750results about "Nuclear reaction control" patented technology

The invention relates to the field of reactor data processing, and particularly discloses a numerical calculation method for solving a neutron transport equation. The method comprises the following steps: 1, describing the geometry of a reactor core of a nuclear reactor by utilizing a construction entity geometric modeling method, and subdividing a curved surface grid along a curved surface structure; 2, directly expanding a neutron flux distribution function in each curved surface grid by using a multivariate polynomial; 3, deriving a neutron transport equation and an integral residual equation of a boundary condition under each curved surface grid; 4, solving geometric integral parameters of each curved surface grid; step 5, establishing an adaptive linear system; and step 6, iteratively calculating and solving a maximum characteristic value and an unknown expansion coefficient.

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.

A method for controlling a pressurized water reactor, computer program product and control system, the pressurized water reactor includes a reactor core and a primary cooling circuit. The primary cooling circuit includes a primary cooling medium, which includes: acquiring a plurality of measurable reactor process variables and obtaining a plurality of non-measurable reactor process variables. The method further includes calculating future axial offsets at the end of a predetermined prediction time interval for a plurality of different possible boration / dilution actions based on the plurality of measurable reactor process variables and the plurality of non-measurable reactor process variables, the axial offset being a normalized difference between power of an upper half of the reactor core and a lower half of the reactor core. The calculation of the future axial offset for each of the plurality of different possible boration / dilution actions is performed in parallel.

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 invention belongs to the technical field of nuclear power, and particularly relates to a device and method for relieving remote expansion of a cushion block locking cap of a heat insulation sleeve. Comprising a locking cap expansion device and a long rod, the long rod is used for remote operation above a pool, and the locking cap expansion device comprises a positioning pin, a positioning cylinder, a clamping gripper, an aligning and screwing operation head, an expansion head and a pressing expansion operation head. The device has the beneficial effects that a long-distance long rod is adopted to operate screwing positioning alignment and pressing expansion, and remote operation of locking of the cushion block locking cap is achieved. A special device integrating positioning of an expansion tool, screwing positioning of an expansion head, clamping and fixing and pressing expansion is adopted, underwater remote expansion integrated operation of the relieving cushion block locking cap is achieved, and the process steps are simplified.

The embodiment of the invention provides a reactor control method and device, electronic equipment and a storage medium, and belongs to the technical field of nuclear power. The method comprises the steps that the type of a steam turbine and a control strategy of a nuclear power unit are obtained, and the nuclear power unit comprises a reactor; according to the type of the steam turbine and the control strategy, an energy balance signal and a heat signal are calculated, the energy balance signal is used for indicating the minimum energy needed by operation of the steam turbine, and the heat signal is used for indicating the energy generated by the reactor; obtaining a feedforward signal according to the energy balance signal and the heat signal; and controlling the rod position action of the control rod according to the feedforward signal. According to the embodiment of the invention, the response speed and the adjustment capability of the nuclear power unit in the case of rapid load change can be improved.

The embodiment of the invention provides a self-adjusting shielding heat preservation device for a micro reactor and an operation method of the self-adjusting shielding heat preservation device, and relates to the field of nuclear reactors. The reactor comprises an outer shell, an inner shell, a control rod and a spiral flow channel, the inner shell is sleeved with the outer shell, an outer air inlet hole and an outer air outlet hole are formed in the outer shell, an inner air inlet hole and an inner air outlet hole are formed in the inner shell, a reaction cavity is formed in the inner side of the inner shell, and the spiral flow channels are arranged on the outer side of the inner shell and the inner side of the outer shell. The control rod is rotatably arranged on the side wall of the inner shell in a penetrating mode and located on the inner side of the outer shell, the control rod is provided with a control area and a non-control area, and the spiral runner is arranged between the inner shell and the outer shell; the outer gas inlet hole is used for inputting cooling gas, so that the cooling gas sequentially passes through the inner gas inlet hole, the reaction chamber, the inner gas outlet hole and the spiral flow channel and then is discharged from the outer gas outlet hole, and the cooling gas is used for flowing along the spiral flow channel and enabling the control rod to rotate so as to drive the control region to rotate into or out of the reaction chamber.

The invention discloses a research reactor fault detection method, device and system and a storage medium, relates to the technical field of nuclear power, and aims to at least solve the problems that a fault detection result is fuzzy and inaccurate, the troubleshooting workload is large and the fault processing efficiency is low. The method is applied to a research heap system and comprises event nodes, state nodes and a preset change trend, caused by fault events corresponding to the event nodes, of the state nodes associated with the event nodes. Comprising the steps of determining a first event node associated with a target state node under the condition that the target state node is detected to be in a fault state; determining a first state variable quantity of a state variable of a first state node associated with the first event node; and selecting a second event node of which the change trend of the first state change quantity associated with the event is the same as the target preset change trend corresponding to the first state node from the first event nodes, so as to determine the fault event of the second event node as a target fault event.

A nuclear reactor shutdown system includes a shielded path that passes through a reactor core fuel housed in a nuclear reactor vessel in a hermetically sealed manner, one end of the shielded path having an opening and another end of the shielded path being closed; a neutron absorber that is allowed to enter from the opening of the shielded path; an elastic member that is configured to urge the neutron absorber in a direction entering inside from the opening of the shielded path by being released from a compressed state; and a braking part that is disposed so as to maintain the compressed state of the elastic member and is configured to release the elastic member from the compressed state when the braking part reaches or exceeds a threshold temperature.

The application relates to a reactor core power distribution measurement uncertainty analysis method, device, equipment, storage medium and product. The method comprises the following steps: constructing a simulation operation state based on an actual operation state of a reactor core, determining state parameters of the reactor core in the simulation operation state, and obtaining group constants of the reactor core; performing calculation based on a material calculation subprogram and the state parameters to obtain material compositions of each fuel rod in the reactor core; performing calculation based on a power calculation subprogram and the material compositions of each fuel rod to obtain a real power distribution of the reactor core and obtain detector reaction intensities of the reactor core; determining power parameters of the reactor core in the simulation operation state based on the state parameters and the group constants, and performing flux map simulation based on the power parameters and the detector reaction intensities to obtain a simulation power distribution of the reactor core; and determining a measurement uncertainty of the reactor core power distribution based on a difference between the real power distribution and the simulation power distribution. The method can improve the accuracy and acquisition speed of the reactor core power distribution measurement uncertainty.

The invention provides a multipurpose small reactor control method, device, equipment and medium, and the method comprises the following steps: in an automatic temperature control mode, if the deviation between the actually measured temperature of a reactor outlet and the set temperature meets a preset automatic temperature control condition, determining a first control instruction of each adjusting rod of an adjusting rod group; a first control instruction is sent to an adjusting rod set executing mechanism so as to control an adjusting rod to move till the deviation between the actually measured temperature and the set temperature is within the temperature adjusting dead zone range; in the power automatic control mode, if the deviation between the set power and the actually measured power of the reactor meets a preset power automatic control condition, determining a second control instruction of the circulating pump of the intermediate loop; and a second control instruction is sent to the circulating pump executing mechanism so as to control the rotating speed of the circulating pump until the deviation between the set power and the actually measured power is within the power adjusting dead zone range. According to the invention, the temperature and the power are respectively controlled, and the control performance is optimized.

A control rod drive mechanism having a torque tube, a control rod assembly including a connecting rod and a spider, a lock cam assembly rotatably secured to a bottom end of the connecting rod and including a locking cam, and a locking collar disposed non-rotatably within the spider, the locking collar including a locking recess with an entry slot, wherein in a first axial position the lock cam assembly is rotatable with respect to the torque tube, and a second axial position the lock cam assembly is non-rotatable with respect to the torque tube.

The present invention relates to a reactor construction comprising an upper compartment above a reactor compartment, said reactor compartment being separated from the upper compartment by a radiation shield, wherein a molten salt reactor (MSR) is situated in the reactor compartment, the MSR comprising a reactor vessel with a reactor vessel lid assembly comprising a reactor vessel lid shield and a reactor vessel lid wherein a lifting element is situated in the reactor construction, the lifting element comprising: at least one bar being substantially vertical and axially adjustable along its longitudinal axis by a drive mechanism situated in the upper compartment, and wherein at least one through-hole for the at least one bar is provided in the radiation shield and wherein the reactor vessel lid shield has at least one receiving structure configured to engage with and lock to the at least one bar. The invention also relates to a method of performing a maintenance operation in the reactor compartment and a power barge comprising at least one reactor construction.

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.

An integral molten salt nuclear reactor includes a drain tank section configured to hold a volume of fuel salt. The integral molten salt nuclear reactor further includes a reactor section configured to receive the volume of fuel salt from the drain tank and cause fission reactions that heats the molten salt. The integral molten salt nuclear reactor further includes a heat exchange section configured to receive a flow of the heated fuel salt from the reactor section and remove heat therefrom.

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.

A nuclear engine system includes: a pump configured to pump a propellant; a fuel element including a set of nuclear fuel particles; a moderator configured to surround the fuel element and defining a set of moderator coolant channels configured to cool the moderator; a reflector including a neutron-reflecting material and a reflector coolant channel arranged within the reflector to cool the reflector, the reflector configured to at a first time, operate in a closed configuration to reflect neutrons to the fuel element to increase an energy flux, and at a second time, operate in an open configured to leak neutrons out of the engine system to decrease the energy flux; and a thrust nozzle configured to outlet propellant from the fuel element to produce thrust including a nozzle coolant channel arranged within a wall of the thrust nozzle configured to cool the nozzle.

A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs; and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.

The invention provides a MoAlB-SiC composite material as well as a preparation method and application thereof, and belongs to the technical field of ceramic matrix composite materials. The preparation method of the composite material comprises the following steps: mixing Mo powder, Al powder and B powder according to a molar ratio of 1: (1-2): 1, carrying out wet ball milling, drying, and carrying out vacuum pressureless sintering to obtain MoAlB powder; and S2, adding SiC particles with the mass percentage of 5%-20% into the MoAlB powder obtained in the step S1, carrying out wet ball milling, drying, and carrying out electric field assisted direct current heating rapid hot pressed sintering to obtain the MoAlB-SiC composite material. The MoAlB-SiC composite material obtained through the preparation method is high in density, secondary phases are reduced, the mechanical performance and the high-temperature oxidation resistance of the MoAlB material are enhanced by adding SiC, and the preparation method has great significance for preparing the high-strength MoAlB-based ceramic composite material.

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 method for controlling reactivity in a nuclear reactor is provided. The method comprises circulating coolant through the nuclear reactor. A composition of the coolant comprises water and gadolinium. The gadolinium is present in the coolant at a concentration suitable for controlling a neutronic reactivity of the nuclear reactor. A method for adjusting reactivity in a nuclear reactor and a coolant composition for a nuclear reactor are also provided.

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.

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.

A reactor control system for a nuclear reactor, the reactor control system comprising: one or more hollow tubes having a neutron absorbing material, each hollow tube having a first end and a second end; and a pump connected to the first end of each hollow tube and operable to control a quantity of a first fluid within the hollow tube, the first fluid comprising a neutron moderator, the pump being controlled based on a level of reactivity within the reactor; and the second ends of the hollow tubes being in fluid communication with a second fluid, the second fluid having a neutron moderating capacity that is less than 10% of the capacity of the first fluid.

The invention belongs to the technical field of material surface strengthening, and provides a boron-free nickel-based wear-resistant coating as well as a preparation method and application thereof. Mixed powder serves as a raw material, a base body is heated through an electric heating plate, the raw material is subjected to laser cladding through synchronous powder feeding, and a wear-resistant coating is formed on the surface of the base body; the mixed powder is prepared from the following components: 35.0 to 65.0 percent of zirconium carbide powder and 35.0 to 65.0 percent of nickel-based alloy powder; the nickel-based alloy powder comprises the following components in percentage by mass: 28.0 to 31.5 percent of chromium, 8.5 to 10.0 percent of iron, 0 to 0.1 percent of carbon and 58.4 to 63.5 percent of nickel. Compared with the prior art, the hardness of the obtained coating can reach 40 HRC or above, good normal-temperature and high-temperature wear resistance is achieved, and application of the coating in the field of control rod drive mechanism bearing strengthening is guaranteed.

The invention discloses a coated granular YHx-based moderator, and relates to the technical field of nuclear reactor materials, the coated granular YHx-based moderator comprises YHx particles and a coating layer, the chemical formula of the YHx particles is YHx, x ranges from 1.5 to 2, the coating layer sequentially comprises a loose pyrolytic carbon layer, an inner compact isotropic pyrolytic carbon layer, a silicon carbide layer and an outer compact isotropic pyrolytic carbon layer from inside to outside, and the thickness of the coating layer is 10 to 100 microns. The preparation method of the YHx particles comprises the step that high-purity metal yttrium particles directly react with high-purity hydrogen in a high-temperature vacuum environment to prepare the YHx particles. The preparation method of the coating layer is chemical vapor deposition. The coated granular YHx-based moderator is subjected to heat treatment, the heat treatment temperature is 1200-1500 DEG C, the heat treatment time is 1-2 hours, and the coated granular YHx-based moderator is suitable for being used as a moderator material in a nuclear reactor. The YHx particles are protected by the coating layer, so that the stability of the YHx particles in high-temperature and irradiation environments is improved, and the service life of the YHx particles is prolonged.

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.

To provide a nuclear power plant and a method for generating power in a nuclear power plant which can improve the load following property of a nuclear power generation plant and can further stabilize the output of a nuclear reactor.SOLUTION: The nuclear power plant having a nuclear reactor includes: an output control unit 70 for controlling the opening degree of an air extraction valve 13 according to a load request; and an energy storage unit for storing renewable energy. The output control unit 70 controls the temperature of water to supply to the nuclear reactor on the basis of the opening degree of the air extraction valve 13 and the amount of stored energy in the energy storage unit.SELECTED DRAWING: Figure 1