83 results about "Core catcher" patented technology

The invention provides a large-scale passive nuclear plant reactor core catcher with bottom water injection and external cooling. The catcher comprises a reactor cavity coating the lower middle part of a reactor pressure vessel, and a reactor cavity concrete soleplate is formed at the bottom of the reactor cavity; a refractory layer is formed on the side surface of the reactor cavity and the bottom of the reactor cavity concrete soleplate; a steel cylinder is sleeved outside the refractory layer; an external cooling passage is formed at the bottom of the steel cylinder, and a cooling passage inlet and a cooling passage outlet are respectively formed at the two outward-extending ends of the external cooling passage; and dozens of nozzles are fixed at the bottom of the steel cylinder, and the upper ends of the nozzles extend into the reactor cavity concrete soleplate while the lower ends of the nozzles extend into the external cooling passage. According to the invention, the dilution and the temperature reduction of a melt are implemented through the melting of concrete by adopting the reactor cavity concrete soleplate as a sacrificial material. A reactor core melt is collected in the refractory layer after the reactor cavity concrete soleplate is molten through, so that the security and the reliability of a nuclear plant are further improved.

An assembly includes a base grid configured to be disposed below a pressure vessel and spaced vertically above a floor of a containment vessel to define a sump therebetween. The assembly further includes an annular wall extending vertically upwards from the floor and laterally bounding the base grid and the sump. The wall separates the sump from a suppression pool, an inlet passage extending through the wall and providing flow communication between the sump and the suppression pool, and an outlet passage extending through the wall and providing flow communication between the sump and the suppression pool.

The invention relates to apparatus for positioning and cooling melting lining layer when the melting lining layer flows out of the reactor shell during accident. The improvements of invention are described as following: the design of the cooling lining layer trap which has steel basket shell and arranged in sub-reactor, wherein sacrifice material is filled in the steel basket for diluting the component containing uranium and steel component of the lining layer; the shape (arrangement) of the sacrifice material in reactor core; the choice for optimum number of the sacrifice material; installation of guiding device used for the lining layer flowing into the reactor core trap. Especially, the thickness of bottom of the cooling jacket is larger than the thickness of the side wall thereof for no less than 30%, and the cooling jacket inclines to its center for 10 to 20 degree; the diluent and sacrifice material is made into blocks packed in steel shell.

The invention discloses a large passive pressurized water reactor nuclear power plant crucible-type reactor core catcher which comprises a reactor cavity concrete bottom plate (4), a crucible cooling system water filling nozzle (6), a crucible cooling system water vapor outlet (7), a crucible component (8), a crucible cooling system cavity (9) and a melt collector (10). The reactor core catcher is organically combined with an interactive voice response (IVR) system, the safety of the nuclear power plant can be further improved, and the reliability of the system is higher due to the crucible design.

The invention provides a large-scale passive pressurized water reactor nuclear power plant reactor core catcher with a melt expansion room. The large-scale passive pressurized water reactor nuclear power plant reactor core catcher with the melt expansion room comprises a reactor cavity which coats the middle lower portion of a reactor pressure vessel, a reactor cavity concrete base plate is arranged on the lower portion of the reactor cavity, and a reactor cavity refractory layer is arranged on the lower portion of the reactor cavity concrete base plate. The upper end of a melt release passage is communicated with the reactor cavity refractory layer, and the lower end of the melt release passage is communicated with the melt expansion room. The inner wall of the melt release passage surrounds the refractory layer. An expansion room concrete base plate is arranged on the lower portion of the melt expansion room, an expansion room refractory layer is arranged on the lower portion of the expansion room concrete base plate, and an expansion room outside cooling passage is arranged on the lower portion of the expansion room refractory layer. Two ends of the expansion room outside cooling passage extend outwards and are respectively an outside cooling passage entrance and an outside cooling passage exit. The large-scale passive pressurized water reactor nuclear power plant reactor core catcher with the melt expansion room is used for successively implementing expansion, retention and cooling of the melt when the a pressure container loses efficacy and can strengthen capacity of relieving severe accidents of the large-scale passive pressurized water reactor nuclear power plant.

The invention provides a device combining in-core and out-of-core dwelling of a molten material of a large-scale passive nuclear power plant. The device comprises a concrete sacrificial layer (4), a core catcher chamber (7), a core catcher refractory layer (8), a cooling channel inlet (9), a cooling channel outlet (10) and a core catcher bottom cooling channel (11). The invention provides a set of device organically combining molten material out-of-core cooling with an IVR (interactive voice response) system, when IVR succeeds, in-core dwelling of the molten material can be realized; and after the IVR fails, out-of-core dwelling of the molten material is realized by passive cooling of the core catcher bottom cooling channel, and the capability of mitigating severe accidents of the large-scale passive pressurized water reactor nuclear power plant is further enhanced.

The object of the present invention is to provide a core catcher having an integrated cooling path, which comprises a structure able to effectively collect, retain and cool molten core material discharged through a damaged part of a nuclear reactor pressure container during a major incident in a nuclear power station. To this end, the present invention is a core catcher which is disposed underneath the nuclear reactor pressure container in order to retain and cool molten core material discharged through a damaged part of the nuclear reactor pressure container and prevent interaction between the molten core material and the pressure-holding structure of the reactor building during a major incident in the nuclear power station, and which comprises: a main container in the shape of an inverted roof which is provided underneath the nuclear reactor pressure container and collects the molten core material; and a lower structure which is disposed below and outside the main container with supports disposed at scattered points placed in between, thereby forming a cooling path having a predetermined spacing for eliminating the heat of the molten core material.

Core debris generated during a molten reactor core in a reactor containment vessel penetrating the reactor containment vessel is configured to be caught by a core catcher located beneath the reactor containment vessel which has a main body having first stage cooling water channels and second stage surrounded by cooling fins extending radially. The number of the second stage cooling channels is larger than that of the first stage cooling channels. Cooling water is supplied from a cooling water injection opening and distributed to the first cooling water channels at a distributor. An intermediate header is formed between the first and the second cooling water channels, and the cooling water is distributed to the second cooling water channels uniformly.

Devices and methods for obtaining cores from a sea bed. A corer device includes one or more core barrels for retaining a cores and one or more pressure barrels. Fluid pressure within the pressure barrels is selectively varied to cause the corer device to be drawn into and released from the sea bed. The core barrels are provided with core catchers for retaining a core within.

The invention discloses a reactor core water injection evaluation method for a nuclear power plant equipped with a reactor core catcher. The method comprises the following steps that S1, a reactor core melting process in a pressure container is simplified to three stages; and S2, in combination with a specific reactor core melting process, the water injection evaluation method comprises the following sub-steps of S21, monitoring a process of relocating reactor core molten debris in the pressure container, judging a state of reactor core melting according to instrument monitoring data, and performing analysis in combination with a specific reactor core state to determine a reactor core water injection strategy; S22, monitoring a cooling effect of reactor core water injection, and further adjusting the reactor core water injection strategy; S23, when melt-through of a lower seal head of the pressure container is monitored, stopping water injection; and S24, monitoring melt-through scale and duration of the pressure container, and performing reactor core water injection according to actual position and state of the reactor core molten debris. The method has the beneficial effects that different water injection strategies are given in different accident stages; the water injection flow is controlled according to the cooling effect, so that steam explosion is avoided; and resources are reasonably utilized.

The invention relates to designing technology of reactor safety systems, specifically to a molten core catcher with interior cooling capacity. The molten core catcher comprises a melt retaining container arranged in a vertical shaft vertically connected with the bottom of a reactor pit, a plurality of interior tube bundles arranged in the melt retaining container and used for injecting a coolant and a sacrificial material arranged in the outer tube walls of the interior tube bundles and in the melt retaining container. Under a working condition of a serious accident, the molten core catcher provided by the invention can realize maximization of removal of the heat of melts by exchanging heat through the tube bundles distributed in the molten core catcher and injecting cooling water formed by later burning-up of the interior tube bundles for cooling, so long-term security of a nuclear power plant after the serious accident is guaranteed.

The invention discloses a hydraulic pressure type coring tool which comprises a safe joint, a hydraulic pressurizing device, an outer cylinder assembly, an inner cylinder assembly and a core catcher assembly. The safe joint is of a big-end-up cone shape, the bottom and the top of the safe joint are opened, the middle of the safe joint is connected with the outer cylinder assembly through threads, the lower portion of the safe joint is connected with the hydraulic pressurizing device through threads, the inner cylinder assembly is hung below the hydraulic pressurizing device through a hanging device, the core catcher assembly is arranged on the lower side of the inner cylinder assembly, and the hydraulic pressurizing device, the inner cylinder assembly and the core catcher assembly are located in the outer cylinder assembly. After the hydraulic pressurizing device exerts hydraulic pressure, the hanging device falls off, the inner cylinder assembly and the core catcher assembly fall along with the hanging device, and the core catcher assembly clamps under the action of hydraulic pressure to achieve the aim of completely wrapping a smashing core. When plastic deformation of a core sealing sleeve reaches a certain degree, drilling fluid is discharged from a gap between the core sealing sleeve and a connection sleeve, so that the core can not be compressed excessively, and integrity of the core is guaranteed.

The invention relates to a core catcher and its manufacturing method, and an reactor container and its manufacturing method, to improve the efficiency for cooling the core debris, which is produced when the core in a reactor container melts and flows through the reactor container. The core debris, which is produced when the core in the reactor container melts and flows through the reactor container, is caught by a core catcher including a steel body (20), which is positioned below the reactor container and provided with cooling channels (21a) of a first stage and cooling channels (21b) of a second stage defined by cooling fins (31) extending radially in the reactor container. The number of the cooling channels (21b) of the second stage is larger than that of the cooling channels (21a) of the first stage. The cooling water is fed from a cooling water inlet (22) and distributed into the cooling channels (21a) of the first stage by a distributor (10). Between the cooling channels (21a, 21b) of the first and second stages, there is formed an intermediate header (24) for feeding the cooling channels (21b) of the second stage homogeneously, too, with the cooling water.

A coring bit for extracting a sample of subterranean formation material from a well bore may include a bit body having a bit face and an inner surface defining a substantially cylindrical cavity of the bit body. A first portion of the inner surface may be configured to surround a core catcher. The coring bit may include a face discharge channel inlet formed in the inner surface of the bit body longitudinally at or above the first portion of the inner surface. The coring bit may also include a face discharge channel extending through the bit body from the face discharge channel inlet to the bit face. A tubular body having a core catcher may be disposed in the coring bit to form a coring tool. Methods of forming such bit bodies may include forming an inlet for a face discharge channel in the inner surface of the bit body at a location longitudinally at or above the first portion of the inner surface and forming a face discharge channel extending from the inlet to the bit face.

The invention discloses a pressurized coring tool comprising a pressure bearing device, a rotating assembly and a core catcher assembly, wherein the pressure bearing device comprises a pressure bearing assembly and a pin component, the pressure bearing assembly comprises a pressure bearing piston and a pressure bearing sleeve sheathed on the pressure bearing piston, the pin component comprises a shearing pin; the rotating assembly comprises a core shaft, one end of the core shaft is provided with a rotating device, the other end of the core shaft is provided with an automatic pressure relieving assembly; and the core catcher assembly comprises a connecting sleeve, a clamp seat, a clamp, a pressurized core catcher and a self-locking core catcher, one end of the clamp seat is connected with the lower end of the connecting sleeve, the other end of the clamp seat is connected with the pressurized core catcher, the upper end of the connecting sleeve is connected with an internal cylinder assembly, the clamp is arranged in the clamp seat, and the self-locking core catcher is arranged in the pressurized core catcher. When the pressurized coring tool disclosed by the invention is used for coring, the internal cylinder of a pressurizing tool can rotate along with the rotation of a drilling tool, and the problem that a core entering into the internal cylinder breaks easily is solved.

The invention discloses a novel siliceous nuclear power sacrificial material and a preparation method thereof. The novel sacrificial material is mainly prepared from 325-335 parts of PII.52.5-grade portland cement, 175-190 parts of pulverized fuel ash, 15-25 parts of silicon powder, 1,650-1,750 parts of quartz sand, 145-155 parts of water, 7-10 parts of water reducing agent, 1-1.5 parts of polypropylene fibers and 0.5-1.5 parts of sulfonated graphene. The preparation technology is simple, and a common forcing-type single-horizontal-shaft concrete mixer is adopted for preparing the nuclear power sacrificial material which is excellent in liquidity, strength and corrosion resistance. The prepared novel siliceous iron nuclear power sacrificial material has the advantages of good working performance, high strength, good corrosion resistance and the like, is mainly applied to a current third-generation nuclear power station reactor core catcher and has high engineering application value.

The invention discloses a novel ferrosilicon nuclear power sacrifice material and a preparation method thereof. The novel ferrosilicon nuclear power sacrifice material is primarily composed of 375-400parts of PII.52.5 level silicate cement, 130-145 parts of coal ash, 15-25 parts of silicon powder, 950-1100 parts of quartz sand, 900-1050 parts of hematite iron ores, 175-185 parts of water, 7-10 parts of a water reducer, 1-1.6 parts of polypropylene fibers and 0.5-1.6 parts of sulfonated graphene. The preparation process is simple. The nuclear power sacrifice material which is excellent in flowability, strength and corrosion resistance can be prepared by adopting a conventional forced single horizontal shaft concrete mixer. The prepared novel ferrosilicon nuclear power sacrifice material has the advantages of good working property, high strength, good corrosion resistance, is primarily applied to an existing reactor core trap of a third generation nuclear power plant and has wide engineering application value.

The invention belongs to the technical field of nuclear safety control and relates to a double-layer crucible reactor core melt capturing device with an internal cooling tube. The capturing device comprises a reactor pressure container, an inner crucible, an outer crucible, a cooling runner, a reactor pit, a reactor pit cavity, cooling tubes and cooling tube water inlets, wherein the inner crucible is arranged right below the reactor pressure container, is fixed outside the reactor pressure container and is positioned inside the outer crucible below the reactor pressure container; the coolingrunner in which cooling water flows is formed between the inner curable and the outer crucible; the outer crucible is mounted in the reactor pit cavity formed in the reactor pit; a plurality of cooling tubes are arranged inside the inner crucible; each cooling tube communicates with the cooling runner through the cooling tube water inlet in the bottom of each cooling tube; small holes are formed in side walls of a part of the cooling tubes; the small holes are externally covered by sacrificial concrete protection layers of 5-30mm in thickness. By adopting the capturing device provided by the invention, the retention success rate and the cooling efficiency of a reactor core capturer upon reactor core melts can be remarkably improved.

A core catcher comprising: a cap configured to be secured to a first end of a core liner such that when the first end of the core liner is inserted into sediment a sample sediment core enters the core liner through the cap; a cross-beam coupled to the cap and mounted across the first end of the core liner such that a cross-section of the first end of the core liner is divided into two openings; a flexible member secured to the cross-beam such that the flexible member, the cross-beam, and the cap form a dual-flap valve designed to allow the sediment core to enter the core liner through the two openings and to prevent the sediment core from escaping the core liner through the cap.

The invention relates to designing technology of reactor safety systems, specifically to a molten core catcher capable of guiding layered spreading of melts. The molten core catcher is arranged in a shaft well vertically connected with the bottom of a reactor pit and comprises multiple layers of melt spreading and detaining chambers, and adjacent melt spreading and detaining chambers for communicated space through a plurality of melt pouring channels. Under a severe accident condition, adequate spreading of the melts is realized through a layered spreading means, so heat of the melts is maximally led out and long-term security of a nuclear power plant after a severe accident is guaranteed.