387results about "Containment" patented technology

To dismantle a nuclear facility affected by a severe accident in an underwater environment by submerging the facility in water so that the water shields radiation from the nuclear facility.SOLUTION: The method for dismantling a nuclear facility includes: stopping water leakage at a leakage portion by using a particle dispersion liquid containing fine particles having a specific gravity greater than that of water, when dismantling a nuclear facility in which the water leakage portion has occurred due to a severe accident; and submerging at least a part of the nuclear facility. This makes it possible to submerge a reactor well and to perform dismantling work from above a reactor building.SELECTED DRAWING: Figure 1

An installation includes: a plurality of pilings securable to a bed under a surface of a body of water; a base structure disposed atop the plurality of pilings; and a module disposable on the base structure, wherein the module is positioned and securable on the base structure after being floated on the surface of the body of water over the base structure.

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.

To suppress horizontal vibration of a nuclear pressure vessel during an earthquake, and make a dynamic vibration absorber compact to suppress an installation space of the dynamic vibration absorber, in a nuclear power plant.SOLUTION: An earthquake resistance support device for a nuclear power plant is arranged in a reactor containment vessel, and suppresses horizontal vibration of a reactor pressure vessel supported by a pedestal when an earthquake occurs. The earthquake resistance support device comprises a horizontal beam that is arranged between the reactor containment vessel and the reactor pressure vessel, and the pedestal, and extends in the radial direction of the reactor pressure vessel and the pedestal; and a dynamic vibration absorber installed on the horizontal beam. The dynamic vibration absorber comprises a hollow weight extrapolated to the horizontal beam and movable in an axial direction of the horizontal beam, and a coil spring device that elastically supports the hollow weight in the axial direction of the horizontal beam, to allow the hollow weight to vibrate in the axial direction of the horizontal beam.SELECTED DRAWING: Figure 3

This invention discloses an in-core component with highly uniform core outlet flow rate and its design method, relating to the field of nuclear reactor design technology. It solves the problem of poor uniformity in coolant flow distribution at the core outlet in existing reactors, balances flow resistance at various points at the core outlet, and reduces lateral flow between different channels. The specific solution is as follows: it includes a core top plate and a support column assembly mounted above the core top plate. The core top plate is provided with several water flow holes and mounting holes. The water flow holes consist of circular and square water flow holes. The circular water flow holes are divided into first and second circular water flow holes with different functions. The area ratio of the square water flow holes to the circular water flow holes is 1.1:1 to 1.3:1.

To facilitate separation of fuel debris from a cut-off material and reduce the amount of waste without increasing the amount of cut-off materials.SOLUTION: There is provided a leakage part blocking method for a reactor pressure vessel which blocks a leakage point (opening) at the bottom of the reactor pressure vessel by using a cut-off material. The method uses a camera mounted on a remote device to confirm the shape of the leakage point from the outside of the reactor pressure vessel, when the shape of the leakage point is known, operates the remote device to insert and fix a plug, patch, or mortar being the cut-off material from the outside of the reactor pressure vessel to the leakage point to block the leakage point, when the shape of the leakage point is unknown but the position of the leakage point can be identified, operates the remote device to insert a bag containing fluid to be solidified with accumulation and expansion being the cut-off material from the outside of the reactor pressure vessel to the leakage point, and then, blocks the leakage point with the bag in which the fluid is accumulated and expanded.SELECTED DRAWING: Figure 2

This invention discloses a passive spray system for aerosol removal in nuclear power plants, comprising: a condensate collector, a guide pipe, a spray water tank, a spray pipe, a burst valve, and nozzles. The condensate collector is connected to the spray water tank via the guide pipe and is used to collect condensate within the containment. The spray water tank is connected to the nozzles via the spray pipes. The burst valve is installed on the spray pipes. When the pressure inside the containment reaches the activation trigger pressure of the burst valve, the burst valve opens, and water from the spray water tank flows into the nozzles through the spray pipes, where it is sprayed to remove aerosols from the containment. The beneficial effects of this system are as follows: compared with natural removal methods, this system provides more efficient removal of suspended aerosols within the containment; compared with active spray systems, this system does not require pumps and power supplies, and has higher reliability under accident conditions; this system can collect condensate near the walls, providing a more sustainable water source for the spray system.

The embodiment of the invention relates to the field of cooling devices of pressure vessels, in particular to an oxygen control device, a lead-bismuth reactor and a method for adjusting the oxygen content of lead-bismuth alloy in the reactor. According to the oxygen control device provided by the embodiment of the invention, the oxygen content data of the lead-bismuth alloy in the container is measured and obtained in real time by arranging the measuring piece and the control assembly, and then the oxygen content level in the container is adjusted in real time by utilizing the deoxygenation mass exchanger and the oxygen release mass exchanger; therefore, the oxygen concentration in the lead-bismuth alloy is accurately maintained in a preset range, so that stable operation of a cooling system is ensured; the closed space is formed among the container, the oxygen removal mass exchanger and the oxygen release mass exchanger, so that the oxygen content adjustment process of the lead-bismuth alloy is realized in a closed environment, impurities are prevented from being mixed in, and the quality of the lead-bismuth alloy is ensured. According to the lead-bismuth reactor provided with the oxygen control device, the content of oxygen in the lead-bismuth alloy can be actively adjusted, and long-term stable operation of the reactor is achieved.

A limit stop relates to devices for limiting the effect of severe accident consequences on process equipment connected by pipelines passing through walls. The stop may be used, in particular, in the nuclear industry. The limit stop installed in a protective wall. The stop is made in the form of an anchor with horizontal grooves and an insert into the pipeline with horizontal teeth. The anchor is mounted on a protective wall. The insert is installed on the pipeline from the outer side of the protective wall. The anchor and insert are made with the possibility of locking the teeth in the grooves during torsion. The insert is provided with a postulated break site. The stop makes it possible to increase the safety of operation of high-pressure pipelines.

Described herein are structures forming modules, such as modules for use in nuclear reactor buildings, and related systems and methods. A representative structure may include a first plate, a second plate positioned parallel to and spaced apart from the first plate, and a support assembly positioned between the first and second plates. The support assembly may include a column, a first beam extending from the column parallel to the first and second plates, and a second beam extending from the column parallel to the first and second plates. The panel structure may further include a plurality of tie plates extending between and connecting the first and second plates. The tie plates may support the first and second beams. The panel structure may further include a filler material, such as concrete, between the first and second plates and surrounding the support assembly and the tie plates.

The present invention relates to a nuclear power plant with improved steam explosion mitigation performance, the nuclear power plant comprising: an integrated reactor including a hemispherical first portion inside which a core and a steam generator are positioned and a cylindrical second portion positioned above the first portion; a containment vessel for accommodating the integrated reactor, having a cooling space surrounding the integrated reactor, and including a first containment portion facing the first portion and a second containment portion facing the second portion; and a lower structure which is located in the cooling space and is located under the integrated reactor, wherein the lower structure comprises a first plate and a second plate disposed below the first plate, and the first plate and the second plate are arranged in a horizontal direction and face each other.

The invention provides a pressure-bearing annular sealing device suitable for a nuclear island containment vessel and an installation method of the pressure-bearing annular sealing device. The sealing device comprises a first supporting mechanism, a sealing mechanism and a second supporting mechanism, one end of the first supporting mechanism is connected with the steel containment, the other end of the first supporting mechanism extends towards the wall of the shielding plant, one end of the second supporting mechanism is connected with the wall of the shielding plant, the other end of the second supporting mechanism extends towards the steel containment, and the first supporting mechanism and the second supporting mechanism are correspondingly arranged in the circumferential direction of the steel containment and form an annular mounting gap; the sealing mechanism is connected to the annular mounting gap in a sealing mode and comprises elastic buffering pieces arranged in the axial direction and the radial direction of the steel containment correspondingly, and the elastic buffering pieces abut against the position between the first supporting mechanism and the second supporting mechanism correspondingly.

The invention relates to a supporting device for nuclear power station equipment. The supporting device comprises a supporting body and at least one mounting assembly. A first supporting part and a second supporting part which extend in the circumferential direction of the supporting body are formed in a protruding mode in the peripheries of the two opposite ends of the supporting body in the longitudinal direction of the supporting body. At least part of the outer end, protruding out of the supporting main body, of the second supporting part and the inner wall of the target opening are arranged at intervals; all the mounting assemblies are matched and connected to the outer ends, spaced from the inner wall of the target open hole, of the second supporting part in the circumferential direction of the supporting main body at intervals; the mounting assembly comprises a mounting piece and a fixing piece, and the mounting piece is connected to the corresponding outer end in a matched mode; the fixing piece is movably connected to the installation piece in a matched mode. The first supporting part of the supporting body is in lap joint with the edge of the target hole, and the second supporting part extends into the target hole and abuts against the inner wall of the target hole through the fixing piece in the installation assembly. The supporting device can be stably supported in the target open hole, and the supporting device is simple in structure and convenient to operate.

A reactor containment vessel vent system continuously releases steam generated in a reactor containment vessel to the atmosphere even when a power supply is lost. In the reactor containment vessel vent system, the noble gas filter that allows steam to pass through but does not allow radioactive noble gases to pass through among vent gas discharged from the reactor containment vessel is provided at a most downstream portion of the vent line. An immediate upstream portion of the noble gas filter and the reactor containment vessel are connected to each other by the return pipe via the intermediate vessel. When the radioactive noble gases having pressure equal to or higher than predetermined pressure stay in the immediate upstream portion of the noble gas filter, the staying radioactive noble gases flows into the intermediate vessel by the relief valve. Thus, steam permeability is maintained and the system continuously releases the steam.

The present application relates to a reactor pressure vessel protection method and system, the method comprising the following steps: when the unit is in a downward state, judging whether the residual heat removal system is in an effective state, if the result is yes, generating a cold-state overpressure protection signal for activating a cold-state overpressure protection means; if the result is no, further judging whether the primary loop average temperature is less than a first conversion temperature, if the result is yes, generating the cold-state overpressure protection signal; when the unit is in an upward state, judging whether the primary loop average temperature is greater than a second conversion temperature, if the result is yes, generating a hot-state overpressure protection signal for activating a hot-state overpressure protection means; the present application can control the unit to switch between the cold-state overpressure protection state and the hot-state overpressure protection state according to the primary loop average temperature, thereby executing the corresponding overpressure protection means, and effectively preventing the reactor pressure vessel from breaking.

An end fitting for a pressure tube in a nuclear reactor system includes an inboard end configured to surround and be joined to the end of the pressure tube in a fluid tight manner by a rolled joint. The rolled joint includes a grooved region having at least one annular groove. The end fitting also incudes a wettable inner surface that extends axially outboard from an outboard-most annular groove of the grooved region. The end fitting also incudes a corrosion barrier applied to form a coated portion of the wettable inner surface. The coated portion extends from a first position that is at or outboard of a coating reference position at the outside edge of the outboard-most annular groove, to a second position. An axial extent of the coated portion, measured axially from the coating reference position to the second position, is at least about 20 mm.

The invention is suitable for the technical field of nuclear power, and provides a containment pressure test control method and device and electronic equipment, and the method comprises the steps: receiving a test instruction for carrying out a pressure test on a containment; and if the test instruction is an instruction for performing pressure relief treatment on the containment vessel, controlling a corresponding regulating valve according to a predetermined opening degree of the regulating valve of a nuclear auxiliary plant ventilation system DVN so as to guide gas of the containment vessel to enter the DVN system through a containment vessel ventilation system EBA to be discharged. By means of the method, the duration needed by the pressing test can be shortened, and the operation efficiency of the unit is improved.

A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head. Thus, any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core. This arrangement reduces the opportunity for differential movement between the control elements and the reactor core.

The invention belongs to the technical field of nuclear power plant containment penetration piece isolation valve sealing tests, and particularly relates to a rubber sealing and blocking structure and a test method. Comprising a self-sealing type rubber sealing plug and a pressing type rubber sealing plug and is used for sealing and plugging an outlet of the check valve. The self-sealing type rubber sealing plug comprises first chains, a rubber sealing ring and a plug structural body, the plug structural body is a main body part of the plug, the annular rubber sealing ring is installed in a groove of the plug structural body to play a sealing and plugging role, and the multiple first chains made of metal materials are fastened in the plug structural body. The device has the advantages that a penetration piece swing check valve sealing test method is optimized, a systematic test method is optimized into a valve single body sealing test, and the device has the functions that a check valve rocker arm is not disassembled, and a rubber part can be replaced on site for reuse.

A nuclear installation comprising at least one modular nuclear reactor (SMR) and a reactor vessel well delimiting a water basin in which the SMR reactor unit is immersed. The invention relates to a nuclear installation comprising: at least one SMR reactor unit (4) for heat generation, delimited by a reactor vessel (40, 41, 42); a reactor vessel well (100) delimiting a water-filled basin (B) forming part of a secondary circuit, in which the reactor vessel is immersed; at least one heat exchanger (49) between the primary circuit of the SMR reactor and the secondary circuit, arranged outside the reactor vessel and in the water basin. Figure for the abstract: Fig. 6

This application discloses a floating nuclear power generation system with a more robust emergency power supply system. [Solution] A floating nuclear power generation system comprising a reactor, a turbine generator driven by steam generated by the heat of the reactor, a floating body on which the reactor and turbine generator are arranged and which is moored at sea, and a floating power supply system having an emergency system capable of supplying power to predetermined equipment for cooling the reactor in an emergency, and a normal system capable of supplying power to equipment not connected to the emergency system, wherein a normal power generation facility that generates electricity using natural energy is connected to the emergency system.

According to an embodiment, a nuclear plant has: a plurality of inner shell radial rebars 27 that are arranged at least partially in a base slab 26 of a double shell containment vessel 20, arranged radially having a center line of the base slab as a center of radiation angle, and penetrate an inner shell base part 21a; a plurality of outer shell radial rebars 28 that are arranged radially having the center line of the base slab as a center of radiation angle, and penetrate the outer shell base part 22a; and a plurality of common radial rebars 29 that penetrate both the inner shell base part 21a and the outer shell base part 22a, being a part of the inner shell radial rebars 27 and also a part of the outer shell radial rebars 28, wherein the number of the outer shell radial rebars 28 is larger than the number of the inner shell radial rebars 27; and the maximum number of the common radial rebars 29 is equal to the greatest common divisor of the number of the inner shell radial rebars 27 and the number of the outer shell radial rebars 28.

A liquid metal cooled nuclear reactor includes a passive decay heat removal system having thermal insulation attached to a wall of a cold source reservoir that holds a phase change material, where the insulation is arranged to automatically fall by gravity from the wall in response to the wall reaching a predetermined temperature. The nuclear reactor may be a fast neutron reactor that incorporates an integral system having a final cold source with a reservoir incorporating an integral exchanger divided into a plurality of parallel tubes between which a phase change material is inserted, the reservoir being surrounded by a thermal insulating layer that can be detached in a passive manner in the event of reaching a predetermined threshold temperature.

The utility model discloses a fastener for a top cover of a reactor pressure vessel of a nuclear power station, which comprises a chuck and a penetrating rod, a fixing shaft is arranged at the connecting position of the penetrating rod and the chuck, a threaded rod is arranged at the upper side position of the penetrating rod, a fixing nut is arranged at the external position of the threaded rod, and the fixing nut is connected with the chuck. Rubber pads are arranged on the outer sides of the penetrating rods, the clamping plates can rotate in the inner grooves, the rotating plates can rotate on the clamping plates through the movable shafts, the connecting holes and the clamping holes are used for being matched with connecting bolts to conduct fixing and other operations, and the overall height of the chuck can be increased according to needs. Therefore, nuclear power plant reactor pressure vessel top covers (hatch covers) with different thicknesses can be effectively clamped, the application range of the fastener is greatly widened, fasteners with different specifications do not need to be frequently replaced due to the thickness difference of the hatch covers, and the use cost and the reserve pressure of spare parts are reduced.

Device and Method for Maintaining a Pressure Reactor Containment The present invention relates to a maintenance device (10) for a pressure reactor containment, comprising a connecting fitting (120) on a wall (20) of the containment, said connecting fitting (120) extending in a longitudinal direction (X) between an internal base (55) and an external base (60) and comprising: a) an insertion portion (65) intended to be positioned in a receiving recess (90) machined in the wall (20) of the containment, b) an external portion (70) intended to be positioned outside (30) of the containment and comprising a support element (105) intended to be placed opposite the wall (20) of the containment on a periphery (P) of the receiving recess (90), a fluid conduit (75) extending through the connecting fitting (120), a groove (88) of reception of a compression seal (100) being provided in the insertion portion,the maintenance device (10) comprising means for fixing said connecting branch (120) to the wall (20). Figure for the abbreviation: 4,

The invention relates to the field of nuclear reactors, in particular to a lower chamber structure suitable for a pressurized water reactor. The lower chamber structure is characterized in that a reactor core supporting plate is welded at the lower end of the hanging basket barrel, and a water flowing through hole is formed in the reactor core supporting plate; a plurality of radial supporting key grooves are uniformly formed in the lower surface of the reactor core supporting plate in the circumferential direction; a plurality of radial supporting keys are arranged on the RPV lower sealing head, the positions of the radial supporting key grooves correspond to the positions of the radial supporting keys, and the radial supporting keys extend into the corresponding radial supporting key grooves in the reactor core supporting plate; supporting tables are arranged on the two sides of the radial supporting key; a flow distribution cover is hung on the supporting table; drain holes are formed in the surface of the flow distribution cover; and a vortex suppression assembly is arranged in the flow distribution cover and is connected with the reactor core supporting plate. Through the integral flow distribution cover structure, the flow distribution structure is simplified; the reactor core supporting structure is simplified through the reactor core supporting plate, and meanwhile, the secondary supporting structure is simplified through the radial supporting keys on the RPV. And generation of unstable eddy current is inhibited through the eddy current inhibition assembly.

There is provided a nuclear reactor 21, 23 comprising a reactor vessel (37, Fig. 6) having a central longitudinal axis (30) defining an upper (40) and lower (42) end. Within the reactor vessel is an i

The heat conduction containment is provided with a concrete shell (1) and a bottom plate (2) and is characterized by further comprising a first steel shell (3), a second steel shell (4), a plurality of annular partition plates (5) and an exhaust water conveying pipe (6), the concrete shell (1) is arranged on the outermost side, the first steel shell (3) is arranged on the inner edge face of the concrete shell (1) in an attached mode, the second steel shell (4) is arranged in the first steel shell (3), and the annular partition plates (5) are arranged on the outer edge face of the second steel shell (4). A heat exchange cavity is formed between the second steel shell (4) and the first steel shell (3), the annular partition plate (5) is arranged between the first steel shell (3) and the second steel shell (4) and divides the heat exchange cavity into a plurality of water storage layers, through holes (51) are formed in the annular partition plate (5), so that the water storage layers are in fluid communication, and the exhaust water delivery pipe (6) penetrates through the heat exchange cavity and the exterior of the containment.

A nuclear power plant has a nuclear reactor including a reactor pressure vessel which houses plural fuel rods containing fissile material. The nuclear power plant further has means for submerging the reactor pressure vessel in water and thereby water-cooling the reactor pressure vessel in the event of an emergency requiring cooling of the nuclear reactor. The nuclear power plant further has a primary core catcher outwardly of the reactor pressure vessel, the primary core catcher being formed of a material suitable for retaining molten corium in the event corium escapes the reactor pressure vessel. The nuclear power plant further has secondary core catcher outwardly of the primary core catcher, the secondary core catcher lining a tank which is water-filled in normal use of the plant to submerge and thereby water-cool the primary core catcher. The secondary core catcher is also is formed of a material suitable for retaining molten corium in the event corium escapes the primary core catcher.