467 results about "Control rod" patented technology

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 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 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 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 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.

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.

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.

The application belongs to the technical field of control rod drive mechanism, and particularly relates to a heat insulation sleeve assembly of a magnetic lifting type control rod drive mechanism. The heat insulation sleeve assembly comprises a pipe base, a guide sleeve and a guide cover. The upper part of the pipe base is a first end, and the lower part is a second end. The radial dimension of the first end is larger than that of the second end. The lower part of the second end is provided with a first connecting end, and the guide sleeve is fixedly connected with the first connecting end of the pipe base. The upper part of the guide cover is provided with a fourth connecting end, and the lower part is provided with a horn cover. The fourth connecting end of the guide cover is fixedly connected with the second fixed end of the guide sleeve. The heat insulation sleeve assembly of the application is in a fixed state, and the problem of active wear of the heat insulation sleeve assembly is solved from the root.

This utility model relates to the field of dispersion technology, specifically a dispersion machine for producing fireproof sealant, comprising: a device body, the device body including an equipment body, a control rod disposed at the bottom of one side of the equipment body, and a disperser disposed at the bottom end of the control rod; an assembly structure sleeved on the outer wall of the control rod, the assembly structure including a control ring, and a threaded sleeve connected to the bottom end of the control ring. This utility model, by rotating the angle of the control ring, causes the threaded sleeve connected to the bottom end of the control ring to be rotatably connected to the outer surface of the bottom end of the control rod. The rotation of the threaded sleeve using a bearing does not affect the angle of the fixed ring, and the fixed ring and support frame limit the position of the threaded sleeve. The thread connects the control rod and the threaded sleeve, thereby achieving a rapid assembly effect between the control rod and the disperser, avoiding the problems of easily damaging the disperser by drilling screw holes, and the need to re-drill holes when the screw holes are severely worn, further causing damage.

The utility model provides a blowing and sucking all-in-one machine. The blowing and sucking all-in-one machine comprises a shell provided with a containing groove; the dust cup assembly is arranged in the accommodating groove; the locking and releasing assembly is arranged on the shell and comprises a releasing control element and a control rod, the releasing control element is provided with a first position and a second position, when the dust cup assembly is in a locking state, the releasing control element is located at the first position, and when the dust cup assembly is in a releasing state, the releasing control element is located at the second position; the release control element is located at the second position so that the dust cup assembly can be loosely located in the containing groove. Wherein the second position is obtained by limiting the release control element through the control rod. According to the blowing and sucking all-in-one machine, the locking and releasing assembly is arranged on the shell, the control rod and the releasing control element in the locking and releasing assembly are matched with each other to control locking and releasing of the dust cup assembly, and when the dust cup assembly is in the releasing state, the dust cup assembly can be loosely located in the containing groove, so that the dust cup assembly is conveniently taken by a user.

The invention discloses a simulation device for a small low-temperature reactor control rod position closed-loop control system, particularly relates to the technical field of low-temperature reactor control, and is characterized in that a combination valve simulation load is used for generating a high-voltage signal based on a received high-voltage direct-current signal of a control rod driving mechanism and performing voltage reduction processing on the high-voltage signal to obtain a high-voltage signal; a low-voltage signal is obtained; the analog quantity voltage acquisition module is used for receiving the low-voltage signal and analyzing and processing the low-voltage signal to obtain a control rod simulation action; the PXI controller is used for receiving a control rod simulation action to generate a rod position simulation value and calculating a binary code value of the rod position simulation value; the switching value signal output module is used for outputting a switching value signal based on the binary code value of the received rod position simulation value so as to control the rod position simulation module; and the rod position simulation module is used for generating and outputting a rod position simulation signal under the control of the switching value signal output module based on the received rod position excitation signal of the rod position measurement device.

The utility model relates to the technical field of parts spraying, disclose a kind of cable bridge bracket, including adjusting sleeve, the inner wall sliding connection of adjusting sleeve has stand, the inside sliding connection of adjusting sleeve has control rod, the outer wall fixed connection of control rod has rotating rod, the inner wall rotation connection of rotating rod has fixed shaft, the both ends fixed connection of fixed shaft have fixed link, the inner wall fixed connection of rotating rod has locking rod, the bottom fixed connection of adjusting sleeve has bridge seat, the inner wall fixed connection of bridge seat has cable rack, the bottom of adjusting sleeve is equipped with the installation component of being installed with ease. In the utility model, press control rod compression spring, push rotating rod to make locking rod separate from adjusting sleeve to adjust bridge height, spring reset lock after loosening, realize tool-free adjustment and automatic locking by spring and lever principle, stable and suitable for complex working conditions.

To adjust a core flow rate higher than that in a stationary state when a power change operation of a natural circulation reactor is conducted by a control rod, thus improving a power change speed while maintaining a stable condition.SOLUTION: A nuclear power plant includes a large-diameter space chimney at an upper part of a reactor core within a shroud of a reactor pressure vessel. The nuclear power plant includes: a coolant flowmeter configured to measure a coolant flow flowing into the reactor core; a water level gauge configured to measure a water level of a coolant within the reactor pressure vessel; a water-supply flowmeter connected to the reactor pressure vessel and configured to measure a water-supply flow rate; a monitoring device configured to monitor the coolant flow, the water level and the water-supply flow rate; and a controlling device configured to control a control rod and the water-supply flow rate. The controlling device is configured to: calculate, in advance, a fluctuation margin of a core flow rate by a time lag of the water-supply flow rate; change a target value of the water level to be higher than a fluctuation margin of the water level corresponding to the fluctuation margin of the core flow rate so as to change the water-supply flow rate and then change the water level; and thereafter operate and control a position change of the control rod.SELECTED DRAWING: Figure 4

The utility model discloses a multifunctional foreign matter extractor for a coated film, which comprises a control rod, and the bottom of the control rod is fixedly connected with a lower clamping plate; and the control assembly comprises an upper clamping plate, and the upper clamping plate is rotationally connected to the top of the control rod. When the clamping device is used, air in the pressing bag can enter the telescopic bag through the telescopic air pipe by pressing the pressing bag, the telescopic bag is expanded, the upper clamping plate can rotate along the outside of the control rod after the telescopic bag is expanded, meanwhile, the upper clamping plate is close to the lower clamping plate, and therefore the purpose of clamping is achieved. In the using process of the whole device, if the length of the whole device needs to be adjusted, a control rod can be rotated to drive a threaded rod to rotate in an internal thread of a threaded sleeve, so that thread displacement can be achieved, the purpose of stretching and retracting in the length direction is achieved, and the practicability of the whole device is improved.

The invention relates to a reactor shutdown method and system, and the method comprises the steps: a reactor protection system receives a monitoring signal and carries out the preprocessing of the monitoring signal, and obtains a preprocessing signal; the reactor protection system is designed by adopting a plurality of safety sequences; the reactor protection system judges whether an emergency shutdown condition is met based on the pre-processing signal; if yes, the reactor protection system outputs a local shutdown signal; if not, not outputting the local shutdown signal; the control rod shutdown subsystem receives the local shutdown signal and cuts off a power supply of a control rod driving system according to the local shutdown signal; and the shutdown rod shutdown subsystem receives the local shutdown signal and cuts off a power supply of the shutdown rod driving system according to the local shutdown signal. According to the invention, the emergency shutdown of the reactor can be rapidly and effectively realized under the accident condition, the influence of common cause failure on the shutdown function can be effectively avoided, and a diversified instrument control system does not need to be designed to cope with the influence of the common cause failure of the reactor protection system.

The utility model relates to copper foil detection field discloses a copper foil tensile strength detection device, including bottom plate, first clamping unit, second clamping unit, drive unit, the bottom plate is equipped with support plate, support plate first clamping unit and second clamping unit are connected in sequence on the bottom plate, drive unit includes first drive module, control rod, ratchet, pawl, elastic part, first drive module is connected on the support plate, and the power output end of first drive module is connected with first clamping unit, the ratchet is connected on first drive module, the pawl rotation is connected on the support plate, one end of elastic part is connected with support plate, and the other end is connected with pawl, control rod sliding is connected on the support plate. This detection device can improve the convenience of detecting tensile strength and tensile endurance.

The application provides a control rod uncontrolled lifting accident analysis method of a reactor, including providing a first neutron dynamics model, and setting a shutdown protection signal, the shutdown protection signal including an over-power protection signal and a period protection signal; carrying out power spectrum analysis according to the first neutron dynamics model to obtain a transient peak power; obtaining a transient MDNBR based on the transient peak power and initial thermal parameters of the reactor; comparing the transient MDNBR with a safety analysis limit value, if the transient MDNBR is less than or equal to the safety analysis limit value, then carrying out a system optimization operation and returning to carry out the power spectrum analysis until the transient MDNBR is greater than the safety analysis limit value. The application only carries out neutron dynamics calculation and does not carry out thermal flow and heat transfer calculation, the calculation process is the most conservative, for example, if the accident analysis process only carries out a first analysis stage, the analysis process is the most simple, and the work efficiency of the accident analysis can be greatly improved.

This invention belongs to the field of nuclear power control rod processing technology, specifically relating to a chromium plating method and a continuous-pass chromium plating apparatus for ultra-long, ultra-fine, thin-walled cladding tubes used in nuclear power control rods. The chromium plating method includes pretreatment and chromium plating treatment. The pretreatment includes degreasing and cleaning the ultra-long, ultra-fine, thin-walled cladding tube. The chromium plating treatment is a continuous-pass chromium plating process, in which the pretreated cladding tube is continuously passed horizontally and at a uniform speed along its axial direction through at least one chromium plating tank. The cladding tube is supported by a support structure as it passes through each chromium plating tank, maintaining horizontal linear movement. Within each chromium plating tank, an annular anode surrounds the movement path of the cladding tube, and a pulsed power supply applies a cathode current to the cladding tube for pulse electroplating. This invention, by employing a uniform-speed continuous-pass chromium plating method and using an annular anode, ensures that the chromium plating time and current conditions are consistent along the entire axial length of the workpiece.

The invention discloses a barrier-free 360-degree rotating water sprayer which comprises a rotating body, a water outlet assembly and a water supply seat, a water drainage cavity communicated with the water outlet assembly and the water supply seat is defined in the rotating body, and a reversing assembly and an impeller are arranged between the water drainage cavity and the water outlet assembly; the reversing assembly comprises a reversing seat, a control rod, two adjusting seats and a control ring, the two adjusting seats are provided with two oppositely-arranged limiting walls, the control ring is provided with a transition groove and a reversing rod, the end of the control rod abuts against the groove wall of the transition groove and is spaced from the limiting walls, and the reversing rod is stopped on the limiting walls and forces the control rod to swing to switch the water outlets. The water outlet assembly comprises a plurality of water outlet heads, eccentric water outlet nozzles are arranged on the water outlet heads, rotating water retaining rings are arranged on the water outlet nozzles in a sleeving mode, water retaining protrusions are arranged on the water retaining rings, and the water retaining protrusions are partially exposed in front of the water outlet nozzles so that the spraying posture of water flowing through the water outlet nozzles can be changed.

The application discloses a liquid heavy metal cooling micro small reactor control rod drive mechanism which is composed of a motor drive transmission mechanism, an outer cylinder, a supporting cylinder, a rod position measurer, an electromagnetic clutch mechanism, a screw rod connecting rod, a guide pipe and a gas protection system; a speed reducer and a drive motor in the motor drive transmission mechanism are installed upside down at the lower end of a gear transmission box in sequence, a rotating cylinder is coaxially installed in the outer cylinder and is installed at the lower end of the gear transmission box through a connector at the upper end; the rod position measurer is fixedly installed on the outer wall of the outer cylinder; the electromagnetic clutch mechanism is fixedly installed at the lower end of the outer cylinder and the rotating cylinder; the lower end of the screw rod connecting rod is fixedly connected with a control rod, and the upper part is in screw thread cooperation with a ball nut of the electromagnetic clutch mechanism. The single motor and the electromagnetic clutch mechanism are adopted, the liquid heavy metal buoyancy is fully utilized, the spring is assisted, the control rod adjusting and falling rod functions are realized, the height and weight above the top cover are reduced, the metal vapor is avoided from escaping through the gas protection system, the structure is compact, and the safety and reliability are high.

The invention relates to a control method and device for a high-temperature gas cooled reactor, and the method comprises the steps: responding to a received power automatic control instruction inputted by a user, and obtaining a power automatic control parameter; and performing rod position control on each control rod in a control rod group of the high-temperature gas cooled reactor based on the automatic power control parameters, and acquiring and displaying at least one parameter of the high-temperature gas cooled reactor in the rod position control process.