760results about "Containment" patented technology

One variation of a system includes a pressure vessel: including a wall; defining a primary working fluid circuit extending vertically within the wall; defining a secondary working fluid circuit extending vertically within the wall and fluidly isolated from the primary working fluid circuit; and configured to store a nuclear fuel, a primary working fluid, and a secondary working fluid. The wall of the pressure vessel: defines a heat exchanger configured to transfer thermal energy from the primary working fluid flowing through the primary working fluid circuit into the secondary working fluid flowing through the secondary working fluid circuit; and defines a radiation shield configured to attenuate radiation emitted by the nuclear fuel.

A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from the containment vessel.

The invention relates to a containment pressure suppression, filtration and discharge system and method and application thereof, and belongs to the field of special safety facilities and radiation protection of nuclear power devices. The containment pressure suppression, filtration and discharge system comprises a discharge valve (2), a discharge pipeline (3), a spray pipe (4), a pressure suppression pool, an expansion chamber (7), a steam-water separator (9), a metal fiber filter layer (10), a rupture disk (12), a heat exchanger and a valve. According to the containment pressure suppression filtering and discharging system, the seawater side heat exchanger and the pressure suppression pool heat exchanger are arranged, and a natural circulation loop is constructed by means of the potential difference between the seawater side heat exchanger and the pressure suppression pool heat exchanger and the temperature difference between seawater and a liquid phase in a pressure suppression pool under the accident condition; the heat of the suppression pool can be guided out without time limit under the condition of an LOCA accident or a main steam pipeline fracture accident in the containment; by adopting a pressure suppression washing method with multi-stage bubbling, rapid pressure suppression of the containment and efficient retention of airborne radioactive substances can be realized; occupation of total resources is reduced by arranging the combined metal fiber filter layer.

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 embodiment of the invention relates to the technical field of nuclear reactors, in particular to a cock assembly for a reactor. The reactor comprises a reactor container and a reactor core assembly arranged in the reactor container, the reactor container comprises a container opening, and the reactor further comprises a refueling machine. The cock assembly comprises a first cock, a second cock and a third cock. The first cock is rotatably arranged at a container opening of a reactor container of a reactor, the first cock is provided with an eccentric first through hole, and the size of the first through hole is larger than the radius of the first cock. The second cock is arranged in the first through hole of the first cock and can rotate relative to the first cock, and the second cock is provided with an eccentric second through hole. The third cock is arranged in the second through hole of the second cock and can rotate relative to the second cock, and the third cock is provided with an eccentric third through hole. And the refueling machine is arranged in a third through hole of the third cock. According to the cock assembly, the moving range of the refueling machine can be increased, and the size of the first cock is reduced.

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.

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.

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.

The invention discloses a solid-state reactor core fuel assembly and a shielding system and belongs to the field of nuclear power. The solid reactor core fuel assembly comprises a base body with a fuel rod mounting hole, a fuel rod is arranged in the fuel rod mounting hole in a penetrating manner, a sealing section is formed between the fuel rod mounting hole and the end part of the fuel rod mounting hole, a deep hole end plug is arranged in the sealing section to seal the fuel rod in the fuel rod mounting hole, and end cover plates are fixed at two ends of the base body. According to the solid reactor core fuel assembly, multi-layer containing can be formed on reactor core radioactive substances, and the radioactive substances are sealed in the fuel rod mounting holes of the base body through the deep hole end plugs under the condition that a fuel rod cladding is damaged, so that the safety and reliability of a solid reactor core are improved. The invention also provides a solid reactor core shielding system.

The invention discloses a multi-layer steel lining containment structure, and the containment comprises an inner layer steel lining which is in contact with gas in the containment and is used for encapsulating radioactive substances; the outer-layer steel lining and the inner-layer steel lining form an interlayer, and the interlayer is provided with a filling space; the concrete shell is arranged on the outer layer of the outer-layer steel lining so as to protect the outer layer of the outer-layer steel lining; the filling space is filled with the phase change material, and the phase change performance of the phase change material can realize defect self-repairing of the containment. According to the structure, multiple functions of passive impact buffering, pressure balancing, rapid heat guiding-out, defect repairing and the like can be integrated.

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

Pressure vessels and closures for pressure vessels, such as for use in nuclear reactor systems, are described herein. A representative pressure vessel includes (i) a first enclosure including a first flange having a lower surface and a first inner surface, and (ii) a second enclosure including a second flange having an upper surface and a second inner surface. The pressure vessel can further include a sealing member having a first portion and a second portion. The first portion is configured to contact both the lower surface of the first flange and the upper surface of the second flange to provide a first seal between the first and second enclosures. The second portion is configured to contact, via an interference fit, both the first inner surface of the first flange and the second inner surface of the second flange to provide a second seal between the first and second enclosures.

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.

An apparatus including an integrated system, which can include a nuclear reactor; and a containment isolation system configured to prevent release of radioactive material from the nuclear reactor. The containment isolation system can include a containment vessel and a containment isolation test valve. The containment isolation test valve can include a body having a first test port and a first test port plug. The containment isolation test valve can include a cover configured to couple with the body, the cover having, a first seal, a second seal, an area between the first seal and the second seal, a second test port, and a second test port plug. The containment isolation system can include a containment isolation valve.

A nuclear reactor is configured with a primary coolant loop for transferring heat away from the nuclear reactor core. In a shutdown event, the primary coolant pump may stop pumping primary coolant through the reactor core, resulting in decay heat buildup within the reactor core. An inertial energy coast down system can store kinetic energy while the nuclear reactor is operating and then release the stored kinetic energy to cause the primary coolant to continue to flow through the nuclear reactor core to remove decay heat. The inertial energy coast down system may include an impeller and a flywheel having a mass. During normal reactor operation, the flowing primary coolant spins up the impeller and flywheel, and upon a shutdown event where the primary coolant pump stops pumping, the flywheel and impeller can cause the primary coolant to continue to flow during a coast down of the flywheel and impeller.

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.

The invention discloses a device and method for cleaning the bottom of a nuclear reactor pressure vessel, the device comprises a workbench, a collector, a telescopic rod, a six-axis mechanical arm and a water inlet pipe, the workbench is separably fixed to a top opening of the pressure vessel and straddles the opening edge of the top opening, the collector is connected to the lower portion of the workbench, and the telescopic rod is connected to the lower portion of the workbench; the upper end of the telescopic rod is fixedly connected with the workbench, and the six-axis mechanical arm is connected to the lower end of the telescopic rod. The collector comprises a submersible pump, the telescopic rod can stretch and deform in the vertical direction to adjust the length, a sweeping tool is arranged at the tail end of the six-axis mechanical arm, one end of the water inlet pipe is connected with the collector, and the other end of the water inlet pipe is connected with the six-axis mechanical arm. By means of the device, the bottom of the nuclear reactor pressure vessel can be cleaned more efficiently, and a good cleaning effect is achieved.

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.

To provide a reactor capable of securing long-term energy from accumulated spent nuclear fuels from a light water reactor.SOLUTION: Power is generated using a reactor having a low power density and a void reactivity coefficient of zero. The inherent safety can be enhanced as much as possible by reducing the output scale. Even if a coolant is lost, cooling can be achieved using air or nitrogen. Metallic spent nuclear fuel (10), obtained by metallizing oxide-based spent nuclear fuel from a light water reactor, is used.SELECTED DRAWING: Figure 3

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.

A coolant bypass flow control method and leak tightness test device for a high-temperature gas cooled reactor. The coolant bypass flow leak tightness test device for a high-temperature gas cooled reactor comprises a reactor unit (100), which comprises a protective layer (101) and a plurality of groups of graphite blocks (102); a blocking unit (200), which comprises longitudinal sealing members (201) and transverse sealing racks (202); and an adjusting unit (300), which comprises a plurality of rotating rods (301), a transmission member (302) which is arranged on one side of the rotating rods, and a limiting cover (303). Testing of the leak tightness is conducted by means of a simulation experiment device, and the longitudinal bypass flow and transverse leakage flow of a helium coolant are blocked, thereby reducing the effect of structural bypass flow on the flow distribution of the helium coolant within a pebble bed, ensuring an effective flow rate of the coolant flowing through the pebble bed, and thus optimizing the temperature distribution within the pebble bed and the maximum temperature of fuel, thereby providing support for the design and justification of the reactor structure of the high-temperature gas cooled reactor, further improving the safety and reliability of the pebble bed high-temperature gas cooled reactor.

The invention discloses a heat preservation structure of a reactor pressure vessel and a reactor pit water injection system. The heat preservation structure of the reactor pressure vessel comprises a heat preservation assembly which is provided with a first mounting part and a second mounting part; the first supporting piece is suitable for being connected with a supporting ring arranged on the periphery of the reactor pit, and the first supporting piece is configured to bear the first mounting part when the heat preservation assembly stretches into the reactor pit in the preset direction; and the second supporting piece is suitable for being arranged in the reactor pit, and the second supporting piece is configured to center the heat preservation assembly when the heat preservation assembly stretches into the reactor pit in the preset direction and limit the second mounting part in the circumferential direction of the heat preservation assembly. The heat preservation assembly, the first mounting part and the second mounting part are preassembled into a whole; hoisting and positioning installation work is integrated in one step, so that side wall welding and adjusting work possibly needed in a traditional method is omitted; the construction difficulty can be reduced, the construction time is shortened, and the overall construction efficiency is improved; therefore, the installation and adjustment period in a pile pit is shortened.

The invention provides a sea surface nuclear power plant steel containment pressure suppression and heat extraction device showered by ocean. The sea surface nuclear power plant steel containment pressure suppression and heat extraction device comprises a seawater showering device, a containment, a pressure vessel, a steam generator and a pressure stabilizer, wherein the pressure vessel, the steam generator and the pressure stabilizer are arranged in the containment; the seawater showering device is connected into the ocean, so that the outer wall of the containment is showered by utilizing the ocean in the ocean; the pressure container is connected with the steam generator and the pressure stabilizer through a main pipeline, and a main pump is further arranged on the main pipeline between the pressure container and the steam generator. The characteristics of good heat conductivity and the like of the ocean infinite heat trap and the steel containment are fully utilized, the seawater shower device is arranged outside the containment, and heat exchange between high-temperature steam in the containment and seawater outside the containment is realized under the accident condition, so that heat of the containment is taken out in a long-term stage, and the integrity of the containment is ensured.

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