366results about "Nuclear reaction control" patented technology

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 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.

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.

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

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 invention relates to the technical field of nuclear reactor design, in particular to a safety assembly, a lead-cooled fast neutron reactor and a passive negative reactivity feedback method. The safety assembly comprises a first positioning piece, a second positioning piece and a containing piece. The first positioning piece and the second positioning piece are respectively connected with the accommodating piece so as to position the two ends of the accommodating piece in the linear direction, the accommodating piece is provided with an accommodating cavity for accommodating a coolant, and one end of the accommodating cavity in the length direction is communicated with the outside of the accommodating piece. The safety assembly is applied to the lead-cooled fast neutron reactor to serve as a safety barrier on the periphery of the reactor core, passive negative reactivity can be rapidly introduced, the structure is simple, implementation is convenient and fast, the nuclear reactor design specification and related technical requirements can be better met, and safety and reliability are further improved.

The invention discloses a neutron source assembly which comprises a neutron source rod body, a lower end plug, a composite upper end plug and a guide cylinder, and the neutron source rod body comprises a neutron source rod end plug, a neutron source rod cladding tube, an upper reflecting layer, a lower reflecting layer, a source box and a matched end plug. The neutron source assembly adopts the rod-in-rod design, the possibility of abrasion of the neutron source rod body in the transportation process and the like can be reduced, the neutron source leakage risk is reduced, the counterweight design of the composite upper end plug can counteract the buoyancy of a coolant in a reactor, and it is ensured that the neutron source assembly smoothly falls to the bottom and keeps stable; the neutron source rod body can be used in a pressurized water reactor and can also be used in a liquid heavy metal reactor. Meanwhile, the sealing packaging structure of the neutron source rod body can reduce the risk of neutron source leakage caused by abrasion in the transportation and in-reactor operation process, the arrangement of the guide cylinder provides guidance for the assembly of the neutron source rod body, and the probability of collision damage of the neutron source rod body in the assembly process is reduced.

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.

The invention discloses a nuclear rod power generation device, the nuclear rod power generation device comprises a nuclear fuel device, a neutron source device, a control assembly and a water pipe device, the nuclear fuel device is arranged in the water pipe device, and the water pipe device comprises a water inlet and a water outlet; the nuclear fuel device comprises an inner sleeve and an outer sleeve, the inner sleeve is arranged in the outer sleeve, the two ends of the inner sleeve and the two ends of the outer sleeve are connected in a sealed mode, a vacuum cavity is formed between the inner sleeve and the outer sleeve, and nuclear fuel coatings are arranged on the outer side of the inner sleeve and the inner side of the outer sleeve. The neutron source device is arranged on the inner side of the inner sleeve through a guide pipe, and the control assembly adjusts the position of the neutron source device in the guide pipe. The invention provides a nuclear rod power generation device which adopts a safe and miniaturized nuclear reaction technology and can replace a huge nuclear reactor.

To enable reactivity control using a simplified configuration.SOLUTION: A nuclear reactor 201 is provided, comprising: a core section 11 not including nuclear fuel; and a plurality of fuel drums (fuel units) 251 arranged so as to surround the core section 11, and each having a neutron absorbing part 55 for absorbing neutrons and a nuclear fuel part 56, where positions of the neutron absorbing part 55 and the nuclear fuel part 56 are adjustable relative to the core section 11.SELECTED DRAWING: Figure 3

To provide a lower component attaching / detaching device capable of easily attaching a spool piece to a main body of a control rod drive mechanism.SOLUTION: And a push-up mechanism 14 that pushes up and holds the spool piece 32a to a height at which the spool piece 32a can be attached to the drive mechanism body 31 of the control rod drive mechanism 3 in a case where the spool piece 32a that can be included in the control rod drive mechanism 3 that drives the control rod cannot be held by the lifting and lowering mechanism 11 due to the expansion and contraction of the plurality of fluid pressure cylinders 11a.SELECTED DRAWING: Figure 10

A high temperature control rod (22) for a nuclear fuel assembly (10) is described herein that includes a neutron absorbing material (24) having a melting point greater than 1500 °C that does not form a eutectic with a melting point less than 1500 °C, and may further include a cladding material (30) having a melting point greater than 1500 °C. The cladding material (30) is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material (24) is selected from the group consisting of Gd2O3, Ir, B4C, Re, and Hf. The metal cladding (30) or the absorbing material (24) may be coated with an anti-oxidation coating (26) of Cr with or without a Nb intermediate layer (28).

A measuring device for determining the power level of the reactor core is provided, which includes an in-vessel detection assembly. The in-vessel detection assembly comprises a rotatable housing that defines a cavity and a detection element positioned at a first angular portion of the cavity within the housing. A control drum for the reactor core and a system for monitoring the reactor power level are also provided.

The invention relates to the technical field of nuclear reactors, in particular to a control rod, a lead-based fast neutron high-flux research reactor and an experimental method thereof. Wherein the research reactor comprises a reactor container, a supporting platform, a shielding layer, a reactor lower chamber, a guide pipe and a control rod; a fuel assembly is arranged in the reactor container; one end of the guide pipe is located in the reactor container and is of a sealed structure, the length direction of the guide pipe is parallel to the length direction of the fuel assembly, the other end of the guide pipe sequentially penetrates through the reactor container, the supporting platform, the shielding layer and the under-reactor chamber and is located in the under-reactor chamber, and a driving mechanism matched with the guide pipe is arranged in the under-reactor chamber; the control rod is located in the guide pipe and can be driven by the driving mechanism to move in the length direction of the guide pipe. In a working state, the height of one end of the sealing structure of the guide pipe is not lower than that of the fuel assembly. According to the invention, the control rod can be installed, enough top space is reserved for the reactor vessel, and the reactor vessel has inherent safety characteristics.

An absorber-reflector unit (100) for a nuclear reactor control drum, the absorber- reflector unit comprising a base plate (10), a neutron-reflecting material (20), and neutron-absorbing material (30); at least one shaft (40) connected to the base plate and passing through the neutron-reflecting material, the at least one shaft being coupled to the neutron-reflecting material such that when the at least one shaft is rotated the neutron-reflecting material is rotated; and at least one attachment member (50), the at least one attachment member being at least partially housed within both the neutron- reflecting material and the neutron-absorbing material so as to couple the neutron- reflecting material to the neutron-absorbing material.

The invention belongs to the technical field of lead-bismuth reactors, and particularly relates to a lead-bismuth reactor control rod assembly positioning structure. The control rod cluster comprises an upper end positioning structure, a lower end positioning structure, a tuning fork type upper end plug and a tuning fork type lower end plug, the control rod cluster is located between the upper end positioning structure and the lower end positioning structure, the control rod cluster comprises 19 control rods, the upper end positioning structure is connected with the tuning fork type upper end plug in a matched mode, and the lower end positioning structure is connected with the tuning fork type lower end plug in a matched mode. The upper end positioning structure and the lower end positioning structure are located at the two ends of the control rod bundle and jointly achieve positioning of the control rod. On the basis of meeting the requirement of flow distribution uniformity of the control rod assembly coolant and overcoming transverse shaking of the control rod, the lead-bismuth coolant uniformly flows through the rod cluster type control rod and the transverse impact of the coolant on the control rod is reduced on the basis of realizing rapid assembly of the control rod assembly.

A system for use in shutting down a nuclear reactor without user intervention. The system is actuated by temperature exceeding a pre-determined upset condition and causing the gross failure or phase change of neutron absorbing material and / or additional fuses. When actuated, gravity causes the absorbing material to migrate from a non-active region of the reactor to an active region, shutting down the reactor.

Techniques for latching a shaft assembly with an integrated system are discussed herein. The integrated system including a nuclear reactor configured to raise a stem of the shaft assembly into a hold out. The hold out can include a sleeve, and metallic balls, the metallic balls being positioned in openings of the sleeve. The hold out can include a housing positioned around the sleeve and the metallic balls. The housing can include a gap that is narrower than a chamber of the housing. The hold out can include a spring coupled to the sleeve. The hold out can include an electromagnetic coil configured to engage the spring and the sleeve to raise the stem until the metallic balls are moved from positions between the gap of the housing and the stem, to positions between the chamber of the housing and the stem.

Proposed is a control rod fixing mechanism for a control rod assembly (100) with an assembly hole that passes through vertically, wherein the control rod fixing mechanism includes a control rod (110) inserted into the assembly hole and screw-fastened, an end plug (112) extended to an upper portion of the control rod and having a recessed fastening groove (112A) provided on an upper surface thereof and, and a cap member (120) provided with a fastening projection (121) that tightly fits into and secures the recessed fastening groove (112A) and configured to be inserted into and assembled with an open end of the assembly hole.

The application discloses a kind of optimal flow distribution methods under the total flow of given total flow in core life, and the method steps are as follows:1, input parameter: rod or plate fuel element core parameter, core power distribution parameter and assembly non-uniformity coefficient, core calculation control variable parameter.2, calculate channel total power.3, initial flow distribution calculation.4, flow distribution fine adjustment.5, compare the space-time maximum value of core assembly outlet temperature with the calculated value of last step, if greater, carry out next step calculation, if less than or equal to, set flow adjustment proportion coefficient, return to step 4.6, set assembly flow distribution as the calculated value of last step.7, core temperature distribution calculation.8, output optimal flow distribution scheme and core temperature distribution under the scheme.The advantages of the method are as follows:1, flow distribution scheme considers power change in whole life.2, flow distribution fine adjustment sets magnitude, to achieve rapid adjustment while ensuring the accuracy of adjustment amount.

The present disclosure discloses a method and an apparatus for determining a rod position of a control rod of a pressurized water reactor, a rod position measurement system and a non-volatile computer-readable storage medium, and belongs to the technical field of nuclear power. In the method for determining a rod position of a control rod of a pressurized water reactor, a rod position determination condition of each rod position of a full stroke is determined according to a Gray code bit signal voltage of the rod position of the full stroke, and Gray code bits and corresponding Gray code bit signal voltage values are enabled to correspond to rod positions, so that according to a real-time signal and by means of a rod position interval and the rod position determination condition, each Gray code bit signal, which is currently obtained in real time, can be accurately positioned to each rod position point, so that rapid and accurate full-stroke rod position measurement is realized, accurate full-core real-time rod position information is provided for an operator to perform monitoring, and precise full-core and full-fuel-cycle rod position measurement data is provided for use in reactor core operation tracking, reactor core safety calculation and fine fuel management.

The present application relates to a kind of high radiation resistance of control rod for stack entropy rare earth zirconate ceramic material and its preparation method and application, belong to nuclear reactor neutron absorption rod material technical field.The control rod ceramic material provided by the present application is prepared by using europium oxide, dysprosium oxide, thulium oxide and zirconium oxide as raw materials, according to certain proportion, after ball milling, calcination, green body forming and green body sintering process, and then processing to obtain the middle entropy rare earth zirconate ceramic material that can be applied to control rod.The rare earth zirconate ceramic material has excellent radiation resistance, large neutron absorption cross section and low reactivity value loss, and has high density, excellent thermal conductivity and low thermal expansion coefficient, and shows good application prospect in the field of control rod materials.

The application belongs to the technical field of nuclear energy functional materials and advanced ceramic preparation, and discloses a preparation method of high-uniformity europium hafnate nano-powder based on a complexation-gel method. 3+ With Hf 4+ Atomic-level uniform mixing, solves the microsegregation problem existing in the traditional preparation method, reduces the synthesis temperature, and the product is free of impurities and hard agglomeration, has excellent sintering activity, and is strong in process controllability and easy to be enlarged in engineering, is suitable for the preparation of nuclear reactor neutron absorption control rod materials, and has good industrial application prospect.

Proposed is a control rod assembly used in a reactor of a nuclear power plant and, more particularly, a control rod assembly with enhanced control rod worth using highly enriched B4C and for enhancing core safety under boron-free operation and top-mounted in-reactor instrumentation (TM-ICI) conditions, wherein the control rod assembly includes shutdown group neutron absorbers made of B4C comprising B-10 is enriched to at least 70%.

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, each of the functionally independent modules comprising a digital module or a combination digital and analog module, an analog module electrically coupled to one or more of the functionally independent modules, 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.