718 results about "Control rod" patented technology

The invention discloses an electric steam generator with a waste heat recovery device, and relates to the technical field of steam generators, the electric steam generator comprises a main body, a heating cavity is fixedly connected to the inner side of the main body, a plurality of electric heating pipes are fixedly connected to the inner side of the main body and located on the periphery of the heating cavity, and a recovery unit is arranged on the outer side of the main body. The upper side of the main body is fixedly connected with a first water inlet pipe, the right side of the main body is fixedly connected with a steam discharge pipe and a gas pipeline, the recovery unit comprises a fixing frame, and the fixing frame is fixedly connected to the outer side of the main body. According to the electric steam generator with the waste heat recovery device, the main body, the heating cavity, the electric heating pipe, the smoke conveying pipe, the heat exchange pipe and the recovery barrel are arranged, generated high-temperature smoke waste heat is conveniently recovered, stirring plates on the upper side and the lower side are conveniently controlled to rotate through a control rod, a second gear, a first gear, a motor and a fixing ring, water is stirred, and the heat exchange effect is improved.

A molten salt nuclear reactor includes a vessel and a control blade assembly disposed within the vessel. The control blade assembly includes a drive rod and a control blade. The drive rod further includes an oblique surface wherein vertical motion of the drive rod and its oblique surface causes horizontal motion of the control blade into and out of a reactor section of the molten salt reactor.

The invention belongs to the technical field of nuclear power, and particularly relates to a device and method for remote installation of a heat insulation sleeve relieving cushion block. Comprising a gripping apparatus and a screwing tool, the gripping apparatus is used for gripping the cushion block, the bolt and the locking cap to mount and dismount the cushion block, and the screwing tool is used for positioning and mounting the relieving cushion block on the upper cover plate of the control rod guide cylinder and fastening the bolt. The clamping device has the beneficial effects that the air cylinder is adopted to drive the grabhooks to be opened and closed, clamping of the cushion block is achieved, meanwhile, it is guaranteed that the grabhooks are in an open state during air loss through the built-in springs, and the cushion block is prevented from falling off. A grabbing structure that the bolts and the locking caps are lifted along with the cushion blocks is adopted, meanwhile, the anti-falling function is achieved, and integrated operation of clamping, conveying, positioning and screwing of the cushion blocks is achieved.

The utility model belongs to the technical field of preparation of carbon nanotubes, and particularly relates to a carbon nanotube discharging device. The discharging device is arranged at the discharging end of the tubular heating furnace and comprises a collecting bin, and a collecting cavity communicating with a discharging opening of the tubular heating furnace is formed in the collecting bin. An operation opening is formed in the collecting bin, a flexible pipeline is connected to the operation opening, and the operation opening is connected with the near end of the flexible pipeline in a sealed mode; at least one operating rod penetrates through the flexible pipeline and extends into the collecting cavity, and the far end of the flexible pipeline is in sealed connection with the operating rod; a discharging connector is arranged at the bottom of the collecting bin. The collecting bin arranged at the discharging end is beneficial to timely removal of flocculent single-walled carbon nanotubes formed in the growth process, furnace tube blockage is prevented, production continuity is guaranteed, and safety is improved. And a flexible pipeline and an operating rod are arranged on the collecting bin, so that an operator can collect the carbon nanotubes under the condition that the normal operation of the heating furnace is not influenced. The winding roller is beneficial to orderly collection of carbon nanotube floccules.

The invention discloses a three-dimensional fluid-solid coupling simulation method and device for a rod falling behavior of a control rod drive line, and relates to the technical field of simulation of the rod falling behavior of the control rod drive line. Fluid boundary updating in the rod falling process of the control rod is processed through a structural grid and dynamic grid layer laying technology on the basis of computational fluid dynamics and multi-body dynamics theories; a modal synthesis method and a Hertz contact model are adopted to solve the problems of flexibility and contact friction of a large-length-diameter-ratio moving part, key factors including fluid resistance and mechanical friction resistance influencing rod falling simulation accuracy are calculated, fluid-solid coupling is achieved through one-way data transmission, three-dimensional fluid-solid coupling of the rod falling behavior of the control rod drive wire is achieved, and the control rod drive wire rod falling simulation accuracy is improved. The accuracy of a simulation result is improved, the degree of dependence on a prototype test is reduced, and a technical basis is provided for researching the rod falling behavior of the reactor control rod drive wire.

The utility model relates to the technical field of extrusion molding equipment, and discloses a quick color changing device for secondary coating of an optical cable, which comprises a main machine hopper, a support plate is fixedly connected in the main machine hopper, mounting ports are symmetrically arranged on the support plate, a first containing hopper and a second containing hopper are arranged at the mounting ports, and the first containing hopper and the second containing hopper are arranged in the main machine hopper. A color changing assembly is arranged on the supporting plate and comprises a control rod rotationally installed on the supporting plate, the upper end of the control rod is fixedly connected with a color changing knob, a color changing piece is fixed to the lower end of the control rod, and the color changing piece is in a cross shape. According to the color changing device, the color changing component is arranged, the color changing knob can be rotated to realize the function of releasing the color masterbatch, so that the natural color base material and the color masterbatch can be conveniently mixed, the function of quickly changing the color is realized, and the color changing device is compact in overall structure, does not need to additionally occupy the space at the upper part of the screw extruder and is convenient to use.

The invention belongs to the technical field of special maintenance of reactor bodies, and particularly relates to an electric spark machining head for cutting a sleeve flange in a narrow space. Comprising an expansion mechanism, a fine adjustment jacking mechanism, a rotating mechanism, an electrode and a radial servo feeding mechanism, the rotating mechanism provides rotary motion of the electrode and drives the electrode to conduct rotary machining, the radial servo feeding mechanism provides radial feeding motion of the electrode, and the expansion mechanism plays a role in fixing and positioning. The fine adjustment jacking mechanism drives the rotating mechanism, and the radial servo feeding mechanism drives the electrode to do up-down, rotating and radial feeding movement. The method has the beneficial effects that the damage to the pressure-bearing boundary of the primary loop of the nuclear power unit can be avoided under the condition that the heat sleeve is worn out of limits and needs to be replaced aiming at the common problem of wear settlement of the heat sleeve of the control rod driving mechanism of the nuclear power unit, and the whole dismantling work has relatively high safety, reliability and economical efficiency; and greater benefits can be created for the operation of a power plant.

The present invention relates to a nuclear fuel assembly suitable for a small modular reactor (SMR), the nuclear fuel assembly comprising: a spacer grid (110) having 17x17 grid cells; a plurality of fuel rods (120) arranged in the grid cells of the spacer grid (110); guide tubes (130) arranged and fixed in the grid cells of the spacer grid (110); and an upper end fitting (140) and a lower end fitting (150) fixed to the upper end and the lower end of the guide tubes (130), respectively, wherein the guide tubes (130) are characterized in that eight guide tubes are arranged in the main axis directions (Ixx)(Iyy) with respect to the central cell of the spacer grid (110), four guide tubes are arranged in the diagonal direction (Ixy), and sixteen guide tubes are arranged in the non-diagonal directions (Ixxy)(Ixyy).

The invention belongs to the technical field of processing of nuclear reactor control rod neutron absorber materials, and particularly relates to a preparation method of a nuclear-grade hafnium cast ingot. The method comprises the following steps: preparing sponge hafnium into an electrode block; performing vacuum electron beam melting on the electrode block for at least two times to obtain a finished cast ingot; and processing the finished cast ingot to prepare the nuclear-grade hafnium cast ingot which can be used for processing the control rod profile for the nuclear reactor assembly. According to the preparation method of the nuclear-grade hafnium cast ingot, the tensile strength, the welding performance and the creep performance of a nuclear-grade hafnium profile can be effectively improved; meanwhile, the technological process is simplified, and the technological economy and the production efficiency are remarkably improved; in addition, sponge hafnium is directly adopted for vacuum electron beam melting, so that the cost of raw materials is greatly reduced. According to the method, the application performance of the nuclear-grade hafnium profile is improved, meanwhile, the process is simplified, the production efficiency is improved, the production cost is reduced, and the economical efficiency of nuclear-grade hafnium profile manufacturing is greatly improved.

The present invention belongs to the technical field of ceramic preparation, and relates to a preparation method and device for a high-purity porous boron carbide nuclear control rod. The present invention uses boron trichloride gas as the boron source, methane as the carbon source, argon as the carrier gas and protective gas, and hydrogen as the catalytic gas and reducing gas to prepare a high-purity porous boron carbide nuclear control rod. The method of increasing the deposition temperature of boron carbide step by step and region by region from the back to the front is adopted, which can not only improve the deposition rate of boron carbide, but also ensure that the physical and mechanical properties of each part of the prepared high-purity porous boron carbide nuclear control rod are consistent. By changing the particle size of the boron carbide powder for preparing the boron carbide blank and coordinating the adjustment of temperature, flow rate, pressure and deposition time, the porosity and pore size of the prepared high-purity porous boron carbide can be regulated and a high total boron and carbon content can be obtained, so as to meet various actual requirements.

The invention belongs to the technical field of maintenance of upper reactor internals of a reactor, and particularly relates to a process and a device for maintaining a bolt locking cap of a control rod guide cylinder of an upper reactor internals. Comprising a bolt torque reinspection tool and a locking cap automatic bending tool. The bolt torque reinspection tool is matched with a torque wrench to realize reinspection of bolt torque; the automatic bending tool for the locking cap is used for controlling the bulging claw to correspond to a groove of a locking bolt head and driving the bulging claw to press downwards to bend the locking cap, so that looseness prevention of the bolt is achieved. The device has the beneficial effects that a bolt torque reinspection tool and an automatic locking cap bending tool are conveyed to a working area through a ring crane, and the field environment is not changed; the bolt torque reinspection tool and the locking cap automatic bending tool are both of a long-rod-shaped structure as a whole, an operator can perform remote operation on an operation platform, and whether the torque of the guide cylinder bolt meets the locking requirement or not can be inspected in cooperation with a torque spanner.

The invention discloses a high-temperature-resistant electromagnetic coil for a control rod driving mechanism of a nuclear power station, which comprises a shell internally provided with a high-temperature electromagnetic coil, a lead end of the high-temperature electromagnetic coil upwards penetrates out of the shell, an electrical penetration piece is arranged at the joint of the lead end and the shell, the electrical penetration piece is arranged on the upper end surface of the shell, and the high-temperature-resistant electromagnetic coil is arranged in the shell. The lead wire end upwards penetrates out of the electrical penetration piece; the outer side of the electrical penetration piece is sleeved with an insulating cloth sleeve, the lower end of the insulating cloth sleeve is arranged on the outer side of the electrical penetration piece in a sleeving mode, and the upper end of the insulating cloth sleeve is arranged on the outer side of the lead wire end in a sleeving mode. Through the collaborative design of the shell, the electrical penetration assembly and the insulating cloth sleeve, the problems of difficult maintenance and poor heat dissipation of a traditional resin encapsulation process are solved, the dustproof, insulating and high-temperature-resistant performances are considered at the same time, and a more efficient and reliable high-temperature electromagnetic coil solution is provided for a control rod driving mechanism of a nuclear power station.

The mechanical arm tail end grabbing mechanism comprises a reinforcing frame, a clamping plate, a transverse moving block, a control rod, a material supporting component and supporting plates, the reinforcing frame is installed on a lifting machine, the lifting machine drives a device to move downwards, in the downward moving process, the material supporting component can drive the supporting plates to be far away from each other, the device is adjusted to the proper position, and then the device is clamped. An output shaft rotates to drive a transmission rod to rotate through a conveying component so as to drive a lead screw to rotate, the lead screw rotates to drive a control unit block to move, a grabbing rod rotates clockwise around the connecting position of the grabbing rod and a mechanical block to push a transverse moving block to slide in a transverse moving groove, and therefore a clamping plate on a grabbing plate grabs and clamps materials needing to be grabbed. In the process that the lifter drives the device to move upwards, the arranged material supporting component can drive the supporting plates to get close to each other to form a supporting face at the bottoms of materials, the materials needing to be grabbed and transferred are supported and protected, and the safety in the material grabbing and transferring process is guaranteed.

The invention belongs to the technical field of ceramic preparation, and relates to a preparation method and device of a high-purity porous boron carbide nuclear control rod. The high-purity porous boron carbide nuclear control rod is prepared by taking boron trichloride gas as a boron source, methane as a carbon source, argon as a carrier gas and a protective gas and hydrogen as a catalytic gas and a reducing gas, and the deposition temperature of boron carbide is increased by adopting a step-by-step and region-divided method from back to front, so that the deposition rate of boron carbide can be increased; the physical and mechanical properties of all parts of the prepared high-purity porous boron carbide nuclear control rod can be ensured to be consistent, the porosity and aperture of the prepared high-purity porous boron carbide can be regulated and controlled by changing the particle size of the boron carbide powder for preparing the boron carbide blank and cooperatively regulating the temperature, flow, pressure and deposition duration, and the high boron-carbon total content can be obtained; therefore, various actual requirements can be met.

The application relates to a neutron absorption material and application thereof to a control rod for a nuclear reactor core. The neutron absorption material provided by the application is prepared by mixing ytterbium elements and holmium elements in a certain proportion, can effectively play the high neutron capture cross-section characteristics of the ytterbium elements and the holmium elements, effectively absorb thermal neutrons, and can ensure good chemical and thermal stability, so that the neutron absorption material can maintain its structure and performance stability for a long time in a high irradiation environment, effectively avoids the conversion of the neutron absorption material into a weak neutron absorption material after absorbing neutrons, and further controls the neutron absorption characteristics of the neutron absorption material. Further, the neutron absorption material provided by the application can still ensure the neutron absorption characteristics thereof and maintain the reactivity value under high burnup depth, so as to prolong the service life of the control rod for the nuclear reactor core.

The invention discloses a cross section data calculation method and device and a rod position prediction method and system.The cross section data calculation method comprises the steps that according to a reactor core structure of a micro reactor, initial cross section data of the micro reactor under target working conditions are determined, and the target working conditions comprise working conditions corresponding to different insertion states of a control rod; determining a target SPH factor according to the initial cross section data and an SPH factor iteration method based on flux comparison; and correcting the initial section data according to the target SPH factor to obtain corrected section data under the target working condition. Therefore, the calculation precision of the section data of the micro reactor is improved.

The invention provides an anomaly detection method, system, equipment and medium for a control rod in a reactor, and the anomaly detection method comprises the following steps: obtaining standard optical signal information of a chain when the chain drives the control rod to move under a standard working condition by adopting a laser detection device; acquiring a plurality of actual optical signal information of the chain when the chain drives the control rod to move under different actual working conditions by adopting a laser detection device; based on different actual optical signal information and standard optical signal information, obtaining quantity information of the actual optical signal information when the quantity information is inconsistent with the standard optical signal information; in response to the fact that the number information exceeds a first threshold value, determining that the chain is abnormal, and stopping the motion of the driving control rod; and in response to the fact that the quantity information does not exceed the first threshold value, determining that the control rod is not abnormal under the driving of the chain. Through the anomaly detection method provided by the invention, whether the control rod breaks down in the moving process or not can be determined under the condition that the control rod is not contacted.

The invention provides a nuclear-grade hafnium plate preparation method and a nuclear-grade hafnium plate, and belongs to the technical field of nuclear fission reactor control rod neutron absorber material processing.The nuclear-grade hafnium plate preparation method comprises the steps that nuclear-grade sponge hafnium is adopted as a raw material, the oxygen content of a hafnium cast ingot is controlled within a specific range through a smelting technology, and the more obvious strengthening effect is achieved; and the strength of the finished hafnium plate can meet the nuclear pole requirement. Meanwhile, the deformation resistance of the material is increased, so that the problem that the high-strength hafnium plate is difficult to machine is further solved through optimal combination of forging upsetting, hot rolling, annealing, one-pass cold rolling, intermediate annealing, two-pass cold rolling and finished product heat treatment parameters, and the nuclear-grade hafnium plate with various properties meeting the technical requirements is prepared; the tensile strength and the welding strength of the hafnium plate are improved, the process is stable, and the yield reaches 95% or above.

The invention relates to the technical field of nuclear power equipment, in particular to forming equipment and a forming method. The forming equipment comprises a positioning device, a machining device and a hoisting device, the positioning device comprises a first positioning column and a second positioning column which are arranged in a spaced mode, the first positioning column and the second positioning column are suitable for being connected to center holes of two adjacent control rod guide cylinders, and the machining device comprises a first driving assembly, a second driving assembly and a tool bit assembly; the first driving assembly and the second driving assembly are both connected with the tool bit assembly, the first driving assembly is used for driving the tool bit assembly to rotate, and the second driving assembly is used for driving the tool bit assembly to ascend and descend so that the tool bit assembly can machine threaded holes in the upper surface of the control rod guide cylinder. And the water is hoisted into water by the hoisting device. The forming method comprises the step of remotely machining the threaded hole underwater by applying the forming equipment. By means of the forming equipment, threaded holes can be conveniently machined in the upper surface of the control rod guide cylinder underwater.

A wave energy conversion device, comprising a fluid flow channel which is configured to convert wave energy transmitted to the fluid flow channel into pneumatic energy; an energy conversion system which is connected to the fluid flow channel, is configured to convert the pneumatic energy converted by the fluid flow channel into electric energy, and comprises an air turbine, wherein the air turbine comprises a flow channel wall, two groups of flow guide blades and a group of rotor blades; and a pressure relief system which is connected to the fluid flow channel, is configured to control the pressure of an air chamber in the fluid flow channel, and comprises a valve disk, a valve seat, an elastic unit, a control rod and a connection tube, the control rod being fixedly connected to the valve seat, the control rod being movably connected to the valve disk and the control assembly, and the control assembly being deployed on a surface of the connection tube and configured to dynamically adjust, on the basis of sea conditions of the wave energy conversion device, an initial length of the elastic unit by means of the control rod so as to control opening threshold values corresponding to the valve disk.

The invention discloses a reactor control rod position control method and a related device, and the method comprises the steps: obtaining an original rod position sequence of a reactor control rod, decomposing the original rod position sequence, and obtaining M IMF components; inputting the M IMF components into a trained long short-term memory network model to obtain predicted values X1, X2,..., XM of the M IMF components, establishing an error evaluation index D-SMAPE according to the predicted values X1, X2,..., XM of the M IMF components and actual values thereof, and obtaining error coefficients delta Y1, delta Y2,..., delta YM corresponding to SWT-LMD subsequences; inputting the error coefficients delta Y1, delta Y2,..., and delta YM into a trained ResNet prediction model to obtain final IMF component prediction values Y1, Y2,..., and YM of the original rod position sequence; and controlling the control rod to act according to the final IMF component predicted values Y1, Y2,..., YM of the original rod position sequence. According to the method and the related device, the rod position of the reactor control rod can be accurately controlled.

A slide rail assembly includes a spring pressure device set including a base member with a stroke path and a step path, an elastic member, a slider and a control rod, and a slide rail including a first rail and a second rail with an activating member. The control rod moves on the stroke path and step path, allowing the slider to store elastic force through the stretch of the elastic member, and the slider to pop up through the elastic force of the elastic member. The spring pressure device set is installed on the first rail. When the second rail is received in the first rail, the activating member drives the slider and the control rod is locked at the base member. When the activating member is pushed, the control rod is unlocked, and the elastic member pops the slider out of the second rail.

The application discloses a nuclear power plant control rod guide tube, which comprises a protective cover and a full-range guide assembly installed in the protective cover; the full-range guide assembly comprises at least one full-range continuous guide element, and a full-range continuous guide channel is arranged in the full-range continuous guide element; the full-range continuous guide channel continuously guides at least one control rod in a single control rod assembly in a full range of the guide tube stroke. Compared with the prior art, the nuclear power plant control rod guide tube changes the non-continuous guide segment structure of the interval arranged guide panel into the full-range continuous guide segment formed by the long double-pipe structure, optimizes the control rod stroke protection function, reduces the risk of the control rod bending deformation caused by the transverse impact of the upper chamber fluid on the control rod, and guarantees the integrity of the control rod structure; meanwhile, the wear resistance of the specific position of the control rod guide tube is improved, so that the service life of the control rod guide tube is greatly prolonged, and the later operation cost is reduced.

This invention relates to the field of power work equipment technology, specifically a combined multi-functional live-line working insulated operating rod and its operating method. The operating rod includes a handle, a control rod fixedly connected to the top of the handle, an extension rod movably connected to the top of the control rod, and a tool connecting mechanism fixedly connected to the top of the outer wall of the extension rod. The control rod includes a control rod housing, a rotating rod rotatably connected to the inner wall of the control rod housing, and one end of the rotating rod extending to the outer wall of the control rod housing and fixedly connected to a handle. This invention, by incorporating a control rod, an extension rod, a tool connecting mechanism, and a small monitoring camera, achieves adjustable operating rod length through the cooperation of the control rod and the extension rod, meeting the needs of different working heights. Simultaneously, the design of the tool connecting mechanism makes tool replacement simple and quick, improving work efficiency, while the small monitoring camera enhances work safety.

The invention provides a rapid power reduction method and system based on an adjusting rod group and a pressurized water reactor, and relates to the technical field of nuclear reactors. According to the method and the device, the target rod group for rapid power reduction is selected from the grey rod group and the at least part of the black rod group in the adjusting rod group according to the target sequence, and the target sequence is the rod falling sequence determined based on the insertion sequence of the grey rod group and the at least part of the black rod group, so that rapid power reduction based on the adjusting rod group is realized; and the disturbance on the reactor core is small after the rod is dropped, and the influence on the shutdown capacity of a unit and the power distribution of the reactor core is reduced.

The application discloses a kind of determination methods and program products of core reactivity state, the method includes: the key state parameter in the process of core reaction is collected, key state parameter includes at least one of core power distribution parameter, coolant temperature, coolant density, control rod position, boric acid concentration and burnup;Determine the burnup step of fuel, the evolution process of fissile nuclide and fission product in core is modeled based on the burnup step of fuel and burnup model, to obtain the reactivity parameter related to the burnup of fuel, the burnup model is used to describe the nuclide transmutation and consumption logic of fuel during the operation of core;Corresponding digital twin is constructed with the reactivity state of the core, the reactivity state of the core is mapped by the digital twin based on the reactivity parameter and the key state parameter driving, can realize high-precision, real-time, full life cycle dynamic digital mapping and intelligent detection of core reactivity state.

The application relates to an anti-vibration ring network box, and relates to the technical field of ring network boxes, which comprises a box body, a mounting cavity is formed on the vertical surface of the front side of the box body, a box door for detachably mounting the opening of the mounting cavity is arranged, wire connection ports communicated with the mounting cavity are formed on the left and right side surfaces of the box body; a fixing seat located below the wire connection port is fixedly arranged on the inner wall of the box body, a sealing seat is rotationally connected to the upper side edge of the fixing seat away from the box door; a control rod is fixedly arranged on the side surface of the sealing seat facing the box door, an elastic extrusion piece is arranged on the inner wall of the box body, the elastic extrusion piece drives the control rod to rotate towards the fixing seat, a sealing gap is formed on the side surface of the fixing seat and the sealing seat away from each other, and an elastic pad is fixedly arranged on the inner wall of the sealing gap; the application reduces the possibility that the insulation layer and other parts of the external cable are damaged and broken due to long-term friction.

Systems and methods use inserted dividers with control rod drives (CRDs) to flush CRDs from inside a reactor. Dividers separate flush zones from the reactor. Pumps, injectors, gravity, or any other drive, potentially in combination with draining pumps, vacuums, or other suctioning device, flow the fluid through the divider into the zone and back out of the same for flushing out radiation and debris or bringing about any other desired condition. A handling pole may extend several meters to allow operators to reach any CRD and place the divider and flushing components about the same. Flow paths may extend with the pole to deliver and remove the flush fluid to divider ports. Additional cameras, locators, detectors, batteries, etc. may be used to inspect and clean. The systems may clean CRDs whenever accessible, such as after a control blade or rod has been removed during a maintenance outage.

This invention provides a method, apparatus, device, and medium for correcting control rod calibration curves. The correction method includes: acquiring a reference temperature curve during a load reduction period; correcting the reference temperature curve based on the negative reactivity introduced by xenon to generate a xenon correction curve; calculating an overheat correction curve based on a set balance coefficient, a primary loop completely untracked curve, and the xenon correction curve; calculating the power data in the overheat correction curve and its corresponding overheat correction power data based on the overheat correction curve and the reference temperature curve, and generating an overheat correction parameter set; and correcting the control rod calibration curve based on the overheat correction parameter set to generate a corrected control rod calibration curve. The method, apparatus, device, and medium provided by this invention can correct control rod calibration curves to adapt to different generating units.

The invention discloses an energy-saving compressed air drying device and a control method thereof, and relates to the technical field of air drying devices.The energy-saving compressed air drying device comprises a drying machine, an air inlet pipe is fixedly connected to the side wall of the drying machine in an inserted mode, the outer wall of the air inlet pipe is fixedly sleeved with a machine shell, and a one-way rotating disc is rotationally arranged in the machine shell; a plurality of adsorption discs are mounted on the one-way rotating disc, and the one-way rotating disc is movably inserted into the air inlet pipe. When the control rod is pushed by the driving part to move, the one-way rotating disc is controlled to rotate by 120 degrees, so that a new adsorption disc is moved into the air inlet pipe through rotation of the one-way rotating disc, replacement of the adsorption disc is achieved, shutdown is not needed when the adsorption disc is replaced, and the adsorption disc is more convenient to replace; when the one-way rotating disc rotates, the used adsorption disc is moved to the extrusion plate to be treated, then water in the adsorption disc is extruded through the extrusion plate, the water is discharged through the water outlet, and therefore the adsorption disc is more convenient to dewater.