A rapid nuclear waste vitrification reactor

Abstract

The present invention relates to the field of a rapid nuclear waste glass solidification reactor, and discloses a rapid nuclear waste glass solidification reactor, including a reactor shell, a crucible kiln installed in the reactor shell, which is a glass solidification nuclear waste container, a kiln cover installed at the upper end of the crucible kiln, a motor installed at the upper end of the kiln cover, a stirring rod fixedly connected to the output end of the motor, the stirring rod is placed in the crucible kiln, and a temperature controller is installed on the side wall of the reactor shell. Compared with the prior art, the present application has the advantages of precise temperature control during the reaction process, optimal ratio reaction of nuclear waste and glass substrate, etc., and solves a series of problems such as serious imbalance of the ratio of glass substrate and nuclear waste, serious waste of glass substrate, etc.

Description

Technical Field

[0001] The invention relates to the field of nuclear waste glass solidification, in particular to a rapid nuclear waste glass solidification reactor. Background Art

[0002] Nuclear waste vitrification is a process of mixing radioactive waste liquid with glass raw materials, melting them at high temperatures, and then cooling them to form a vitreous body. This vitreous body can effectively contain radioactive substances and form a stable form. It is currently an advanced waste liquid treatment method in the world. The vitreous body has a low leaching rate and high strength, which can ensure that radioactive substances are contained stably for a long time and achieve the goal of isolating them from the biosphere.

[0003] At present, for the solidification of nuclear waste by glass, the glass substrate and nuclear waste are generally mixed in proportion, and then heated, melted and stirred. The heating temperature is a preset optimal temperature. In this process, part of the nuclear waste will turn into steam under high temperature. However, in the actual reaction, due to the material of the glass substrate and the treatment of different nuclear wastes, the set temperature is not necessarily the optimal temperature. If the steam pressure is too large under the optimal temperature, the nuclear waste will be lost too quickly, and the ratio of nuclear waste to glass substrate will change. If the temperature is not controlled, and even if the nuclear waste is supplemented, it will lead to a serious imbalance in the ratio of glass substrate to nuclear waste, which will seriously cause waste of glass substrate, increase solidification cost, and reduce nuclear waste treatment efficiency.

[0004] If nuclear waste is solidified in a closed environment, a large amount of steam will also be generated, and the steam will not return to the reaction, which will also lead to the above-mentioned problems. Therefore, based on the above reasons, the present invention provides a rapid nuclear waste glass solidification reactor. Summary of the invention

[0005] In view of the shortcomings of the prior art, the present invention provides a rapid nuclear waste glass solidification reactor, which has the advantages of precise temperature control during the reaction process and optimal ratio reaction of nuclear waste and glass substrate, thus solving a series of problems such as the serious imbalance in the ratio of glass substrate and nuclear waste, which seriously causes waste of glass substrate.

[0006] To achieve the above object, the present invention provides the following technical solution: a rapid nuclear waste vitrification reactor, comprising:

[0007] A reactor shell, a crucible kiln is installed in the reactor shell, which is a glass solidified nuclear waste container, a kiln cover is installed on the upper end of the crucible kiln, a motor is installed on the upper end of the kiln cover, a stirring rod is fixedly connected to the output end of the motor, and the stirring rod is placed in the crucible kiln, and a temperature controller is installed on the side wall of the reactor shell;

[0008] An alloy storage barrel is installed on one side of the reactor shell and is used to store nuclear waste liquid. A diaphragm pump is installed between the alloy storage barrel and the reactor shell, and the input end and output end of the diaphragm pump are respectively connected to the alloy storage barrel and the reactor shell;

[0009] An exhaust assembly is installed on one side of the reactor shell and is used for discharging steam during the curing process, including a steam blocking cylinder fixed on one side of the reactor shell, one end of the steam blocking cylinder is connected to one end of the exhaust pipe, the other end of the exhaust pipe extends into the crucible kiln, the other end of the steam blocking cylinder is connected to one end of the connecting pipe, the other end of the connecting pipe is connected to a cooling cylinder, a plurality of first cylinders are installed on the end side wall of the steam blocking cylinder, a first telescopic plate is fixedly connected to the telescopic end of the first cylinder, a plurality of connecting grooves are arranged on the inner wall of the steam blocking cylinder, a connecting pipe is connected between the plurality of first cylinders, an air cylinder is installed on the end of the steam blocking cylinder, and a fixed pipe is connected between the air cylinder and the connecting pipe;

[0010] A second cylinder is installed on the side wall of the inner end of the air cylinder, a second telescopic plate is connected to the telescopic end of the second cylinder, and a displacement sensor is installed on the second telescopic plate;

[0011] A cooling telescopic cylinder is vertically telescopically installed in the cooling cylinder, the other end of the connecting pipe passes through the cooling cylinder and extends into the bottom of the cooling telescopic cylinder, a cooling pipe is installed at the top of the cooling telescopic cylinder, the pipe openings at both ends of the cooling pipe extend from the top side walls of the cooling telescopic cylinder respectively, the upper end of the cooling telescopic cylinder is connected to a steam exhaust pipe, and a pressure sensor is installed at the bottom of the cooling cylinder.

[0012] Preferably, a flow control valve is installed on the output pipeline of the diaphragm pump.

[0013] Preferably, a spiral heating resistance coil is installed around the inside of the crucible furnace, and both ends of the spiral heating resistance coil are connected to the temperature controller.

[0014] Preferably, a first heat exchange tube is wound around the outer surface of the steam-blocking cylinder, a second heat exchange tube is wound around the outer surface of the connecting tube, one end of the first heat exchange tube is connected to one end of the second heat exchange tube, the other end of the first heat exchange tube extends into the crucible kiln and is connected to the other end of the second heat exchange tube, and the first heat exchange tube and the second heat exchange tube are filled with heat exchange liquid.

[0015] Preferably, a fixed metal bracket is provided on the side wall of the reactor shell, which is used to fix the steam blocking cylinder and its connected connecting pipe and cooling cylinder on the side wall of the reactor shell.

[0016] Preferably, coolers are externally connected to the pipe openings at both ends of the cooling pipe.

[0017] Preferably, the steam exhaust pipe is a metal bellows.

[0018] Compared with the prior art, the present invention provides a rapid nuclear waste vitrification reactor, which has the following beneficial effects:

[0019] 1. The rapid nuclear waste glass solidification reactor can achieve real-time control of the set temperature in the crucible furnace according to the steam generated during the solidification process through the installed steam barrier, so that the glass substrate and the nuclear waste have the best reaction effect at the set temperature.

[0020] 2. This rapid nuclear waste glass solidification reactor can control the opening of the flow control valve and the flow rate of the nuclear waste liquid through the pressure signal detected by the pressure sensor, so as to realize feeding during the nuclear waste solidification process, ensure that a certain amount of glass substrate can solidify a certain proportion of nuclear waste, improve the utilization rate of the glass substrate and reduce material waste. BRIEF DESCRIPTION OF THE DRAWINGS

[0021] Figure 1 It is a schematic diagram of the three-dimensional structure of the present invention;

[0022] Figure 2 This is a schematic diagram of the internal structure of the crucible furnace of the present invention;

[0023] Figure 3 It is a schematic diagram of the three-dimensional structure of the exhaust assembly of the present invention;

[0024] Figure 4 This is a schematic diagram of the internal structure of the steam blocking cylinder of the present invention;

[0025] Figure 5 This is a schematic diagram of the installation structure of the first telescopic plate of the present invention;

[0026] Figure 6 It is a schematic diagram of the internal structure of the gas cylinder of the present invention;

[0027] Figure 7 It is a schematic diagram of the three-dimensional structure of the cooling cylinder of the present invention;

[0028] Figure 8 This is a schematic diagram of the three-dimensional structure of the cooling telescopic cylinder of the present invention;

[0029] Fig. 9 It is a schematic diagram of the cross-sectional structure of the cooling cylinder of the present invention.

[0030] In the figure: 1. Reactor shell; 2. Diaphragm pump; 3. Alloy storage barrel; 4. Temperature controller; 5. Kiln cover; 6. Motor; 7. Exhaust assembly; 8. Flow control valve; 9. Crucible kiln; 10. Stirring rod; 11. Exhaust pipe; 12. Steam barrier cylinder; 13. First heat exchange tube; 14. Connecting pipe; 15. Second heat exchange tube; 16. Steam exhaust pipe; 17. Cooling cylinder; 18. First telescopic plate; 19. Connecting groove; 20. First cylinder; 21. Connecting pipe; 22. Cylinder; 23. Fixed pipe; 24. Second telescopic plate; 25. Displacement sensor; 26. Second cylinder; 27. Cooling telescopic cylinder; 28. Cooling pipe; 29. ​​Pressure sensor. DETAILED DESCRIPTION

[0031] The following will be combined with the drawings in the embodiments of the present invention to clearly and completely describe the technical solutions in the embodiments of the present invention. Obviously, the described embodiments are only part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0032] As introduced in the background technology, there are deficiencies in the prior art. In order to solve the above technical problems, the present application proposes a rapid nuclear waste glass solidification reactor.

[0033] Embodiment 1

[0034] like Figure 1-6 As shown, a rapid nuclear waste glass solidification reactor comprises a reactor shell 1, a crucible kiln 9 is installed in the reactor shell 1, and the crucible kiln 9 is a glass solidification nuclear waste container. A kiln cover 5 is installed at the upper end of the crucible kiln 9, and a motor 6 is installed at the upper end of the kiln cover 5. A stirring rod 10 is fixedly connected to the output end of the motor 6, and the stirring rod 10 is placed in the crucible kiln 9. A temperature controller 4 is installed on the side wall of the reactor shell 1. A glass substrate and a nuclear waste liquid to be treated are put into the crucible kiln 9 according to a certain proportion. The crucible kiln 9 is a common electric heating crucible at present. The temperature controller 4 is used for heating temperature control. After the glass substrate and the nuclear waste liquid are put into the crucible kiln 9, the kiln cover 5 is covered for rapid heating. The heating temperature is controlled at 1100°C-1300°C. During the heating process, the motor 6 is turned on, and the motor 6 drives the stirring rod 10 to rotate, so as to accelerate the melting and reaction of the glass substrate and the nuclear waste. The glass substrate and the nuclear waste react to form a glass solidified body in a molten state, which is then discharged from the bottom of the reactor shell 1, collected through a crucible, and cooled to form a glass solidified body.

[0035] The crucible kiln 9 mentioned above is surrounded by a spiral heating resistance coil, and both ends of the spiral heating resistance coil are connected to the temperature controller 4. The core of the temperature controller 4 is a temperature sensor, and the temperature sensor adopts a thermocouple temperature sensor, which is used to detect the temperature inside the crucible kiln 9. A thermocouple can be used. The thermocouple is installed on the inner wall of the crucible kiln 9 and is used to monitor the temperature inside the crucible in real time. The thermocouple includes a microprocessor of a PID control algorithm. In addition, the temperature controller 4 also includes an actuator, which adopts a relay to control the power supply of the spiral heating resistance coil;

[0036] The PID control principle mentioned above is:

[0037] Proportional (P) control: The output of the temperature controller 4 is proportional to the current temperature deviation. If the temperature is lower than the set value, the temperature controller 4 will increase the power of the heating element. If the temperature is higher than the set value, the temperature controller 4 will reduce the power.

[0038] Integral (I) control: The output of the temperature controller 4 is proportional to the accumulation of temperature deviation over time, which helps to eliminate steady-state errors and ensure that the system temperature is stable after long-term operation;

[0039] Derivative (D) control: The temperature controller 4 output is proportional to the rate of change of temperature deviation, which helps predict the future behavior of the system and reduce overshoot and oscillation;

[0040] The control process of controlling the temperature in the crucible kiln 9 by the temperature controller 4 is as follows:

[0041] 1) Monitoring temperature: The temperature sensor continuously monitors the real-time temperature of the electric crucible;

[0042] 2) Signal transmission: The temperature sensor converts the monitored temperature into an electrical signal and transmits it to the temperature controller 4;

[0043] 3) Deviation calculation: The temperature controller 4 calculates the deviation between the actual temperature and the set target temperature;

[0044] 4) PID adjustment: The temperature controller 4 calculates the required control signal based on the PID algorithm, which takes into account the deviation, the integral of the deviation and the rate of change of the deviation;

[0045] 5) Execution control: The actuator adjusts the power output of the heating element according to the signal of the temperature controller 4 to reduce the temperature deviation;

[0046] 6) Feedback loop: The system repeats the above process until the actual temperature is very close to the set temperature and remains stable;

[0047] The set temperature mentioned above is the temperature under the optimal reaction state between the glass substrate and the nuclear waste liquid.

[0048] Alloy storage barrel 3, alloy storage barrel 3 is installed on one side of reactor shell 1, used for storing nuclear waste liquid, diaphragm pump 2 is installed between alloy storage barrel 3 and reactor shell 1, input end and output end of diaphragm pump 2 are respectively connected with alloy storage barrel 3 and reactor shell 1, nuclear waste liquid is pumped into crucible kiln 9 by diaphragm pump 2 to mix with glass substrate, sampling diaphragm pump 2 is used for infusion, which can avoid corrosion caused by nuclear waste liquid;

[0049] As a preferred implementation in this embodiment, a steam exhaust component 7 is also provided, which is installed on one side of the reactor shell 1 and is used for discharging steam during the curing process, including a steam blocking cylinder 12 fixed on one side of the reactor shell 1, one end of the steam blocking cylinder 12 is connected to one end of the steam exhaust pipe 11, and the other end of the steam exhaust pipe 11 extends into the crucible kiln 9, the other end of the steam blocking cylinder 12 is connected to one end of the connecting pipe 14, and the other end of the connecting pipe 14 is connected to a cooling cylinder 17, a plurality of first cylinders 20 are installed on the end side wall of the steam blocking cylinder 12, and the telescopic end of the first cylinder 20 is fixedly connected to a first telescopic plate 18, a plurality of connecting grooves 19 are provided on the inner wall of the steam blocking cylinder 12, and connecting pipes 21 are connected between the plurality of first cylinders 20, a gas cylinder 22 is installed at the end of the steam blocking cylinder 12, and a fixed pipe 23 is connected between the gas cylinder 22 and the connecting pipe 21;

[0050] Furthermore, under high temperature, the water and some nuclear wastes contained in the nuclear waste liquid, including xenon (Xe) and krypton (Kr), etc., will turn into steam, and the steam will be discharged into the steam blocking cylinder 12 through the exhaust pipe 11. The steam pushes the first telescopic plate 18 in the steam blocking cylinder 12 to move, and a plurality of first cylinders 20 are compressed. In this process, the moving first telescopic plate 18 will expose the connecting groove 19 on the inner wall of the steam blocking cylinder 12, so that the space on both sides of the first telescopic plate 18 is connected, and the steam flows along the connecting groove 19 and enters the connecting pipe 14, and then enters the cooling cylinder 17 along the connecting pipe 14, and is discharged from the steam exhaust pipe 16 after condensation for subsequent treatment;

[0051] A second cylinder 26 is installed on the side wall of the inner end of the air cylinder 22, and a second telescopic plate 24 is connected to the telescopic end of the second cylinder 26, and a displacement sensor 25 is installed on the second telescopic plate 24;

[0052] It is worth mentioning that when the nuclear waste steam is first discharged into the steam blocking cylinder 12 through the exhaust pipe 11, the steam first needs to push the first telescopic plate 18 open to offset the pressure of the first cylinders 20 until the steam pressure can push the first telescopic plate 18 to move, until the steam can pass through the connecting groove 19, at this time, the steam enters the connecting pipe 14 through the connecting groove 19, in this process, the gas in the first cylinder 20 enters the cylinder 22 through the connecting pipe 21 and the fixed pipe 23 connected thereto, and pushes the second telescopic plate 24 to move, and the second cylinder 26 is compressed;

[0053] The above process can represent two situations:

[0054] First, the greater the displacement of the first telescopic plate 18, the higher the steam pressure, indicating that the temperature in the crucible kiln 9 is higher, the greater the displacement of the first telescopic plate 18, the greater the compression of the first cylinder 20, the greater the displacement of the gas cylinder 22 connected thereto, and the displacement is detected by the displacement sensor 25, that is, the greater the displacement detected by the displacement sensor 25, the higher the temperature in the crucible kiln 9 is;

[0055] Second: On the contrary, the smaller the displacement detected by the displacement sensor 25 is, the lower the temperature in the crucible furnace 9 is;

[0056] Therefore, if the temperature in the crucible kiln 9 is the set temperature, but the displacement detected by the displacement sensor 25 is large or small at this time, it means that the set temperature is not conducive to the solidification of nuclear waste. We need to change the set temperature. Its change is inversely proportional to the displacement detected by the displacement sensor 25. The formula is: T=λ / S, where T is the set temperature, S is the displacement detected by the displacement sensor 25, and λ is the inverse coefficient. The control steps are as follows:

[0057] 1) The signal generated by the displacement sensor 25 is usually an analog signal and needs to be processed by a signal conditioning circuit (such as an amplifier or a filter);

[0058] 2) Convert the processed analog signal into a digital signal;

[0059] 3) Substitute the digital signal into the formula to calculate the set temperature that needs to be changed;

[0060] 4) The temperature controller 4 adjusts the output of the heating or cooling element through an actuator (such as a relay, transistor or inverter) to change the actual temperature to match the new set temperature;

[0061] 5) The displacement sensor 25 continues to monitor the displacement change, and the temperature controller 4 continuously receives new data and further adjusts the set temperature as needed, forming a closed-loop control system.

[0062] Through the above control process, it can be achieved that the temperature in the crucible furnace 9 is always the optimal set value under actual conditions.

[0063] Embodiment 2

[0064] like Figure 7-9As shown, a cooling telescopic cylinder 27 is vertically telescopically installed in the cooling cylinder 17, the other end of the connecting pipe 14 passes through the cooling cylinder 17 and extends into the bottom of the cooling telescopic cylinder 27, a cooling pipe 28 is installed at the top of the cooling telescopic cylinder 27, and the two end nozzles of the cooling pipe 28 extend from the top side walls of the cooling telescopic cylinder 27 respectively, the upper end of the cooling telescopic cylinder 27 is connected to the steam exhaust pipe 16, a pressure sensor 29 is installed at the bottom of the cooling cylinder 17, a flow control valve 8 is installed on the output pipeline of the diaphragm pump 2, and the two end nozzles of the cooling pipe 28 are externally connected to coolers.

[0065] The high-temperature nuclear waste steam is introduced into the cooling telescopic cylinder 27 from the connecting pipe 14, and the high-temperature nuclear waste steam is condensed through the cooling pipe 28 installed in the cooling telescopic cylinder 27. The condensed water vapor and solidified nuclear waste are condensed on the surface of the cooling pipe 28, and the air flow continues to be discharged from the steam exhaust pipe 16, while the condensed water vapor and nuclear waste remain in the cooling telescopic cylinder 27. The mass of the cooling telescopic cylinder 27 itself increases, and the mass change of the cooling telescopic cylinder 27 detected by the pressure sensor 29 is the nuclear waste liquid lost in the crucible kiln 9;

[0066] In the above process, the pressure signal detected by the pressure sensor 29 can control the opening of the flow control valve 8 and the flow rate of the nuclear waste liquid, so as to realize the replenishment of the material during the solidification process of the nuclear waste, ensure that a certain amount of glass substrate can solidify a certain proportion of the nuclear waste, improve the utilization rate of the glass substrate, and reduce material waste. The specific control process is as follows:

[0067] 1) The signal output by the sensor is amplified by the signal conditioning circuit, and the conditioned analog signal is converted into a digital signal;

[0068] 2) programming an algorithm in the controller, which adjusts the opening degree of the flow control valve according to the output of the pressure sensor 29;

[0069] 3) The controller compares the reading of the pressure sensor 29 with the preset pressure value, calculates the pressure deviation, calculates the required flow setting value, and adjusts the opening degree of the flow control valve 8 accordingly;

[0070] 4) The controller adjusts the opening degree of the flow control valve 8 through an actuator (such as an electric or pneumatic actuator);

[0071] 5) Flow sensors (such as vortex flowmeters, electromagnetic flowmeters, etc.) monitor the actual flow rate and provide feedback signals to the controller;

[0072] 6) The controller continuously adjusts the flow control valve 8 according to the flow feedback signal to ensure that the actual flow is proportional to the pressure detected by the pressure sensor 29;

[0073] The controller mentioned above adopts a PLC controller, which is used to realize the detection signal of the pressure sensor 29 to control the opening and flow control of the flow control valve 8.

[0074] Embodiment 3

[0075] like Figure 3 As shown, a first heat exchange tube 13 is wound around the outer surface of the steam barrier cylinder 12, and a second heat exchange tube 15 is wound around the outer surface of the connecting tube 14, one end of the first heat exchange tube 13 is connected to one end of the second heat exchange tube 15, and the other end of the first heat exchange tube 13 extends into the crucible kiln 9 and is connected to the other end of the second heat exchange tube 15, and the first heat exchange tube 13 and the second heat exchange tube 15 are filled with heat exchange liquid, and the high temperature in the crucible kiln 9 is transferred to the first heat exchange tube 13 and the second heat exchange tube 15 through the heat exchange liquid, which is used to maintain the temperature in the steam barrier cylinder 12 and the connecting tube 14 to prevent steam from condensing when being transmitted in the steam barrier cylinder 12 and the connecting tube 14.

[0076] A fixed metal bracket is provided on the side wall of the reactor shell 1 for fixing the steam blocking cylinder 12 and its connected connecting pipe 14 and cooling cylinder 17 on the side wall of the reactor shell 1 .

[0077] The steam exhaust pipe 16 is a metal bellows to prevent the gas discharged from the steam exhaust pipe 16 from affecting the pressure sensor 29 on the pressure detection of the cooling telescopic cylinder 27 .

[0078] Working principle of the present invention: when in use, the glass substrate and the nuclear waste liquid to be treated are put into the crucible kiln 9 according to a certain proportion. The crucible kiln 9 is a common electric heating crucible. The temperature controller 4 is used for heating temperature control. After the glass substrate and the nuclear waste liquid are put into the crucible kiln 9, the kiln cover 5 is covered for rapid heating. The heating temperature is controlled at 1100°C-1300°C. During the heating process, the motor 6 is turned on, and the motor 6 drives the stirring rod 10 to rotate, accelerating the melting and reaction of the glass substrate and the nuclear waste. The glass substrate and the nuclear waste react to form a molten glass solid body, which is then discharged from the bottom of the reactor shell 1, collected by the crucible, and cooled to form a glass solid body.

[0079] Although embodiments of the present invention have been shown and described, it will be appreciated by those skilled in the art that various changes, modifications, substitutions and variations may be made to the embodiments without departing from the principles and spirit of the present invention, and that the scope of the present invention is defined by the appended claims and their equivalents.

Claims

1. A rapid nuclear waste vitrification reactor, characterized in that: include, A reactor shell (1), wherein a crucible kiln (9) is installed in the reactor shell (1), and the crucible kiln (9) is a container for glass-solidified nuclear waste. A kiln cover (5) is installed at the upper end of the crucible kiln (9), and a motor (6) is installed at the upper end of the kiln cover (5). A stirring rod (10) is fixedly connected to the output end of the motor (6), and the stirring rod (10) is placed in the crucible kiln (9). A temperature controller (4) is installed on the side wall of the reactor shell (1); An alloy storage barrel (3) is installed on one side of the reactor shell (1) and is used to store nuclear waste liquid. A diaphragm pump (2) is installed between the alloy storage barrel (3) and the reactor shell (1). The input end and the output end of the diaphragm pump (2) are respectively connected to the alloy storage barrel (3) and the reactor shell (1); A steam exhaust component (7), the steam exhaust component (7) is installed on one side of the reactor shell (1) and is used for exhausting steam during the curing process, comprising a steam blocking cylinder (12) fixed on one side of the reactor shell (1), one end of the steam blocking cylinder (12) is connected to one end of the steam exhaust pipe (11), the other end of the steam exhaust pipe (11) extends into the crucible kiln (9), the other end of the steam blocking cylinder (12) is connected to one end of the connecting pipe (14), the other end of the connecting pipe (14) is connected to a cooling cylinder (17), a plurality of first cylinders (20) are installed on the end side wall of the steam blocking cylinder (12), the telescopic end of the first cylinder (20) is fixedly connected to a first telescopic plate (18), a plurality of connecting grooves (19) are provided on the inner wall of the steam blocking cylinder (12), a connecting pipe (21) is connected between the plurality of first cylinders (20), a gas cylinder (22) is installed at the end of the steam blocking cylinder (12), and a fixed pipe (23) is connected between the gas cylinder (22) and the connecting pipe (21); A second cylinder (26) is installed on the side wall of the inner end of the air cylinder (22); a second telescopic plate (24) is connected to the telescopic end of the second cylinder (26); and a displacement sensor (25) is installed on the second telescopic plate (24); A cooling telescopic cylinder (27) is vertically telescopically installed in the cooling cylinder (17), the other end of the connecting pipe (14) passes through the cooling cylinder (17) and extends into the bottom of the cooling telescopic cylinder (27), a cooling pipe (28) is installed at the top of the cooling telescopic cylinder (27), and the two end openings of the cooling pipe (28) extend from the top side walls of the cooling telescopic cylinder (27), the upper end of the cooling telescopic cylinder (27) is connected to a steam exhaust pipe (16), and a pressure sensor (29) is installed at the bottom of the cooling cylinder (17).

2. A rapid nuclear waste vitrification reactor according to claim 1, characterized in that: A flow control valve (8) is installed on the output pipeline of the diaphragm pump (2).

3. A rapid nuclear waste vitrification reactor according to claim 2, characterized in that: A spiral heating resistance coil is installed around the inside of the crucible kiln (9), and both ends of the spiral heating resistance coil are connected to the temperature controller (4).

4. A rapid nuclear waste vitrification reactor according to claim 3, characterized in that: A first heat exchange tube (13) is wound around the outer surface of the steam blocking cylinder (12), and a second heat exchange tube (15) is wound around the outer surface of the connecting tube (14); one end of the first heat exchange tube (13) is connected to one end of the second heat exchange tube (15); the other end of the first heat exchange tube (13) extends into the crucible kiln (9) and is connected to the other end of the second heat exchange tube (15); and the first heat exchange tube (13) and the second heat exchange tube (15) are filled with heat exchange liquid.

5. A rapid nuclear waste vitrification reactor according to claim 4, characterized in that: A fixed metal bracket is provided on the side wall of the reactor shell (1) for fixing the steam blocking cylinder (12) and its connected connecting pipe (14) and cooling cylinder (17) on the side wall of the reactor shell (1).

6. A rapid nuclear waste vitrification reactor according to claim 5, characterized in that: The ends of the cooling pipe (28) are externally connected to coolers.

7. A rapid nuclear waste vitrification reactor according to claim 6, characterized in that: The steam exhaust pipe (16) is a metal bellows.

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