563results about "Containment" patented technology

A structure and process for containing a nuclear reaction is disclosed. The structure and process may involve a nuclear containment structure including a plurality of metallic rings stacked axially to form the nuclear containment structure, the nuclear containment structure being configured to: mitigate, by using a physical barrier, the movement of radionuclides from inside a containment structure to a surrounding space; shield, by varying the alloy properties throughout the containment structure, an exterior of the containment structure from radiation produced inside of the containment structure; regulate, by transferring thermal energy, a temperature within the containment structure; regulate, by storing thermal energy, the temperature within the containment structure; shield, components within the nuclear containment structure from kinetic events external to the nuclear containment structure; and shield, the external environment, from kinetic events within the nuclear containment structure.

The invention belongs to the technical field of nuclear power station containment vessels, and particularly relates to a large fast reactor low-pressure containment vessel system which comprises a low-pressure containment system and a ventilation filtering system. The low-pressure containment system is used for containing radioactive substances in an operation state and an accident working condition, ensuring the air tightness of a containment boundary, and carrying out nuclide closed decay in the containment at the initial stage of an accident; the ventilation filtering system is used for filtering and discharging radioactive substances after short-period nuclide decay in the later period of an accident, and the radioactive level in a plant and the radioactive level in the environment are kept at the low level. According to the system, through coupling of the ventilation filtering system and the low-pressure containment system, the air tightness requirement of the containment can be met under the severe accident working condition, and meanwhile, the economical requirement of unit construction is met.

The invention belongs to the technical field of fluid machinery, and particularly relates to a novel tank type molten salt reactor main pump structure. Comprising a driving device, a sealing section, an air cavity section and a working section which are sequentially connected from top to bottom. The driving device is connected with the working section through a rotating rod; the rotating rod is rotatably connected with the sealing section and the air cavity section; the air cavity section comprises a third outer shell, an air outlet pipe and an air inlet pipe penetrate through the side wall of the third outer shell, an air outlet control unit is arranged at the end, close to the third outer shell, of the air outlet pipe, an air inlet control unit is arranged at the end, close to the third outer shell, of the air inlet pipe, and the air outlet control unit and the air inlet control unit are connected with the working section. The gas outlet control unit and the gas inlet control unit perform negative feedback regulation on the molten salt liquid level of the third outer shell, so that the molten salt liquid level is prevented from being in direct contact with the sealing section; the working section comprises an impeller, a guide vane, a fused salt inlet and a fused salt outlet, fused salt enters the third outer shell from the fused salt inlet, then flows into the impeller and the guide vane section through the pump inlet to be pressurized and stabilized, and finally flows out through the fused salt outlet.

A containment system for an integral molten salt reactor includes a sealed containment structure defining a containment volume. The containment structure includes a fission product adsorbing / absorbing material. The containment system further includes an integral molten salt reactor housed fully within the containment volume of the sealed containment structure. The integral molten salt reactor may permit circulation of a fuel salt therein being heated by fission reactions, and allow for the export of heat from said fuel salt.

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.

A containment system for an integral molten salt reactor includes a sealed containment structure defining a containment volume. The containment structure includes a fission product adsorbing / absorbing material. The containment system further includes an integral molten salt reactor housed fully within the containment volume of the sealed containment structure. The integral molten salt reactor may permit circulation of a fuel salt therein being heated by fission reactions, and allow for the export of heat from said fuel salt.

A reactor head structure and a head system, the reactor head structure (1) comprising a seismic support ring (30) and a seismic plate (40), wherein the seismic plate (40) is mounted in the seismic support ring (30). The reactor head structure further comprises a bracket (10), and a flow baffle (50) for dispersing high-temperature air at the center of a reactor head, wherein the bracket (10) comprises a plurality of support rods (11) arranged at intervals, and one end of each of the support rods (11) is fixed to the seismic support ring (30); and the flow baffle (50) is arranged on the seismic plate (40). The reactor head structure (1) has a simple structure and satisfies an overall seismic strength, facilitates integrated hoisting, allows for convenient maintenance, and is light in terms of weight. Moreover, cooling is realized by means of the natural circulation of air, thereby preventing unplanned emergency reactor shutdown due to burnout of cables.

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.

The invention provides a secondary buffering energy absorption device which comprises a first energy absorption unit and a second energy absorption unit, the first energy absorption unit comprises at least two rigid panels and an energy absorption layer, the two rigid panels are located on the two sides of the energy absorption layer respectively, and the rigid panels make direct or indirect contact with the energy absorption layer; the second energy absorption unit comprises an extrusion part and an expansion pipe, one of the extrusion part and the expansion pipe is directly or indirectly connected with one rigid panel, the expansion pipe is of a hollow structure, one end of the extrusion part is located in the expansion pipe, and the extrusion part and the expansion pipe generate relative displacement to dissipate energy through plastic deformation; the first energy absorption unit and the second energy absorption unit are connected in series. By means of the two-stage energy absorption structural design, the utilization rate of energy absorption materials of all parts can be effectively increased.

The invention provides an integrated reactor pressure vessel and a refueling method, the pressure vessel comprises a cylinder and a bottom seal head arranged at the bottom of the cylinder, and the bottom seal head and the cylinder are detachably connected through a flange; at least one supporting boss is arranged in the bottom sealing head, the supporting boss is used for supporting a reactor core supporting plate and a reactor core shroud mounted on the reactor core supporting plate, and the fuel assembly is arranged in the reactor core shroud; in the refueling and refueling period, the bottom sealing head, the reactor core supporting plate, the reactor core shroud and the fuel assembly are transferred to a refueling pool together for fuel disassembly operation by disassembling the bottom sealing head. According to the pressure vessel, the bottom sealing head is detachably arranged at the bottom of the barrel, refueling is carried out from the bottom of the barrel, and the bottom sealing head, the reactor core supporting plate and the fuel assembly are transferred to the refueling pool together for centralized refueling during refueling, so that the refueling period is shortened, and due to refueling at the bottom of the barrel, the refueling efficiency is improved. Therefore, the problems that a traditional reactor top penetrating piece is difficult and tedious to disassemble and assemble, and long-distance deep reactor core reloading is difficult are solved.

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.

The invention discloses a twisted pressure suppression spray pipe capable of adaptively adjusting the immersion depth, relates to the technical field of reactor thermal hydraulic power, and solves the problems of condensate water hammer and thermal stratification caused by water seal removal, pool swelling and low-speed discharge in the whole operation stage of a pressure suppression system in the prior art. The suppression spray pipe comprises a twisted inner pipe and a circular outer pipe, the twisted inner pipe is arranged at the bottom of the pressure suppression box, one end is communicated with the containment, and the other end penetrates through the water space in the pressure suppression box and is arranged above the liquid level of the water space; the upper end of the circular outer pipe is closed, and the lower end movably sleeves the twisted inner pipe; an air space in the pressure suppression box is communicated with the containment through a vacuum release valve; the twisted inner pipe is a spiral straight pipe. The pressure suppression spray pipe adopts a passive design, the immersion depth of the spray pipe is automatically adjusted by virtue of the spring, the gravity of the outer pipe and the pressure difference between the containment and the pressure suppression box, the pressure suppression spray pipe is simple and reliable, and the problems of condensate water hammer and thermal stratification are solved by virtue of a plurality of through holes formed in the limiting porous ring.

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.

A nuclear power generation system capable of generating power with robust shielding against ionizing radiation is provided. This nuclear power generation system includes: a nuclear reactor that includes a core fuel, and a reactor vessel that surrounds to cover the core fuel and to shield a space having the core fuel for shielding against ionizing radiation; a thermal conductor that is disposed inside of the reactor vessel, and transfers heat of the core fuel via solid thermal conduction; a refrigerant circuit that includes a pipe with a part inserted in the reactor vessel and another part disposed outside of the reactor vessel, and through which refrigerant is passed, and that circulates the refrigerant exchanging heat with the thermal conductor; a turbine that is rotated by the refrigerant circulating through the refrigerant circuit; and a generator that is rotated integrally with the turbine.

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.

Reactor buildings and vessel systems are disclosed. A nuclear power system includes: a building structure that comprises at least two exterior side walls and two end walls, at least one of the exterior walls angled non-orthogonally relative to a floor of the building structure, the at least two exterior walls and two end walls defining an interior volume of the building structure; one or more nuclear reactor systems mounted at least partially in the interior volume of the building structure; and one or more heat exchanger systems mounted at least partially to at least one of the exterior walls. A nuclear reactor vessel system includes: a nuclear fission reactor; an inner vessel that defines an inner volume sized to at least partially enclose the nuclear fission reactor; and an outer vessel sized to wholly or substantially enclose the inner vessel, the inner vessel being removable from the outer vessel.