radioactive nuclide radiation and toxicity on the human body. The peristaltic pump uses a tubing compression method to deliver the separation liquid, and the flow rate of the liquid is controlled by the pump's rotation speed.

[0009] The transfer pump has multiple inlets and outlets. Each storage tank is connected to a different inlet of the transfer pump via a valve. Each outlet of the transfer pump is connected to a TBP chromatography column, a first DN chromatography column, a TRU or RE chromatography column, and a first P chromatography column via a valve. 204 The feed inlets of either HDEHP or LN chromatographic adsorption columns, DAAP or UTEVA chromatographic adsorption columns, or a second DN chromatographic adsorption column can be connected. This way, after feeding, adsorption, and washing, the rinsing and separation processes of different chromatographic adsorption columns can be carried out simultaneously without affecting each other.

[0010] A method for separating the activation product americium-uranium-neptunium-plutonium, comprising the following steps: Step 1: Preparation before separation A radioactive sample containing the activated product americium-neptunium-plutonium was dissolved in acid, sodium nitrite was added, and the mixture was heated to 70℃~100℃ and maintained for 15 minutes. The mixture was then allowed to cool naturally to room temperature to prepare an aqueous radioactive solution containing americium-neptunium-plutonium. The acids are dissolved in water to form an aqueous washing solution, an aqueous rinsing solution, and an aqueous desorption solution. TBP, DN, P 204 Alternatively, HDEHP or LN, DAAP or UTEVA, TRU or RE can be packed into the chromogenic adsorption column respectively; Step 2: Adsorption of americium-uranium-neptunium-plutonium The aqueous radioactive sample containing americium-neptunium-plutonium prepared in step 1 was sequentially separated and adsorbed by passing it through a first DN chromatographic adsorption column and a TRU or RE chromatographic adsorption column, and the effluent was collected as waste liquid. Uranium americium and plutonium are adsorbed on the first DN chromatographic adsorption column, while neptunium is adsorbed on the TRU or RE chromatographic adsorption column. Step 3: Washing The washing solution is sequentially washed through a first DN chromatography column and a TRU or RE chromatography column, and the effluent is collected as waste liquid. Step 4: Isolation and purification of neptunium After step 3, the neptunium eluent is further purified by TRU or RE chromatography adsorption column, and the effluent is collected as waste liquid. Step 5: Washing of uranium-americium-plutonium After step 3, the eluent is rinsed through the first DN chromatography adsorption column, and the effluent is collected as waste liquid. The first-stage desorption solution for uranium desorbs uranium through the first DN chromatographic adsorption column, and the effluent enters the first-stage uranium eluent storage tank. The americium-plutonium desorption solution desorbs americium-plutonium through the first DN chromatographic adsorption column, and the effluent enters the first-stage eluent storage tank for americium. Step 6: Uranium separation and purification After step 5, the first-stage uranium eluent, the second-stage uranium eluent, and the third-stage uranium eluent are successively passed through a TBP chromatography column for further purification of the uranium, and the effluent is collected as waste liquid. Step 7: Separation and purification of americium After step 5, the first-stage eluent of americium passes through the first P... 204 Americium was further purified using HDEHP or LN chromatography-adsorption columns, and the effluent entered the first-stage eluent storage tank for plutonium. The second-stage eluent of americium passes through the first P 204 Americium can be further purified using HDEHP or LN chromatography-adsorption columns, and the effluent can be collected as waste liquid. Step 8: Isolation and purification of plutonium After step 7, the first-stage eluent and the second-stage eluent of plutonium were successively purified by DAAP or UTEVA chromatography adsorption columns, and the effluent was collected as waste liquid. The first-stage desorption solution of plutonium is passed through a DAAP or UTEVA chromatography column and a second DN chromatography column for desorption and resorption of plutonium, and the effluent is collected as waste liquid. The third-stage eluent of plutonium was further purified by passing it through a second DN chromatography adsorption column, and the effluent was collected as waste liquid. Step 9: Desorption The second-stage desorption solution of uranium is passed through a TBP chromatography column; the effluent, i.e., the radioactive solution of uranium, is collected in a uranium product collector. The neptunium desorption solution is sequentially passed through a TRU or RE chromatography adsorption column and a second P column. 204 Alternatively, an HDEHP or LN chromatography column can be used; the effluent, i.e., the radioactive solution of neptunium, is collected in a neptunium product collector; The americium desorption solution passes through the first P 204 Alternatively, an HDEHP or LN chromatography column can be used; the effluent, i.e., the radioactive solution of americium, is collected in an americium product collector; The second-stage desorption solution of plutonium is passed through a second DN chromatographic adsorption column; the effluent, i.e., the radioactive solution of plutonium, is collected in a plutonium product collector.

[0011] The aforementioned radioactive samples of americium-uranium-neptunium-plutonium were non-volatile substances produced after neutron irradiation of a mixture of actinide nuclear fuel. Radioactive nuclides.

[0012] The acid in step 1 above is nitric acid, hydrochloric acid, hydrofluoric acid, diethylenetriaminepentaacetic acid, lactic acid, or a combination of the above acids, and the concentration of the acid is 0.01 to 15 mol / L.

[0013] The acid used to dissolve radioactive samples is 2–4 mol / L HNO3; the washing solution is 2–4 mol / L HNO3 solution; the leaching solution is 2–4 mol / L HCl solution; the first-stage desorption solution for uranium is 0.01–0.2 mol / L HNO3 solution; the desorption solution for americium-plutonium is a 0.5–1.5 mol / L lactic acid solution (pH 3.0–3.5) containing 0.04–0.08 mol / L DTPA; the leaching solution for neptunium is 2–4 mol / L HNO3 solution; the desorption solution for neptunium is 0.01–0.1 mol / L HNO3 solution; the first-stage leaching solution for uranium is 2–5 mol / L HNO3 solution; the second-stage leaching solution for uranium is 2–5 mol / L HNO3 solution; the third-stage leaching solution for uranium is 3–5 mol / L HCl solution; the second-stage desorption solution for uranium is 0.01–0.15 mol / L HNO3 solution. The first-stage eluent for americium is a 0.5–1.5 mol / L lactic acid solution (pH 1.0) containing 0.04–0.08 mol / L DTPA; the second-stage eluent for americium is a 0.01–0.15 mol / L HNO3 solution; the desorption solution for americium is a 0.5–1.5 mol / L lactic acid solution (pH 3.0) containing 0.04–0.08 mol / L DTPA; the first-stage eluent for plutonium is a 4–8 mol / L HNO3 solution containing 0.04–0.08 mol / L DTPA and 0.5–1.5 mol / L lactic acid; the second-stage eluent for plutonium is a 4–8 mol / L HNO3 solution; the first-stage desorption solution for plutonium contains 0.01–0.4 mol / L HNO3. The ACB is a 0.5–3 mol / L HNO3 solution; the third-stage eluent for plutonium is a 0.05–0.3 mol / L HNO3 solution; the second-stage desorption solution for plutonium is a 0.05–0.4 mol / L HCl solution containing 0.05–0.3 mol / L HF.

[0014] The americium is included 241 Am(n, ) 242 Am、 241 Am(n,2n) 240 Various americium isotopes of the Am reaction products, wherein the uranium is a composite of... 238 U(n,2n) 237 Various uranium isotopes of the U reaction products, wherein neptunium is a component of 238 U(n, ) 239 U / 239 Various neptunium isotopes of the Np reaction products, wherein the plutonium is a component of 238 Pu(n,2n) 237 Pu、 239 Pu(n,3n) 237Various plutonium isotopes of the Pu reaction products.

[0015] The beneficial effects of this invention are: A method for separating the activated product americium-uranium-neptunium-plutonium effectively utilizes the differences in the chemical complexation behavior of different forms of americium-uranium-neptunium-plutonium using a chromatographic adsorption column. This method employs a DN chromatographic adsorption column and a P... 204 Americium, uranium, neptunium, and plutonium are separated using either HDEHP or LN chromatography-adsorption columns. Further purification and decontamination using subsequent chromatography-adsorption columns enable the integrated, highly selective separation and recovery of the activated products, americium, uranium, neptunium, and plutonium.

[0016] A method for separating the activation products americium-uranium-neptunium-plutonium is presented, featuring clearly defined separation unit functions, a simple process, and easily adjustable flow rates. A streamlined, automatically controlled separation process is constructed through dynamic transformation of the effluent medium and ingenious inter-column connections.

[0017] A method for separating the activation products americium, uranium, neptunium, and plutonium, from the extraction of the original radioactive liquid to the preparation of americium, uranium, neptunium, and plutonium. The entire separation process of the radioactive measurement source is automatically controlled by a microcomputer program, which can significantly reduce the radiation dose to operators.

[0018] A method for separating the activation products americium, uranium, neptunium, and plutonium has been developed. Compared with existing methods, this method achieves simultaneous and highly decontamination-free separation of these products under automated control. The chemical recovery rates of americium, uranium, neptunium, and plutonium reach 80%–93%, and the decontamination factors between the activation products and on fission products are all within 10. 4 ~10 6 . Attached Figure Description

[0019] Figure 1 This is a schematic diagram of the americium-uranium-neptunium-plutonium separation device of the activated products in Embodiment 1 of the present invention; Figure 2 This is the original solution containing americium, uranium, neptunium, and plutonium in Example 2 of the present invention. Radiometric spectrum; Figure 3 The activated product uranium obtained in Example 2 of this invention. Radiometric spectrum; Figure 4 The activated product neptunium obtained in Example 2 of this invention. Radiometric spectrum; Figure 5 The activated product americium obtained in Example 2 of this invention. Radiometric spectrum; Figure 6 The activated product plutonium obtained in Example 2 of this invention. Radiometric spectrum.

[0020] The attached figures are labeled as follows: 1. Storage tank for radioactive solution containing americium, uranium, neptunium, and plutonium; 2. Washing solution storage tank; 3. Leaching solution storage tank; 4. First-stage desorption solution storage tank for uranium; 5. Desorption solution storage tank for americium and plutonium; 6. Leaching solution storage tank for neptunium; 7. Desorption solution storage tank for neptunium; 8. First-stage leaching solution storage tank for uranium; 9. Second-stage leaching solution storage tank for uranium; 10. Third-stage leaching solution storage tank for uranium; 11. 12. Second-stage desorption liquid storage tank for uranium; 13. First-stage eluent storage tank for americium; 14. Second-stage eluent storage tank for americium; 15. First-stage eluent storage tank for plutonium; 16. Second-stage eluent storage tank for plutonium; 17. First-stage desorption liquid storage tank for plutonium; 18. Third-stage eluent storage tank for plutonium; 19. Second-stage desorption liquid storage tank for plutonium. 20. TBP chromatography column, 21. First DN chromatography column, 22. First P 204 Or HDEHP or LN chromatography column, 23. DAAP or UTEVA chromatography column, 24. Second P 204 Or HDEHP or LN chromatography column, 25. TRU or RE chromatography column, 26. Second DN chromatography column; 27. Uranium product collector; 28. Neptunium product collector; 29. ​​Americium product collector; 30. Plutonium product collector; 31. Waste liquid collector; 40. Transfer pump; 41. Valve. Detailed Implementation

[0021] The present invention will now be described in further detail with reference to the accompanying drawings and specific embodiments.

[0022] Example 1 like Figure 1 As shown, a separation device for the activated product americium-uranium-plutonium (APU) is used for separating radioactive solutions containing APU and Plutonium. It includes a storage tank unit, a chromatography separation unit, a waste liquid collector 31, and a product collection unit. These units and devices are connected by pipelines, preferably silicone tubing. Corresponding valves 41 and a transfer pump 40 are installed in the pipelines. Valve 41 is a solenoid valve, and transfer pump 40 is a peristaltic pump. This allows for automatic control of the separation process via microcomputer control of the solenoid valve and peristaltic pump, reducing the impact of radioactive nuclide radiation on the human body and lowering the labor intensity of personnel. The peristaltic pump uses a flexible tube compression method to deliver the separation liquid, and the flow rate of the liquid is controlled by the rotation speed of the peristaltic pump.

[0023] The storage tank unit includes: 1. A storage tank containing americium, uranium, neptunium, and plutonium radioactive solution; 2. A washing solution storage tank; 3. A leaching solution storage tank; 4. A uranium first-stage desorption solution storage tank; 5. Americium-plutonium desorption solution storage tank; 6. Neptunium leaching solution storage tank; 7. A uranium first-stage leaching solution storage tank; 8. A uranium second-stage leaching solution storage tank; 9. A uranium third-stage leaching solution storage tank; 10. A uranium second-stage desorption solution storage tank; 11. Americium... The first-stage eluent storage tank 12, the second-stage eluent storage tank 13 of americium, the desorption tank 14 of americium, the first-stage eluent storage tank 15 of plutonium, the second-stage eluent storage tank 16 of plutonium, the first-stage desorption tank 17 of plutonium, the third-stage eluent storage tank 18 of plutonium, and the second-stage desorption tank 19 of plutonium are all connected to the corresponding color layer adsorption column via valves and pumps, and each storage tank performs a different function. The chromatography separation unit includes a TBP chromatography adsorption column 20, a first DN chromatography adsorption column 21, and a first P... 204 Or HDEHP or LN chromatography column 22, DAAP or UTEVA chromatography column 23, second P 204 Or HDEHP or LN chromatography column 24, TRU or RE chromatography column 25, second DN chromatography column 26.

[0024] The product collection unit includes a uranium product collector 27, a neptunium product collector 28, an americium product collector 29, and a plutonium product collector 30.

[0025] The connection relationship between the storage tank and the chromatography column is as follows: 1. Americium-uranium-neptunium-plutonium radioactive solution storage tank; 2. Washing solution storage tank; 3. Leaching solution storage tank; 4. Uranium first-stage desorption solution storage tank; 5. Americium-plutonium desorption solution storage tank; 6. Neptunium desorption solution storage tank; 7. Uranium first-stage leaching solution storage tank; 8. Uranium second-stage leaching solution storage tank; 9. Uranium third-stage leaching solution storage tank; 10. Uranium second-stage... The following tanks are arranged side-by-side at the top: desorption liquid storage tank 11, americium first-stage eluent storage tank 12, americium second-stage eluent storage tank 13, americium desorption liquid storage tank 14, plutonium first-stage eluent storage tank 15, plutonium second-stage eluent storage tank 16, plutonium first-stage desorption liquid storage tank 17, plutonium third-stage eluent storage tank 18, and plutonium second-stage desorption liquid storage tank 19. The outlets of each tank are connected to the corresponding inlets of the transfer pump 40 via valve 41. The corresponding outlets of the transfer pump 40 are connected to the TBP chromatograph adsorption column 20, the first DN chromatograph adsorption column 21, the TRU or RE chromatograph adsorption column 25, and the first P... 204The feed inlets of HDEHP or LN chromatographic adsorption column 22, DAAP or UTEVA chromatographic adsorption column 23, and the second DN chromatographic adsorption column 26 are connected; the discharge outlet of TBP chromatographic adsorption column 20 is connected to the feed inlet of uranium product collector 27 and waste liquid collector 31 via valve 41; the discharge outlet of the first DN chromatographic adsorption column 21 is connected to the bottom of the first-stage uranium eluent storage tank 8, the waste liquid collector 31, the feed inlet of TRU or RE chromatographic adsorption column 25, and the bottom of the first-stage americium eluent storage tank 12 via valve 41; the first P 204 The outlet of the HDEHP or LN chromatographic adsorption column 22 is connected via valve 41 to the bottom of the waste liquid collector 31, the americium product collector 29, and the first-stage plutonium leaching solution storage tank 15, respectively; the outlet of the DAAP or UTEVA chromatographic adsorption column 23 is connected via valve 41 to the inlet of the waste liquid collector 31 and the second DN chromatographic adsorption column 26, respectively; the second P 204 The outlet of the HDEHP or LN chromogenic adsorption column 24 is connected to the neptunium product collector 28; the outlet of the TRU or RE chromogenic adsorption column 25 is connected to the second P through valve 41. 204 The feed inlet of the HDEHP or LN chromatographic adsorption column 24 is connected to the waste liquid collector 31; the discharge outlet of the second DN chromatographic adsorption column is connected to the waste liquid collector 31 and the plutonium product collector 30 respectively through valve 41.

[0026] A method for separating the activation product americium-uranium-neptunium-plutonium, comprising the following steps: Step 1, Preparation before separation: A radioactive sample containing the activated product americium-neptunium-plutonium was dissolved in acid, sodium nitrite was added, and the mixture was heated to 70°C–100°C and maintained for 15 minutes. The solution was then allowed to cool naturally to room temperature to prepare an aqueous radioactive solution containing americium-neptunium-plutonium. The acid was dissolved in water to form an aqueous washing solution, an aqueous rinsing solution, and an aqueous desorption solution. The acid used was nitric acid, hydrochloric acid, hydrofluoric acid, diethylenetriaminepentaacetic acid, lactic acid, or a combination of these acids, with a concentration of 0.01–15 mol / L. TBP, DN, and P were then added. 204 Alternatively, HDEHP or LN, DAAP or UTEVA, TRU or RE can be packed into the chromogenic adsorption column respectively.

[0027] The first DN chromatography column is used to separate Np from U, Am, Pu, Nd, Ce, La, and Zr; to separate U from Am, Pu, Nd, Ce, La, Zr, Ba, Nb, Mo, Tc, Te, I, and Ru; and to separate Am and Pu from Ce, La, Ba, Nb, Mo, Tc, Te, I, and Ru. The TBP chromatography column is used for further separation of U from Np, Am, Pu, Nd, Ce, La, Zr, Ba, Nb, Mo, Tc, Te, I, and Ru. The TRU or RE chromatography column and the second P...204 HDEHP or LN chromatography columns are used to further separate Np from U, Am, Pu, Nd, Ce, La, Zr, Ba, Nb, Mo, Tc, Te, I, and Ru; the first P 204 HDEHP or LN chromatography columns are used to separate Pu from Am and Nd, Am from Nd, Zr and Nb, and Am from Ce, La, Ba, Mo, Tc, Te, I, Ru, Np and U; DAAP or UTEVA chromatography columns and second DN chromatography columns are used to separate Pu from Zr, and Pu from Nb, Np, Nd, Ce, La, Ba, Mo, Tc, Te, I and Ru.

[0028] Step 2: Using a peristaltic pump and a solenoid valve, the radioactive solution containing americium-neptunium-plutonium is sequentially passed through the first DN chromatographic adsorption column 21 and the TRU or RE chromatographic adsorption column 25 for separation and adsorption, and the effluent is collected as waste liquid. Americium, uranium, neptunium, and plutonium are adsorbed on different chromatographic columns; specifically, americium, uranium, and plutonium are adsorbed on the first DN chromatographic column 21, and neptunium is adsorbed on the TRU or RE chromatographic column 25.

[0029] Step 3: Using a peristaltic pump and a solenoid valve to select the washing liquid, the washing liquid is sequentially passed through the first DN chromatographic adsorption column 21 and the TRU or RE chromatographic adsorption column 25 for washing, and the outflow is collected as waste liquid. Step 4: Using a peristaltic pump and a solenoid valve, the neptunium eluent is further purified by passing it through a TRU or RE chromatography adsorption column 25, and the effluent is collected as waste liquid. Step 5: Using a peristaltic pump and a solenoid valve, the eluent is passed through the first DN chromatographic adsorption column 21 for rinsing, and the effluent is collected as waste liquid; the first-stage desorption liquid for uranium desorbs uranium through the first DN chromatographic adsorption column 21, and the effluent enters the first-stage eluent storage tank for uranium; the desorption liquid for americium-plutonium desorbs americium-plutonium through the first DN chromatographic adsorption column 21, and the effluent enters the first-stage eluent storage tank for americium. Step 6: Using a peristaltic pump and a solenoid valve, the first-stage uranium eluent, the second-stage uranium eluent, and the third-stage uranium eluent are sequentially passed through a TBP chromatography column 20 to purify the uranium. The effluent is collected as waste liquid. Step 7: Using a peristaltic pump and a solenoid valve, the first-stage eluent of americium is simultaneously passed through the first P... 204 Americium was purified using either HDEHP or LN chromatography column 22, with the effluent entering the first-stage eluent storage tank for plutonium; the second-stage eluent for americium passed through the first P... 204Americium was further purified using an HDEHP or LN chromatography column 22, and the effluent was collected as waste liquid. Step 8: Using a peristaltic pump and a solenoid valve, the first-stage and second-stage plutonium eluents are sequentially passed through a DAAP or UTEVA chromatography column 23 for plutonium purification, with the effluent collected as waste. The first-stage plutonium desorption solution is then sequentially passed through a DAAP or UTEVA chromatography column 23 and a second DN chromatography column 26 for plutonium desorption and resorption, with the effluent collected as waste. The third-stage plutonium eluent is further purified by passing through a second DN chromatography column 26, with the effluent collected as waste. Step 9: Using a peristaltic pump and a solenoid valve, the second-stage desorption solution of uranium is passed through the TBP chromatographic adsorption column 20; simultaneously, the desorption solution of neptunium is passed sequentially through the TRU or RE chromatographic adsorption column 25 and the second P... 204 Alternatively, an HDEHP or LN chromatography column 24 can be used; simultaneously, the americium desorption solution is passed through a first P... 204 The plutonium is either adsorbed onto an HDEHP or LN chromatographic column 22; simultaneously, the second-stage desorption solution is passed through a second DN chromatographic column 26. The effluent is collected in uranium product collector 27, neptunium product collector 28, americium product collector 29, and plutonium product collector 30, respectively, representing the products of uranium, neptunium, americium, and plutonium. Radioactive measurement source.

[0030] In the above method, americium is a component of... 241 Am(n, ) 242 Am、 241 Am(n,2n) 240 Various americium isotopes of the Am reaction products, wherein the uranium is a composite of... 238 U(n,2n) 237 Various uranium isotopes of the U reaction products, wherein neptunium is a component of 238 U(n, ) 239 U / 239 Various neptunium isotopes of the Np reaction products, wherein the plutonium is a component of 238 Pu(n,2n) 237 Pu、 239 Pu(n,3n) 237 Various plutonium isotopes of the Pu reaction products.

[0031] Example 2 A radioactive sample containing the activated product americium-neptunium-plutonium was dissolved in 10 mL of 3 mol / L HNO3, sodium nitrite was added, and the solution was heated to 70℃~100℃ and maintained for 15 minutes. The solution was then allowed to cool naturally to room temperature to prepare an aqueous radioactive solution containing americium-neptunium-plutonium. This solution was placed in storage tank 1. Radioactive energy spectrum such as Figure 2 As shown.

[0032] The flow rate of the americium-containing neptunium-plutonium solution was controlled at 1 mL / min, allowing the radioactive solution to pass sequentially through a first DN chromatographic adsorption column 21 and a TRU chromatographic adsorption column for separation and adsorption. The first DN chromatographic adsorption column 21 is... 8.9×64mm DN chromatography column, TRU chromatography adsorption column is The effluent from the 8.9×64mm TRU chromatography column was collected in waste liquid collector 31.

[0033] 30 mL of 3 mol / L HNO3 solution in the washing liquid storage tank 2 is passed through the first DN chromatography column 21 and the TRU chromatography column in sequence at a flow rate of 1.5 mL / min. The effluent is collected in the waste liquid collector 31.

[0034] 20 mL of 3 mol / L HNO3 solution was added to the neptunium eluent storage tank 6 at a flow rate of 1.5 mL / min and eluent was passed through a TRU chromatography adsorption column. The eluent was collected in the waste liquid collector 31.

[0035] 30 mL of 2.75 mol / L HCl solution from eluent storage tank 3 is passed through the first DN chromatographic adsorption column 21 at a flow rate of 1.5 mL / min, and the effluent is collected in waste liquid collector 31. 20 mL of 0.1 mol / L HNO3 solution from the first-stage desorption solution storage tank 4 is passed through the first DN chromatographic adsorption column 21 for desorption, and the effluent enters the first-stage eluent storage tank 8 for uranium, which is pre-filled with 5 mL of 15 mol / L HNO3 solution. 10 mL of 0.05 mol / L DTPA-1 mol / L lactic acid (pH 3.5) solution from the americium-plutonium desorption solution storage tank 5 is passed through the first DN chromatographic adsorption column 21 to desorb americium-plutonium, and the effluent enters the first-stage eluent storage tank 12 for americium, which is pre-filled with 0.4 mL of americium-plutonium solution. 10 mol / L HNO3 solution; Uranium was further purified by sequentially passing 25 mL of 3 mol / L HNO3 solution from the first-stage eluent storage tank 8, 15 mL of 3 mol / L HNO3 solution from the second-stage eluent storage tank 9, and 8 mL of 4 mol / L HCl solution from the third-stage eluent storage tank 10, at a flow rate of 1 mL / min, through a TBP chromatography column 20. An 8.9×64mm TBP chromatography column was used, and the effluent was collected in waste liquid collector 31. Simultaneously, 10.4 mL of 0.05 mol / L DTPA-1 mol / L lactic acid (pH 1.0) solution from the first-stage eluent storage tank 12 of americium is added at a controlled flow rate of 1 mL / min through the first P... 204 Further purification of americium was achieved using a chromatography column, in which the first P... 204 Chromatographic adsorption column is 5×200mm P 204 The effluent from the chromatography column enters the first-stage eluent storage tank 15 for plutonium, which is pre-filled with 6.8 mL of 15 mol / L HNO3 solution. 25 mL of 0.1 mol / L HNO3 solution from the second-stage eluent storage tank 13 for americium is then passed through the first P... 204 The americium was further purified by a chromatography adsorption column, and the effluent was collected in waste liquid collector 31; 17.2 mL of a 6 mol / L HNO3 solution containing 0.03 mol / L DTPA-0.6 mol / L lactic acid from the first-stage eluent storage tank 15, and 25 mL of a 6 mol / L HNO3 solution from the second-stage eluent storage tank 16, were sequentially passed through a DAAP chromatography column for further purification of plutonium, controlled at a flow rate of 1 mL / min. The DAAP chromatography column was [details omitted]. An 8.9×64 mm DAAP chromatography column was used, and the effluent was collected in waste collector 31. 20 mL of a 1 mol / L HNO3-0.2 mol / L ACB solution from the first-stage desorption buffer storage tank 17 was passed sequentially through a DAAP chromatography column and a second DN chromatography column 26 for desorption and resorption of plutonium. The second DN chromatography column 26 was an 8.9×64 mm DN chromatography column, and the effluent was collected in waste collector 31. 30 mL of a 0.1 mol / L HNO3 solution from the third-stage eluent storage tank 18 was passed through the second DN chromatography column 26 for further purification of plutonium, and the effluent was collected in waste collector 31. 10 mL of 0.1 mol / L HNO3 solution from the second-stage desorption solution storage tank 11 for uranium is passed through a TBP chromatography column 20 at a flow rate of 1 mL / min. Simultaneously, 30 mL of 0.05 mol / L HNO3 solution from the neptunium desorption solution storage tank 7 is passed sequentially through a TRU chromatography column and a second TBP column. 204 Chromatographic adsorption column, wherein the second P 204 Chromatographic adsorption column is P 8.9×64mm 204 Chromatographic column; simultaneously, 25 mL of 0.05 mol / L DTPA-1 mol / L lactic acid (pH 3.0) solution from the americium desorption solution storage tank 14 is passed through the first P... 204A chromatographic adsorption column was used; simultaneously, 10 mL of 0.1 mol / L HCl-0.1 mol / L HF solution from the second-stage desorption tank 19 for plutonium was passed through the second DN chromatographic adsorption column 26. The effluent was collected in uranium product collector 27, neptunium product collector 28, americium product collector 29, and plutonium product collector 30, respectively, representing the fractions of uranium, neptunium, americium, and plutonium. Radioactive measurement source.

[0036] The experimentally obtained uranium, neptunium, americium, and plutonium The radiometric energy spectrum is as follows: Figure 3 , Figure 4 , Figure 5 , Figure 6 As shown, the recoveries of uranium, neptunium, americium, and plutonium were 83.2%, 80.6%, 92.1%, and 86.4%, respectively. The decontamination factors among uranium, neptunium, americium, and plutonium were within 10... 4 ~10 6 The decontamination factor for fission products is 10. 4 ~10 6 .

[0037] Example 3 In Example 2, P 204 The chromatography column was replaced with an LN chromatography column, and the DAAP chromatography column was replaced with a UTEVA chromatography column. The separation process of Example 1 was repeated to obtain uranium, neptunium, americium, and plutonium. As shown in Table 1, the recovery rates of uranium, neptunium, americium, and plutonium from the radioactive measurement sources were 82.1%, 81.4%, 93.0%, and 85.1%, respectively, with decontamination factors between them ranging from 10 to 10. 4 ~10 6 The decontamination factor for fission products is 10. 4 ~10 6 .

[0038] Table 1. Recovery rate and decontamination factor analysis Note: ">" indicates the lower limit assigned when no detection is detected.

[0039] The above description is merely a preferred embodiment of the present invention and is not intended to limit the present invention in any way. Any simple modifications, alterations, and equivalent changes made to the above embodiments based on the technical essence of the present invention shall still fall within the protection scope of the present invention.

Claims

1. An apparatus for separating activated products americium, uranium, neptunium, plutonium, characterized in that, The device comprises a liquid storage tank unit, a chromatographic separation unit, a waste liquid collector (31), a product collection unit, a delivery pump (40) and a valve (41); The liquid in the liquid storage tank unit enters the chromatographic separation unit through the delivery pump (40), and the liquid flowing out of the chromatographic separation unit enters the product collection unit or the waste liquid collector (31); the liquid flows through pipelines, and the valve (41) is arranged on the pipeline through which the liquid flows through each component; The liquid storage tank unit, the delivery pump (40), the chromatographic separation unit and the product collection unit are sequentially arranged from top to bottom; the waste liquid collector (31) and the product collection unit are placed on the same horizontal plane and are located at the lowermost end; The chromatographic separation unit is used for separating activated products.

2. The apparatus for separating the activation products americium, neptunium, plutonium from uranium according to claim 1, characterized in that The liquid storage tank unit comprises an americium-uranium-neptunium-plutonium radioactive solution storage tank (1), a washing liquid storage tank (2), a leaching liquid storage tank (3), a first-stage uranium desorption liquid storage tank (4), an americium-plutonium desorption liquid storage tank (5), a neptunium leaching liquid storage tank (6), a neptunium desorption liquid storage tank (7), a first-stage uranium leaching liquid storage tank (8), a second-stage uranium leaching liquid storage tank (9), a third-stage uranium leaching liquid storage tank (10), a second-stage uranium desorption liquid storage tank (11), a first-stage americium leaching liquid storage tank (12), a second-stage americium leaching liquid storage tank (13), an americium desorption liquid storage tank (14), a first-stage plutonium leaching liquid storage tank (15), a second-stage plutonium leaching liquid storage tank (16), a first-stage plutonium desorption liquid storage tank (17), a third-stage plutonium leaching liquid storage tank (18) and a second-stage plutonium desorption liquid storage tank (19) placed on the same horizontal plane; each storage tank of the liquid storage tank unit is connected with a corresponding chromatographic adsorption column through the valve (41) and the delivery pump (40); The chromatographic separation unit comprises a TBP chromatographic adsorption column (20), a first DN chromatographic adsorption column (21), a first P204 or HDEHP or LN chromatographic adsorption column (22), a DAAP or UTEVA chromatographic adsorption column (23), a second P204 or HDEHP or LN chromatographic adsorption column (24), a TRU or RE chromatographic adsorption column (25) and a second DN chromatographic adsorption column (26); The first DN chromatographic adsorption column is used for separating Np from U, Am, Pu, Nd, Ce, La and Zr, separating U from Am, Pu, Nd, Ce, La, Zr, Ba, Nb, Mo, Tc, Te, I and Ru, and separating Am and Pu from Ce, La, Ba, Nb, Mo, Tc, Te, I and Ru; TBP color column for further separation of U from Np, Am, Pu, Nd, Ce, La, Zr, Ba, Nb, Mo, Tc, Te, I, Ru; TRU or RE color column and second P 204 or HDEHP or LN color column for further separation of Np from U, Am, Pu, Nd, Ce, La, Zr, Ba, Nb, Mo, Tc, Te, I, Ru; first P 204 or HDEHP or LN color column for separation of Pu from Am, Nd, separation of Am from Nd, Zr, Nb and further separation of Am from Ce, La, Ba, Mo, Tc, Te, I, Ru, Np, U; DAAP or UTEVA color column and second DN color column for separation of Pu from Zr and further separation of Pu from Nb, Np, Nd, Ce, La, Ba, Mo, Tc, Te, I, Ru; The product collection unit comprises a uranium product collector (27), a neptunium product collector (28), an americium product collector (29) and a plutonium product collector (30). The connection relationship between each reservoir of the reservoir unit and the corresponding chromatographic column is as follows: the outlet of the reservoir for storing the solution containing americium, uranium and plutonium is connected to the corresponding inlet of the valve (41) and the delivery pump (40); the corresponding outlet of the delivery pump (40) is connected to the inlet of the TBP chromatographic column (20), the first DN chromatographic column (21), the TRU or RE chromatographic column (25), the first P204 or HDEHP or LN chromatographic column (22), the DAAP or UTEVA chromatographic column (23), and the second DN chromatographic column (26) through the valve (41); the outlet of the TBP chromatographic column (20) is connected to the inlet of the uranium product collector (27) and the waste liquid collector (31) through the valve (41); the outlet of the first DN chromatographic column (21) is connected to the bottom of the first-stage uranium elution liquid reservoir (8), the waste liquid collector (31), the inlet of the TRU or RE chromatographic column (25), and the bottom of the first-stage americium elution liquid reservoir (12) through the valve (41); the outlet of the first P204 or HDEHP or LN chromatographic column (22) is connected to the waste liquid collector (31), the plutonium product collector (30), and the bottom of the first-stage plutonium elution liquid reservoir (15) through the valve (41); the outlet of the DAAP or UTEVA chromatographic column (23) is connected to the waste liquid collector (31) and the inlet of the second DN chromatographic column (26) through the valve (41); the outlet of the second P204 or HDEHP or LN chromatographic column (24) is connected to the neptunium product collector (28); the outlet of the TRU or RE chromatographic column (25) is connected to the inlet of the second P204 or HDEHP or LN chromatographic column (24) and the waste liquid collector (31) through the valve (41); and the outlet of the second DN chromatographic column is connected to the waste liquid collector (31) and the plutonium product collector (30) through the valve (41).

3. The apparatus for separating actinides from plutonium and americium according to claim 1, wherein The microcomputer is used to control the valve (41) and the delivery pump (40).

4. The apparatus for separating actinides from plutonium according to claim 1, wherein The valve (41) is an electromagnetic valve, and the delivery pump (40) is a peristaltic pump. The peristaltic pump uses a hose extrusion method to deliver the separation liquid, and the flow rate of the liquid is controlled by the rotation speed of the peristaltic pump.

5. The apparatus for separating actinides from plutonium according to claim 1, wherein The liquid flow pipe is a silica gel pipe.

6. A method for separating activated products americium, uranium, neptunium and plutonium, using the separation device according to any one of claims 1 to 5, characterized in that, The method comprises the following steps: Step 1, solution and column preparation: The radioactive sample containing activated products of americium, uranium and neptunium plutonium is dissolved in acid, sodium nitrite is added, heated to 70-100 DEG C, maintained for a certain time, and naturally cooled to room temperature to prepare an aqueous radioactive solution containing americium, uranium and neptunium plutonium; the acid is dissolved in water respectively to form a washing liquid, an elution liquid and a desorption liquid; The prepared aqueous radioactive solution containing americium, uranium and neptunium plutonium, the washing liquid, the elution liquid and the desorption liquid are respectively filled into the corresponding liquid storage tanks of the liquid storage tank unit; TBP, DN, P 204 or HDEHP or LN, DAAP or UTEVA, TRU or RE, respectively, packed into a color layer adsorption column; Step 2, adsorption of americium, uranium and neptunium: The aqueous radioactive solution containing americium, uranium and neptunium is sequentially passed through the first DN column (21) and the TRU or RE column (25) for separation and adsorption, and the effluent is collected in the waste liquid collector (31); The uranium and plutonium are adsorbed in the first DN column, and the neptunium is adsorbed in the TRU or RE column; Step 3, washing: The washing liquid is sequentially passed through the first DN column (21) and the TRU or RE column (25) for washing, and the effluent is collected in the waste liquid collector (31); Step 4, separation and purification of neptunium: The elution liquid of neptunium is passed through the TRU or RE column (25) for purification of neptunium, and the effluent is collected in the waste liquid collector (31); Step 5, elution of uranium and plutonium: The elution liquid is passed through the first DN column (21) for elution, and the effluent is collected in the waste liquid collector (31); The first-stage desorption liquid of uranium is passed through the first DN column (21) for desorption of uranium, and the effluent enters the first-stage elution liquid storage tank 4 of uranium; The desorption liquid of plutonium is passed through the first DN column (21) for desorption of plutonium, and the effluent enters the first-stage elution liquid storage tank (12) of americium; Step 6, separation and purification of uranium: The first-stage elution liquid of uranium, the second-stage elution liquid of uranium and the third-stage elution liquid of uranium are sequentially passed through the TBP column (20) for purification of uranium, and the effluent is collected in the waste liquid collector (31); Step 7, separation and purification of americium: The first-stage elution liquid of americium is passed through the first P204 or HDEHP or LN column (22) for purification of americium, and the effluent enters the first-stage elution liquid storage tank of plutonium; The second-stage elution liquid of americium is passed through the first P204 or HDEHP or LN column (22) for further purification of americium, and the effluent is collected in the waste liquid collector (31); Step 8, separation and purification of plutonium: The first-stage elution liquid of plutonium and the second-stage elution liquid of plutonium are sequentially passed through the DAAP or UTEVA column (23) for purification of plutonium, and the effluent is collected in the waste liquid collector (31); The first-stage desorption liquid of plutonium is sequentially passed through the DAAP or UTEVA column (23) and the second DN column (26) for desorption and re-adsorption of plutonium, and the effluent is collected in the waste liquid collector (31); The third-stage elution liquid of plutonium is passed through the second DN column (26) for further purification of plutonium, and the effluent is collected in the waste liquid collector (31); Step 9, desorption: The second-stage desorption liquid of uranium is passed through the TBP column (20), and the effluent is collected in the uranium product collector (27); The desorption solution of neptunium passes through the TRU or RE color adsorption column (25) and the second P204 or HDEHP or LN color adsorption column (24) in turn, and the effluent is collected in the neptunium product collector (28); The desorption solution of americium passes through the first P204 or HDEHP or LN color adsorption column (22), and the effluent is collected in the americium product collector (29); The second-stage desorption solution of plutonium passes through the second DN color adsorption column (26), and the effluent is collected in the plutonium product collector (30).

7. The method of claim 6, wherein the activation product is americium-241. In the step 1, The radioactive sample containing the activated product of americium-uranium-neptunium-plutonium is dissolved in acid, sodium nitrite is added, and heated for 15 minutes; The acid is nitric acid, hydrochloric acid, hydrofluoric acid, diethylenetriamine pentaacetic acid, lactic acid, or a combination of the above acids, and the concentration of the acid is 0.01-15 mol / L.

8. The method of claim 6, wherein the activation product is americium-241. The radioactive sample containing the activation products americium, neptunium, plutonium of the actinide series is a non-volatile radionuclide produced after neutron irradiation of a mixed nuclear fuel of actinides.

9. The separation method of the activated product of americium-uranium-neptunium-plutonium according to claim 6, characterized in that, The acid for preparing the aqueous radioactive solution containing americium-uranium-neptunium-plutonium is 2-4 mol / L HNO3, the washing solution is 2-4 mol / L HNO3 solution, and the elution solution is 2-4 mol / L HCl solution; The first-stage desorption solution of uranium is 0.01-0.2 mol / L HNO3 solution; The desorption solution of americium-plutonium is 0.5-1.5 mol / L lactic acid solution containing 0.04-0.08 mol / L DTPA, and the pH value of the desorption solution of americium-plutonium is pH 3.0-3.5; The elution solution of neptunium is 2-4 mol / L HNO3 solution, and the desorption solution of neptunium is 0.01-0.1 mol / L HNO3 solution; The first-stage elution solution of uranium is 2-5 mol / L HNO3 solution, the second-stage elution solution of uranium is 2-5 mol / L HNO3 solution, the third-stage elution solution of uranium is 3-5 mol / L HCl solution, and the second-stage desorption solution of uranium is 0.01-0.15 mol / L HNO3 solution; The first-stage elution solution of americium is 0.5-1.5 mol / L lactic acid solution containing 0.04-0.08 mol / L DTPA, the pH value of the first-stage elution solution of americium is pH 1.0, the second-stage elution solution of americium is 0.01-0.15 mol / L HNO3 solution, the desorption solution of americium is 0.5-1.5 mol / L lactic acid solution containing 0.04-0.08 mol / L DTPA, and the pH value of the desorption solution of americium is pH 3.0; The first-stage elution solution of plutonium is 4-8 mol / L HNO3 solution containing 0.04-0.08 mol / L DTPA-0.5-1.5 mol / L lactic acid, the second-stage elution solution of plutonium is 4-8 mol / L HNO3 solution, the first-stage desorption solution of plutonium is 0.5-3 mol / L HNO3 solution containing 0.01-0.4 mol / L ACB, the third-stage elution solution of plutonium is 0.05-0.3 mol / L HNO3 solution, and the second-stage desorption solution of plutonium is 0.05-0.4 mol / L HCl solution containing 0.05-0.3 mol / L HF.

10. The method of claim 6, wherein the activation product is americium-241, wherein the americium-241 is separated from the plutonium-239. the americium is a variety of americium isotopes comprising 241 Am(n, ) 242 Am, 241 Am(n,2n) 240 Am reaction products, the uranium is a variety of uranium isotopes comprising 238 U(n,2n) 237 U reaction products, the neptunium is a variety of neptunium isotopes comprising 238 U(n, ) 239 U / 239 Np reaction products, the plutonium is a variety of plutonium isotopes comprising 238 Pu(n,2n) 237 Pu, 239 Pu(n,3n) 237 Pu reaction products.

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