226results about "Containment" patented technology

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.

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.

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.

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.

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 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.

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.

A fission product trap for a reactor system, such as for a pipe connection and / or a pump shaft of a pump of the reactor system, includes a porous container. The porous container may be mounted about the pipe connection and / or pump shaft and include an absorbing material contained therein. The absorbing material may be configured to collect fission products emitted from the pipe connection and / or the pump shaft. The fission product trap further includes an assembly encompassing the porous container and that defines a volume about the porous container and the pipe connection and / or the pump shaft.

The invention relates to the technical field of radioactive container treatment, and provides a radioactive pressure container hoisting method, a hoisting instrument and a shielding device are used for hoisting a radioactive pressure container, one side of the radioactive pressure container in the height direction is provided with an opening, and the hoisting method comprises the steps that the shielding device covers the opening and is fixedly arranged; the shielding device is leveled, and a lifting hook of the lifting instrument is aligned with the shielding device; the lifting hook and the shielding device are connected, and the radioactive pressure container is lifted to a designated position to be cut and disassembled. According to the hoisting method for the radioactive pressure container, the radioactive pressure container can be integrally hoisted out of a pile, so that the decommissioning efficiency is improved.

Molten salt nuclear reactor, of the fast neutron type with a safety vessel around the reactor vessel and a drain tank below the vessels. The invention relates to a nuclear reactor (1) comprising: - at least one nuclear reactor vessel (2) (1) filled with a molten salt fuel bath and provided with at least one outlet in its bottom; - another vessel (8), called the safety vessel, arranged around the reactor vessel by defining an inter-vessel space (E) with the reactor vessel; - a tank (10), called the drain tank, arranged below the vessels, and connected to the inter-vessel space by at least one pipe (11) and to the outlet of the reactor vessel by at least one pipe (12); - a selective closure device (13) for the outlet of the reactor vessel, in the closed position during normal reactor operation and in the open position to carry out the emptying of the reactor vessel.Figure for the abridged version: fig.3.

A nuclear reactor core (1) for a molten salt nuclear reactor (100). The nuclear reactor core (1) has a tubular cylindrical center moderator vessel (10) for passage of a liquid moderator (11), a cylindrical fuel salt jacket surrounding the center moderator vessel (10), and a cylindrical neutron reflector jacket surrounding the cylindrical fuel salt jacket, wherein the cylindrical center moderator and neutron reflector vessel (10) has a largest inner cross-sectional area medially between a liquid moderator and neutron reflector inlet (12) of the center moderator and neutron reflector vessel (10) and a liquid moderator and neutron reflector outlet (13) of the moderator and neutron reflector vessel (10).

A pipe connection assembly includes fixed and removable pipes and an anti-rotation assembly. The fixed pipe extends to a fixed pipe proximate end through a sidewall thickness of a vessel body such that the fixed pipe proximate end is open to a vessel interior and fixed in relation to the vessel body. The removable pipe extends between a removable pipe proximate end and a removable pipe distal end. The fixed and removable pipes include respective first and second pipe connectors at the fixed and removable pipe proximate ends. The first and second pipe connectors collectively define a bayonet connection. The removable pipe detachably connects with the fixed pipe via the bayonet connection. The anti-rotation assembly at least partially limit movement of the removable pipe in relation to the vessel independently of the bayonet connection, based on the removable pipe detachably connecting with the fixed pipe.

A Modular Isolated Reactor Support System (MIRSS) assembly includes a cylindrical reactor support structure configured to structurally support a reactor enclosure system on seismic isolators, a collector cylinder configured to at least partially define a riser annulus between an inner cylindrical surface of the collector cylinder and an outer sidewall surface of the reactor enclosure system structurally supported by the cylindrical reactor support structure, and a divider wall configured to at least partially define a downcomer annulus between an outer cylindrical surface of the divider wall and a reactor building, and a plurality of exhaust ducts extending from the collector cylinder and through an interior of the cylindrical reactor support structure.

For stabilizing a pipe connection, in which a first pipe (10) is inserted into a second pipe (12) that has an insertion funnel (20), a stabilizer element (22) has a clamping ring (24) with several tensioners (48) distributed over its circumference, which in the final assembly position engage in an intermediate space between the first pipe (10) and the insertion funnel (20), and tense the first pipe (10) and the second pipe (12) against each other. The clamping ring (24) is composed of several mutually connectable ring segments, in particular of two half shells (34).

This application provides a docking monitoring device, docking system, and docking method for underwater docking structures. The underwater docking structure includes a first annular component and a second annular component located underwater. The second annular component is deployed underwater using a hoisting and deployment device to dock and assemble with the first annular component, or is lifted upwards using the same device to separate from the first annular component. The first annular component forms a positioning element, and the second annular component forms a positioning mating element. Positioning is achieved through the positioning mating element and the positioning element. The device includes: multiple lifting mechanisms, each facing a positioning element; multiple image acquisition devices, each mounted on a lifting mechanism, each lifting mechanism configured to move the image acquisition device in the same direction as the second annular component to continuously acquire images containing the second annular component; and a display device for displaying the images acquired by the multiple image acquisition devices.

This invention discloses a ceramic encapsulation assembly, an electrical penetration component, and a method for manufacturing the same, relating to the field of electrical equipment technology. The ceramic encapsulation assembly includes a ceramic sheet, a metal housing, and at least one end guide pin. The metal housing is cylindrical and has an axially through mounting cavity. The ceramic sheet covers and seals one end of the metal housing. The end guide pin penetrates the ceramic sheet. Both the ceramic sheet and the metal housing, and the ceramic sheet and the end guide pin, are sealed connections. This invention utilizes ceramic material to seal the electrical penetration component, offering advantages such as high temperature resistance and high insulation.

The invention relates to the technical field of concrete pouring, in particular to a containment concrete pouring construction structure and method.The construction structure comprises a containment concrete body, the containment concrete body is composed of a plurality of pouring sections which are sequentially connected in the height direction, and a plurality of pouring layers are arranged in each pouring section in the height direction; a construction joint is formed between every two adjacent pouring sections; the template is arranged on the outer side of the containment concrete body; and the connecting devices are arranged corresponding to each single pouring section, one end of each connecting device is connected with the corresponding pouring section, and the other end of each connecting device is connected with the corresponding formwork so as to fix the position of the corresponding formwork. Segmented and layered control over concrete pouring is achieved, and the construction quality can be accurately controlled.

The present invention provides a blowout panel device that has the contradictory functions of rapid opening and slow stopping of the blowout panel. [Solution] The blowout panel device 100 comprises a blowout panel 1 that closes an opening 30 in the building of a nuclear-related facility, a hinge portion 2 that fixes the blowout panel to the building structure at the top or bottom, and a buffer mechanism 110 with one end connected to the structure and having a spring and damper arranged in parallel. The other end of the blowout panel 1 and the buffer mechanism 110 are attached via a flexible member (for example, a wire 7). When the door of the blowout panel 1 is opened, the door opens almost without load up to a predetermined door opening, and when it exceeds the predetermined door opening, the buffer mechanism 110 operates and the blowout panel stops at a predetermined limited door opening below the limit door opening where damage occurs, and then the blowout panel 1 returns in the direction of closing to the predetermined door opening.