KR20050090199A - Automatic radionuclide separation system and automatic purification method of plutonium (pu) using this system - Google Patents

Abstract

The present invention is installed in the sample storage box 10, the front of the sample storage box 10, the sample selection valve 30 for sample solution selection injection for injecting a sample by one and the sample solution selection injection Three-way solenoid valves (SV1, SV2, SV3, SV4) 40 connected to the sample selection valve 30, and a reagent container connected to one side of the three-way solenoid valves (SV1, SV2, SV3, SV4) 40 ( 20), two tubing pumps and pump speed regulators (P1, P2) 50 installed in front of the three-way solenoid valves (SV1, SV2, SV3, SV4) 40 and the two tubing pumps And two 2-way-6 port valves (TW1, TW2) (60) connected to and installed on the front of the pump speed regulator (P1, P2) (50), and the 2-way-6 port valves (TW1) (60). Is connected to one side of the radionuclide separation resin support column 70 for selectively controlling the injection of the sample and the solvent, and the two-way-6 port valve ( TW2) (60) connected to the eluent collection box 90, the two 2-way-6 port valves (TW1, TW2) (60) connected to the other side of the waste collection container 100, and operating and separating the It relates to a radionuclide automatic separation device composed of a device operating program (110) for inputting a procedure and a plutonium (Pu) automatic separation method using the same.

Description

Automatic radionuclide separation device and automatic plutonium separation method {Automatic radionuclide separation system and automatic purification method of Plutonium (Pu) using this system}

The present invention provides an automatic radionuclide separation device developed to increase the efficiency of analytical work by saving time and manpower required by automating the continuous chemical separation of a plurality of samples during chemical pure separation of radionuclides present in environmental samples. Plutonium (Pu) automatic separation method using the same.

The present invention relates to radionuclides in environmental samples (plutonium (Pu), neptunium (Np), uranium (U), thorium (Th), technet) for environmental monitoring around nuclear facilities or for the study of the behavior of radionuclides in the environment. As a device for automating the chemical pure separation of calcium (Tc), americium (Am), curium (Cm)), it belongs to the field of automatic radionuclide separation technology.

In the conventional case, a method of filling a glass column with a resin for radionuclide separation and sequentially injecting a sample and a solution required for pure water separation into a glass column through a separating nipple was used. Therefore, the analyst had to replace the sample, eluent, and eluent by hand, and the injection speed of each solution was controlled by using the cock of the separator. This separation method was inferior in reproducibility of separation efficiency due to analytical work skill differences, inconsistent solution amounts, and injection speeds. Since the injection speed of the solution using the cock of the separatory noodle uses the potential energy of the solutions filled in the separatory nipple, the injection speed gradually decreases with time, and the separation operation is very inconvenient because the adjustment of the injection speed by the cock adjustment is inaccurate. In addition, there is a possibility that other elements can be introduced from the outside because it is spatially separated, there is a risk of exposure to harmful gases released from the elution and eluent used during the separation process.

The Intergrated Liquid Handling System (PerpLab), which is commercially available from Thermo electron, is composed of a tubing pump, a pinch valve and a 2-way-6 port valve as a solution injection device. It cannot be processed, the solution injection flow path is limited, all the solutions required for separation cannot be supplied through the valve, and the solution transfer speed cannot be controlled during automatic separation. In addition, the complete inconvenience of the entire chemical separation process could not be realized due to the inconvenience of not being able to use the operating program alone without other aids.

In addition, for example, the Republic of Korea Utility Model Registration No. 20-0262106 is a radioactive cladding automatic collection device for sampling the radioactive waste resin and waste filter of the nuclear power plant, to collect the radioactive corrosion products For example, the ion column and the filter holder connected in series, the inline radiation analyzer mounted inside the ion column by drilling to a thickness that ignores the shielding effect, and the sample connected to the inline radiation analyzer to the desired radiation dose setting values The radioactive cladding device is described, including a solenoid valve for collecting

Korean Patent Laid-Open Publication No. 2003-0019932 discloses a method for treating various compounds in supercritical water, wherein ruthenium oxide is used as a catalyst in the supercritical water to convert a highly differentiated compound into a gas and simultaneously It can be seen that a method of treating low level radioactive waste is disclosed in which the attached radioactive metal is converted to an insoluble oxide, and then the radioactive metal, which is converted into an insoluble oxide, is vitrified and disposed of.

It is a situation that does not solve the conventional problems as described above.

The present invention has developed a control and separation process input program for a separation device using a PC for solving the above problems and automation of separation, and to increase the efficiency and reproducibility of analysis by automating all separation processes. In other words, the quality of analysis is improved by reducing time and manpower loss by manual operation and increasing the reproducibility of separation compared to the conventional separation method. In addition, the lines of separation are connected to acid-resistant tubes from sample supply, injection of separation solution, final separation solution recovery, and waste solution recovery, so that chemical separation proceeds only within the tube to prevent leakage of harmful gases and inflow of other elements from the outside. The present invention has been made in an effort to provide a radionuclide automatic separation device and an automatic plutonium (Pu) automatic separation method using the same, which facilitate the safe handling of a sample that may be exposed to radiation such as high-level radioactive waste by remote control. It is a technical task.

In order to achieve the above object, the present invention has automated the chemical pure separation of radionuclides present in environmental samples using a solution transfer device and a control program, automatic radionuclide separation device capable of continuously separating a plurality of samples And it relates to a plutonium (Pu) automatic separation method using the same.

The present invention is installed in the sample storage box 10, the front of the sample storage box 10, a sample selection valve 30 for sample solution selection injection for selecting and injecting a sample one by one, and the sample solution selection injection Three-way solenoid valves (SV1, SV2, SV3, SV4) 40 connected to the sample selection valve 30, and a reagent container connected to one side of the three-way solenoid valves (SV1, SV2, SV3, SV4) 40 ( 20), two tubing pumps and pump speed regulators (P1, P2) 50 installed in front of the three-way solenoid valves (SV1, SV2, SV3, SV4) 40 and the two tubing pumps And two 2-way-6 port valves (TW1, TW2) 60 connected to and installed on the front of the pump speed regulator (P1, P2) 50, and the 2-way-6 port valves (TW1) (60). Is connected to one side of the radionuclide separation resin support column 70 for selectively controlling the injection of the sample and the solvent, and the two-way-6 port valve (T) W2) (60) connected to the eluent collection box (90), the two two-way six-port valve (TW1, TW2) (60) connected to the other side of the waste collection container 100, and operating and separating the It relates to a radionuclide automatic separation device composed of a device operating program 110 for inputting a procedure and an automatic separation method using the same.

In the present invention, all solution transfer paths are connected online by acid-resistant tubes for automation of separation, and two-way-6 ports operate independently of four three-way solenoid valves for various access of elution and eluents to the separation resin. The valves were placed in parallel or in series.

In order to prevent leakage of harmful gases and contamination of other elements from the outside, all of the solution supply, transfer and discharge were made by inserting a small hole into the container so that only PEEK tubing could be inserted in the lid of the container. Inter-part flow paths using acid-resistant PTFE tubing were sealed using PEEK nuts and Tefzel Ferrules. Acid-resistant Tygon®MH Peristaltic tubes were used for tubing pumps. Chemical separation was allowed to occur in the primary seal.

An operating program was developed to input signal input / output control and separation procedures for the control of each component of such a separation device and to automate the entire separation process into a PC. In order to solve the trouble of sample replacement, a sample selection valve and a final eluate collection valve are arranged at the front and the rear of the separator so that multiple samples can be separated continuously. It was. Polyether Ether Ketone (PEEK) and PTFE resistant to acid solution, except for flexible tubes used in tubing pumps to prevent component corrosion and device failure due to acid vapor, because the use of high concentration of acid solution is inevitable due to radionuclide characteristics. (Polytetra Fluoro Ethylene) valves, tubes and pumps were used.

In addition, when the device is not used, in order to open the flexible tube compressed by the cartridge of the tubing pump, it is possible to maintain the integrity of the flexible tube and the device by controlling the flow of the solution by connecting the eluent and the eluent with the 3-way valve. It was made. The pump tube relates to an automatic radionuclide separator using Tygon® MH for use in strong acids.

The present invention provides a solution storage box for supplying and recovering the solutions required for separation as shown in FIGS. 1 and 2, a solution transfer device for sequentially performing chemical separation by injecting the solution into the separation resin, and these devices. It consists of the PC part that controls and executes automation.

The solution container consists of a sample container for storing six samples, a reagent container for storing an eluent and an eluent, an eluent container for recovering the final eluate, and a waste container for collecting and storing the waste liquids. 5M nitric acid, 1M nitric acid, 9M hydrochloric acid and 5M hydrochloric acid are stored and supplied through different pipes.

The solution transfer device for chemical separation consists of a sample selection and eluate recovery valve, a tubing pump and pump speed regulator for transferring the separation solution, four three-way solenoid valves (40) and two two-way-6 ports providing various flow paths. It is comprised by the valve 60.

  The two two-way six-port valves (TW1, TW2) 60 are connected by PC control to two paths, such as 1-2, 3-4, 5-6 and 1-6, 2-3, 4-5, respectively. It can be operated by alternative replacement.

The tubing pump and the pump speed controller 50 were installed in two (P1, P2) so that each can be operated as needed.

All flow path connections were made of acid-resistant PTFE tubing, and only acid-resistant Tygon® HM tubing was used in the tubing pump section.

The three-way solenoid valve 40 is connected to four bidirectional connectors to securely block the flow of the solution when using the device cost to prevent the leakage of solution and gas to open the flexible tube of the device components and pump.

The present invention controlled the operation of all components by PC using RS-232 control communication and digital input / output PCI card, and the device operating program inputs and executes a check window (Test Mode) and a separation process for performance check of each component. It consists of execution mode for execution.

3 shows an inspection window and an execution window of the device operation program. In the inspection window, the components of the device and buttons for executing their operations are displayed so that each of the components can be inspected. I could see.

Two solution selectors (Sample Selector 1 and Vial Selector 2) were able to check six selection ports from one common inlet and installed a Home button for initialization of the solution selector.

For four three-way solenoid valves (SV1, SV2, SV3, SV4), two flow paths (On; 1-2, Off; 1-3) can be inspected using the On button. In the case of (TW Valve 1, TW Valve 2), the two port connection directions (A; [1-2, 3-4, 5-6], B: [2-3, 4-5, 6-1]) To be checked.

In the case of tubing pumps (Pump1 and Pump2), the On and Off buttons and the speed input window were configured to check the pump operation and speed. At this time, the speed of each input pump is set as the initial speed of the pump when the separation procedure is input.

Figure 4 shows a procedure input box (Procedure box) for inputting the operation of each step of the chemical separation process, the commands for the selection and operation of each component used at this time is shown in Table 1. Execution statement is configured to execute one operation per line, and the whole separation process is terminated by "TIME; 0" command. The input separation procedure contents can be copied and removed like normal texts for convenience of input, and the completed contents can be stored and managed as a file to create various separation procedures. In addition, the "!" Commands can be used to create comments.

The separation process is carried out by pressing the Start button. The progress bar and the progress rate are located below the window to determine the overall progress of the separation.In the execution mode main window, you can see the operation status of each component during the separation process. Each component and its operation state are composed of buttons that display color change. In addition, a stop button was installed to stop the separation process during the separation program.

0.5M hydrochloric acid (HCl) is used as a column washing solution as the initial injection solution in the separation phase, and also serves as an eluent to finally elute Pu to be separated into the final injection solution.

In the first process, the column washing process is a step of washing the resin once again to eliminate the influence of the previous sample during repeated use of the column, 0.5M hydrochloric acid completely removes the Pu remaining in the column.

The second step is to change the column to a composition suitable for Pu adsorption before the sample is injected into the atmosphere composition process. The 5M nitric acid (HNO ₃ ) is a nitric acid based composition of TEVA-Spec resin used for Pu separation using TEVA By converting, oxidation such as Pu can adsorb the tetravalent actinide element well. Therefore, when the sample solution is injected after flowing 5M nitric acid, oxidized tetravalent actinide elements including Pu contained in the sample solution may be adsorbed onto the resin.

The third step is to inject a sample, and inject only one desired sample into the sample liquid composed of 5M nitric acid using a sample selection valve, and the injected sample passes Pu contained in the sample by passing the resin through SV1 and SV3. It can adsorb | suck to resin. The solution passed through the resin is discharged into the waste collection vessel via a path such as 5M nitric acid.

The fourth process is

As a step of washing the resin, the tubes and resin passed through the sample contain a small amount of various elements contained in the sample, thus preventing the pure chemical separation of Pu. Therefore, in order to remove only other elements without losing Pu adsorbed on the resin, the washing process is performed through the same path as 5M nitric acid.

The fifth step is to remove other actinide elements that may be adsorbed to some resin during sample injection. Injecting 9M hydrochloric acid and 1M nitric acid, the flow path of the solution is the same as the sample injection route. 9M hydrochloric acid removes Th and 1M nitrate removes U. At this time, the loss of Pu adsorbed on the resin is very small and all used solutions are discharged to the waste collection container.

In the sixth process, a small amount of 0.5M hydrochloric acid is filled into the tube. In the case of Pu separation using a small amount of environmental sample, the Pu content is so small that when the final eluate is large, the concentration of Pu is dilute to present a very small amount in the environmental sample. It becomes very difficult to measure Pu. Measurement will not be possible with the instrument. Therefore, it is very important to minimize the final eluate.

In addition, TW1 and TW2 are shown in Figure A until 0.5M hydrochloric acid reaches TW2 as a method to remove small amount of solution in the tube space reaching TW2 in the resin to prevent the inflow of other elements. Was injected for a short time until 0.5M hydrochloric acid reached TW2 at the A position (1-2, 3-4, 5-6 connection). Therefore, the elution solution in this process is discharged to the waste collection container.

In the seventh process, the 0.5 M hydrochloric acid used in the seventh process is injected along the same route as the final separation (elute) step, but by changing TW2 to the B position (2-3, 4-5, 6-1 concatenation) It is a process to collect the eluate through the eluent collection valve to selectively collect.

Hereinafter, the present invention will be described through Examples.

Example

First process (preparation process)

RS-232 control communication and digital input / output PCI card are used to control the operation of all components with a PC. The instrument operating program enters and executes a check window (Test Mode) and a separation process for performance check of each component. It consists of an execution mode for execution, and a progress bar and a progress rate are placed under the window to grasp the overall progress of separation, and each of the execution mode main windows shows the operation status of each component during separation. After installing the button to display the components and their operation status by color change, and the stop button to stop the separation process while the separation program is in progress, press the start button on the automatic separation device. By,

First, 0.5 M hydrochloric acid in the reagent reservoir 20 is transferred to the 2-way-6 port valve (TW1) 60 through P2 of the tubing pump and the pump speed regulator 50 through the SV4 of the 3-way solo valve 40. Through the 5-6 connection, it is washed by passing through the column for supporting the radionuclide separation resin (TEVA-Spec), and then again through the 3-4 connection of the 2-way-6 port valve (TW1) 60. After the two-way six-port valve (TW1) (60) formed at the lower portion of the two-way six-port valve (TW2) 60, the 1-2 connection portion is recovered to the waste collection container 100, (Fig. 5 Reference)

2nd process (atmosphere formation process)

First, replace the connection of the 2-way-6 port valve (TW1) 60 (1-6, 2-3, 4-5 connection), and then move 5M nitric acid (HNO ₃ ) in the reagent container 20 in 3 directions For radionuclide separation through 1-6 connections of 2-way-6 port valves (TW1) 60 through P1 of tubing pump and pump speed regulator 50 through SV1 and SV3 of solo valve 40 After passing through the column for supporting the resin (TEVA-Spec), and then again recovered to the waste liquid collection container 100 through the 2-3 connection of the two-way six-port valve (TW1) 60, (Fig. 6)

3rd process (sample injection process)

Select the desired sample liquid from the sample storage box (10), and through the SV1 and SV3 of the three-way solo valve (40) through the tubing pump and the P1 of the pump speed regulator (50) 2-way-6 port valve ( Through 1-6 connections of TW1) 60, the column is passed through a column for supporting radionuclide separation resin (TEVA-Spec) to adsorb Pu to the resin, and the remaining non-adsorbed other elements are bidirectional- again. After returning to the waste collection container 100 through the 2-3 connection of the six-port valve (TW1) 60 (see Fig. 6)

4th process (column 2nd washing process)

In the same manner as in the third process, 5M nitric acid (HNO ₃ ) in the reagent reservoir 20 is passed in two directions through P1 of the tubing pump and the pump speed regulator 50 through SV1 and SV3 of the three-way solo valve 40. Through 1-6 connection of 6 port valve (TW1) 60, eluting other elements other than Pu present in the line and resin through the column 70 for supporting radionuclide separation resin (TEVA-Spec) After recovery with the 5M nitric acid (HNO ₃ ) back to the waste liquid collection tank 100 through the 2-3 connection of the two-way-6 port valve (TW1) 60,

5th process (column 3rd washing process)

In the same manner as in the third process, 9M hydrochloric acid and 1M nitric acid in the reagent container 20 are transferred in two directions through P1 of the tubing pump and pump speed regulator 50 through SV2 and SV3 of the three-way solo valve 40. Through 1-6 connections of the six-port valve (TW1) 60, sequentially passed through the radionuclide separation resin (TEVA-Spec) supporting column 70 to elute the Th and U elements, and the 9M hydrochloric acid and After 1M nitric acid is recovered back to the waste collection container 100 through the 2-3 connection of the 2-way-6 port valve (TW1) 60,

6th process (filling in small 0.5M hydrochloric acid tube)

After the connection of the 2-way-6 port valve (TW1) and the 2-way-6 port valve (TW2) 60 is connected to the A position (1-2, 3-4, 5-6 connection), the reagent container (20 0.5M hydrochloric acid is connected to the 6-6 port valve (TW1) 60 through the P2 of the tubing pump and the pump speed regulator 50 through the SV4 of the 3-way solo valve 40. After passing through the resin support column 70 for radionuclide separation, the 2-way-6 port valve (TW1) through the 3-4 connection part of the 2-way-6 port valve (TW1) 60 again. Inject the solution until it reaches port 1 of the 2-way-6 port valve (TW2) 60 connected to the bottom of the

7th process (separation (elution) process)

Again, after replacing the connection state of the 2-way-6 port valve (TW2) 60 (1-6, 2-3, 4-5 connection), 0.5M hydrochloric acid in the reagent container 20 is added to the 3-way solo furnace. Resin for separating radionuclide (TEVA-) through 5-6 connection of 2-way-6 port valve (TW1) 60 through P2 of tubing pump and pump speed regulator 50 through SV4 of Eve valve 40 Spec) was washed by passing through the support column 70, and then recovered to the eluent collection box 90 through the eluent selective collection valve 80 through the 1-6 connection of TW2.

Hereinafter, the present invention will be described in detail with reference to the accompanying drawings.

Figure 1 radionuclide automatic separation device configuration diagram, Figure 2 radionuclide automatic separation device picture, Figure 3 radionuclide automatic separation device operating program check mode and execution mode screen, Figure 4 radionuclide automatic separation device operation flow chart, Figure 5 and FIG. 6 is a diagram illustrating a chemical operation of Pu chemical separation using a radionuclide automatic separation device, and FIG. 7 is a circuit diagram of the radionuclide automatic separation device according to the present invention, and includes a sample storage box 10, a reagent storage box 30, and a sample solution selection injection. Sample selection valve 20, 3-way solenoid valve (SV1, SV2, SV3, SV4) (40), tubing pump and pump speed regulator (P1, P2) (50), 2-way-6 port valve (TW1, TW2) (60), resin supporting column (70) for radionuclide separation, eluent selective collection valve (80), eluent collection box (90), waste collection container (100), separator control interface and operation program (110) It can be seen that.

Looking at the structure, as shown in Figures 1 to 6,

Sample storage for storing and supplying six samples, and the sample is installed on the front of the sample storage box 10, the sample solution for sample injection to select and inject one by one sample sequentially from the sample storage box (10) A three-way solenoid valve (SV1, SV2, SV3, SV4) 40 connected to the selection valve 30, the sample selection valve 30 for sample solution injection, and the three-way solenoid valves SV1, SV2 and SV3; The reagent container 20 connected to one side of the SV4 and 40 and the three-way solenoid valves SV1, SV2, SV3, and SV4 are connected to the front surface of the reagent reservoir 20, and the elution and eluent flow paths are selected and transferred. Two tubing pumps and pump speed regulators (P1, P2) (50), and two tubing pumps and pump speed regulators (P1, P2) (50) are connected to each other and installed in two two-way- It is connected to one side of the six-port valve (TW1, TW2) 60, and the two-way six-port valve (TW1) 60 and the sample and A resin support column (70) for radionuclide separation (resin) for selectively controlling the injection of the medium, an eluate collector (90) connected to the two-way six-port valve (TW2) 60, and the two A radioactive waste container (100) connected to the other side of the two two-way six-port valves (TW1, TW2) 60, and a device operating program 110 and a PC for operating the above and entering the separation procedure. It can be seen that the nuclide automatic separator.

Figure 7 shows the circuit diagram of the radionuclide automatic separation device of the present invention in detail.

The present invention is a very economical separation device by reducing the time and manpower required to replace the sample and solution continuously and automatically separated a large number of samples, and can improve the quality of analysis because of the excellent reproducibility of separation by accurate operation control have. In addition, since the device can control the remote operation using a PC, it will be used as a device capable of separating radionuclides while minimizing the radiation exposure of an analyzer in case of analysis of a sample having a high radiation concentration.

In addition, the device can selectively inject up to six solvents, and because both strong acids and strong basic solutions can be used, it can be applied to complex and poor separation conditions, and thus has a wide range of applications. In addition, it is expected to be widely used as a general experiment equipment for solution transfer because it can be used for chemical experiments using tubes such as column operation, solution distribution, dilution and filtration through simple operation using an inspection window.

The radionuclide automatic separation device proposed in the present invention is manufactured as a prototype and is currently used as an automatic separation device for the analysis of Np-237, Pu-239, and Pu-240 nuclides in environmental samples at the research site (Korea Atomic Safety Institute). Its use can be seen as proven. Therefore, it is expected that nuclear power companies, research institutes, and academia performing research and analysis related to radionuclide analysis will greatly contribute to securing the efficiency and speed of analysis.

1 is a schematic diagram of automatic radionuclide separation apparatus of the present invention

Figure 2 is a photograph of the radionuclide automatic separation device of the present invention

Figure 3 check mode and execution mode screen of the radionuclide automatic separation device operating program of the present invention

Figure 4 overall operation flow diagram of the radionuclide automatic separation device of the present invention

5 and 6 Pu automatic separation operation state using the radionuclide automatic separation device of the present invention

Figure 7 is a circuit diagram of the radionuclide automatic separation device of the present invention

<Explanation of symbols in the drawings>

Sample storage box (10), reagent storage box (20), sample selection valve for sample solution injection (30), 3-way solenoid valves (SV1, SV2, SV3, SV4) (40), tubing pump and pump speed regulator (P1, P2) (50), 2-way-6 port valves (TW1, TW2) (60), column (70), eluent selective collection valve (80), eluent collection box (90), waste collection container (100), separator Control Interfaces And Operating Programs (110)

Claims (5)

In the radionuclide automatic separation device, Sample storage for storing and supplying six samples, and the sample is installed on the front of the sample storage box 10, the sample solution for sample injection to select and inject one by one sample sequentially from the sample storage box (10) A three-way solenoid valve (SV1, SV2, SV3, SV4) 40 connected to the selection valve 30, the sample selection valve 30 for sample solution injection, and the three-way solenoid valves SV1, SV2, and SV3; The reagent container 20 connected to one side of the SV4 and 40 and the three-way solenoid valves SV1, SV2, SV3, and SV4 are connected to the front surface of the reagent reservoir 20, and the elution and eluent flow paths are selected and transferred. Two tubing pumps and pump speed regulators (P1, P2) (50) and two tubing pumps and pump speed regulators (P1, P2) (50) are connected to each other and installed in two two-way- 6 port valves (TW1, TW2) (60) and the two-way-6 port valve (TW1) 60 is connected to one side of the sample Resin support column 70 for selectively controlling the injection of the solvent, the eluent trap 90 connected to the two-way six-port valve (TW2) 60, and the two And a waste liquid recovery container 100 connected to the other side of the two two-way six-port valves (TW1, TW2) 60 and an apparatus operating program 110 for operating the above and inputting a separation procedure. Radionuclide automatic separation device. In the radionuclide automatic separation method, First process (preparation process) RS-232 control communication and digital input / output PCI card are used to control the operation of all components with a PC. The instrument operating program enters and executes a check window (Test Mode) and a separation process for performance check of each component. It consists of an execution mode for execution, and a progress bar and a progress rate are placed under the window to grasp the overall progress of separation, and each of the execution mode main windows shows the operation status of each component during separation. After installing the button to display the components and their operation status by color change, and the stop button to stop the separation process while the separation program is in progress, press the start button on the automatic separation device. By, First, 0.5 M hydrochloric acid in the reagent reservoir 20 is transferred to the 2-way-6 port valve (TW1) 60 through P2 of the tubing pump and the pump speed regulator 50 through the SV4 of the 3-way solo valve 40. Through the 5-6 connection, it is washed by passing through the column for supporting the radionuclide separation resin (TEVA-Spec), and then again through the 3-4 connection of the 2-way-6 port valve (TW1) 60. After returning to the waste collection container 100 through the 1-2 connection of the two-way six-port valve (TW2) 60 formed in the lower portion of the two-way six-port valve (TW1) (60), 2nd process (atmosphere formation process) First, replace the connection of the 2-way-6 port valve (TW1) 60 (1-6, 2-3, 4-5 connection), and then move 5M nitric acid (HNO ₃ ) in the reagent container 20 in 3 directions For radionuclide separation through 1-6 connections of 2-way-6 port valves (TW1) 60 through P1 of tubing pump and pump speed regulator 50 through SV1 and SV3 of solo valve 40 After passing through the column for supporting the resin (TEVA-Spec), and then again recovered to the waste collection container 100 through the 2-3 connection of the two-way six-port valve (TW1) 60, 3rd process (sample injection process) Select the desired sample liquid from the sample storage box (10), and through the SV1 and SV3 of the three-way solo valve (40) through the tubing pump and the P1 of the pump speed regulator (50) 2-way-6 port valve ( Through 1-6 connections of TW1) 60, the column is passed through a column for supporting radionuclide separation resin (TEVA-Spec) to adsorb Pu to the resin, and the remaining non-adsorbed other elements are bidirectional- again. After returning to the waste collection container 100 through the 2-3 connection of the six-port valve (TW1) 60, 4th process (column 2nd washing process) In the same manner as in the third process, 5M nitric acid (HNO ₃ ) in the reagent reservoir 20 is passed in two directions through P1 of the tubing pump and the pump speed regulator 50 through SV1 and SV3 of the three-way solo valve 40. Through 1-6 connection of 6 port valve (TW1) 60, eluting other elements other than Pu present in the line and resin through the column 70 for supporting radionuclide separation resin (TEVA-Spec) After recovery with the 5M nitric acid (HNO ₃ ) back to the waste liquid collection tank 100 through the 2-3 connection of the two-way-6 port valve (TW1) 60, 5th process (column 3rd washing process) In the same manner as in the third process, 9M hydrochloric acid and 1M nitric acid in the reagent container 20 are transferred in two directions through P1 of the tubing pump and pump speed regulator 50 through SV2 and SV3 of the three-way solo valve 40. Through 1-6 connections of the six-port valve (TW1) 60, sequentially passed through the radionuclide separation resin (TEVA-Spec) supporting column 70 to elute the Th and U elements, and the 9M hydrochloric acid and After 1M nitric acid is recovered back to the waste collection container 100 through the 2-3 connection of the 2-way-6 port valve (TW1) 60, 6th process (filling in small 0.5M hydrochloric acid tube) After the connection of the 2-way-6 port valve (TW1) and the 2-way-6 port valve (TW2) 60 is connected to the A position (1-2, 3-4, 5-6 connection), the reagent container (20 0.5M hydrochloric acid is connected to the 6-6 port valve (TW1) 60 through the P2 of the tubing pump and the pump speed regulator 50 through the SV4 of the 3-way solo valve 40. After passing through the column for supporting the radionuclide separation resin (TEVA-Spec), and then again through the 3-4 connection of the two-way six-port valve (TW1) 60, the two-way-6 port valve Inject the solution until it reaches port 1 of the 2-way-6 port valve (TW2) 60 connected to the lower part of (TW1) (60), 7th process (separation (elution) process) Again, after replacing the connection state of the 2-way-6 port valve (TW2) 60 (1-6, 2-3, 4-5 connection), 0.5M hydrochloric acid in the reagent container 20 is added to the 3-way solo furnace. Resin for separating radionuclide (TEVA-) through 5-6 connection of 2-way-6 port valve (TW1) 60 through P2 of tubing pump and pump speed regulator 50 through SV4 of Eve valve 40 Spec) Plutonium (Pu), characterized in that to recover through the eluent collection box (90) through the eluent selective collection valve 80 through the 1-6 connection of TW2 after washing through the support column (70) Separation Method. The two-way six-port valves (TW1, TW2) 60 each have two paths of 1-2, 3-4, 5-6 and 1-6, 2-3, 4-5 connections. Plutonium (Pu) automatic separation method characterized in that the transfer of the solution by selectively replacing. 3. The continuous chemistry of a plurality of samples by reuse of a TEVA-Spec® resin having excellent sample injection, collection, and reproducibility using the sample selection valve 30 and the eluent selective collection valve 80. Plutonium (Pu) automatic separation method characterized in that the separation is made. The method of claim 2, wherein the supply, transport and discharge of all the solution is made by inserting a small hole into the container only the PEEK tubing in the lid of all the solution vessel to prevent harmful gas leakage and other elements from the outside The sealing was maintained, and the flow path connection between components using acid resistant PTFE tubing was sealed by using PEEK nut and Tefzel Penul, and acid resistant Tygon® MH tube was used as the tubing pump. Plutonium (Pu) automatic separation method characterized in that the chemical separation is made under the secondary sealing of the solution.