274 results about "Core cooling" patented technology

The invention relates to the technical field of an electric spindle, in particular to a high-speed precise electric spindle cooling system which comprises an electric spindle shell cooling part, an electric spindle core cooling part and a bearing spindle core lubricating/cooling part, wherein when the electric spindle works, the temperature rise change can be controlled within +/-1 DEG C. The concrete scheme is as follows: a ring sleeve type heat pipe cooling mode is arranged at the electric spindle shell part, and the heat of the shell is taken away quickly by increasing the cooling contact surface; the spindle core cooling part is provided with symmetrical bar-type heat pipes which are uniformly distributed on the spindle core, and the spindle core is cooled by use of the high-speed conductivity and homoiothermy of the heat pipes; and a spindle core liquid lubricating/cooling mode is adopted at the bearing lubricating/cooling part, and makes full use of the high rotation speed of the high-speed electric spindle to generate centrifugal force so that the lubricating/cooling liquid is uniformly distributed on the bearing roller. The temperature stability of the electric spindle can be ensured, the processing precision error caused by thermal expansion of the electric spindle is minimized, and the service life of the spindle and the spindle bearing can be prolonged at the same time.

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.

A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form is provided. The nanoparticles are delivered in locations such as the cold leg accumulator and high and low pressure pumps of an emergency core cooling system. Motor driven valves and pressurization can aid in the delivery. Methods for providing the nanoparticles are also provided.

Provided is an electrical apparatus comprising a magnetic core, a conductive coil wound around at least a part of the core, a cooling element configured to receive a cooling fluid to cool the core and the coil during operation, and at least one biasing element operatively associated with the core to urge the core and the coil into engagement with the cooling element despite differential expansion or contraction of the core and the coil and manufacturing tolerances. Further provided is a method for making an electrical apparatus comprising disposing a conductive coil wound around at least a part of a magnetic core, disposing a cooling element between the core and the coil, the cooling element configured to receive a cooling fluid to cool the core and the coil during operation, and urging the core and the coil into engagement with the cooling element despite differential expansion or contraction of the core and the coil and manufacturing tolerances.

The invention provides a module type pressurized water reactor. A reactor module is composed of a reactor body, a cooling agent system, and a safety system, the reactor body, the cooling agent system, and the safety system are all enclosed in a steel safety shell, and the whole reactor module is immersed in a reactor safety water pool, taking the pool water as the final hot trap for heat discharging of accidents. Emergency core cooling and emergency excess heat discharging are achieved by adopting a complete passive way, and the pressure inhibition and long-term heat discharging of the safety shell are achieved through repressing the water in the water pool and the reactor safety water pool; and during the processes of reloading and maintenance of reactor, through arranging a reloading water jacket between the safety shell reloading channel flange and the reactor container flange, direct-moving underwater fuel lifting operation is achieved between the safety shell and the spent fuel pool. A reactor factory can be provided with a plurality of reactor modules, all reactor modules co-use material loading equipment and other nuclear auxiliary systems, and the safety and economy of the reactor are improved through modularized combination arrangement. The module type pressurized water reactor is suitable for being applied to the fields of nuclear electricity generation, gas application, heat application, sea water desalination, and the like.

The invention discloses a temperature-triggered passive accident residual heat removal system for a pool type reactor. The system consists of a direct reactor core cooling system and an auxiliary reactor safety container cooling system. The system has the significant advantage that the direct reactor core cooling system and the auxiliary reactor safety container cooling system share one air cooling system, so that the system design of the reactor is greatly simplified, and the construction cost is saved. The auxiliary reactor safety container cooling system realizes natural cooling through ambient air on the outer side of a safety container, and the process has the characteristic of passiveness. The passive accident residual heat removal system is passive, independent, high in efficiency and high in reliability and meets the safety design requirement for the pool type reactor.

In accordance with the present invention, there is provided an increased efficiency strainer system which is particularly suited for use in the emergency core cooling system of a nuclear power plant. In certain embodiments of the present invention, the strainer system includes one or more strainer cassettes or cartridges, with each such cassette or cartridge including a plurality of strainer pockets disposed in side-by-side relation to each other. In these embodiments, multiple cassettes or cartridges may be assembled together to form a strainer module of the strainer system. The strainer pockets of the cartridge each define an inflow end. Within the cartridge, or the module including multiple cartridges, the inflow ends of one or more of the strainer pockets may be enclosed by an elastic metal membrane. When in a closed position, the membrane prevents liquid flow into the corresponding strainer pocket via the inflow end thereof. The membrane remains closed when only a low pressure load is exerted thereon, but is deflected or deformed into an open position when a high pressure load is exerted thereon. The movement of the membrane to its open position effectively opens the corresponding strainer pocket, thus allowing for the flow of liquid into the interior of the strainer pocket via the inflow end thereof.

A strainer for an emergency core cooling system (ECCS) in a nuclear power plant comprises a perforated strainer element that is immersed in a reservoir of cooling water, which is drawn through the strainer element into the emergency core cooling system. The side of the strainer element in contact with the cooling water has a contoured configuration for disrupting the formation of a flat bed of fibrous material that can trap small particulate material intended to pass through the strainer element. Incorporating this strainer element into an ECCS strainer enables the strainer to be made more compact, because the debris bed need not be spread over an unduly large area to prevent excessive head loss from the debris load in the event of a reactor loss of coolant accident. The strainer also incorporates a modular construction that uses individual strainer disc modules. Each disc module includes a perforated first disc part having a central opening and a perforated second disc part also having a central opening. The first and second disc parts fit together to form an interior space with facing perforated major surfaces and an axial opening, and connecting tubes between the discs place the axial openings in fluid communication. The entire assembly is secured together by tie rods that hold the discs together with the connecting tubes compressed between them.

The invention relates to temperature-controlled rolling equipment for production of metal thin ribbons and ultra-thin strips in coils.The temperature-controlled rolling equipment is arranged in the bilaterally symmetrical mode. The position where a working roll (15) is used for rolling strips is a rolling mill gap (20). Inlet and outlet side parts comprise measuring tension rolls (13, 17), steering rolls (12, 18), and recoiling machines (11, 19). All parts are sequentially arrayed with the rolling mill gap as the center from the inside to the outside. The equipment further comprises an uncoiling and heating device (21), a plate strip heat-compensating device (24) and a plate strip edge heating device (25) before ingress of the rolling mill gap, a roll surface heating device (26), and a roll core cooling and bearing seat cooling mechanism (3), a plate strip edge heating device (35) and the plate strip heat-compensating device (34) after egress of the rolling mill gap, a pre-coiling heating device (31), heating devices (22, 32) at positions of the steering rolls and heating devices (23, 33) at positions of the measuring tension rolls at the inlet side.

This invention is a kind of sleeve type evaporation cooling transformer, which is consisted with mandrel, electric coil, oil tank, sleeve, air inletting tube, condenser, liquid returning tube, upper pipe, lower pipe, insulating gas, cooling medium in the bottom of the oil tank, pump and iron core cooling channel. The characteristics are that the electric coil is arranged inside of the sleeve added with cooling medium, the upper side of the sleeve can be covered or not, or setting a blowhole. The upper side of the oil tank is connected with the lower side of the air inletting tube, upper side of the air inletting tube is connected with condenser, the bottom (or the side face) of the condenser is connected with liquid returning tube, lower side of the liquid returning tube is connected with the bottom of the sleeve, cooling medium dripping in the bottom of the oil tank is connected with cooling medium in the liquid returning tube through pump. The oil tank is filled with insulating gas such as SF6 gas, mixture of SF6 gas and N2, substitute of SF6 gas, nitrogen and carbon compound gas.

An oil cooler includes a heat exchanger core having a plurality of plates laid one upon another to define each of an oil passage through which oil flows and a coolant passage through which coolant flows, between the plates. An uppermost plate of the plates has a core coolant inlet and a core coolant outlet. The core coolant inlet and the core coolant outlet are communicated with the coolant passage. A flow passage control valve is disposed on an uppermost part of the heat exchanger core and has a first coolant introduction opening through which coolant at a relatively high temperature is supplied and a second coolant introduction opening through which coolant at a relatively low temperature is supplied. The first coolant introduction opening and the second coolant introduction opening are changed over to be communicated with the core coolant inlet.

The present invention discloses a small reactor passive core cooling system including a water replenishing tank, pipes of the water replenishing tank, a safe water injection pool, pipes of the safe water injection pool, a residual heat exchanger, pipes of the residual heat exchanger and a circle-structure shielding water pool, the circle-structure shielding water pool is arranged around a pressure vessel, the circle-structure shielding water pool is provided with a suppression pipe ad a water pipe, a pressure relief pipe is arranged between the shielding water pool and a reactor coolant, and the pressure relief pipe is used for communication of the reactor coolant and a water body in the shielding water pool, and is provided with a valve group. The small reactor passive core cooling system can be used as an important part of a passive safety system of a small containment vessel to achieve the functions of taking away reactor core decay heat and providing a safe water injection source in accidents, and can effectively suppress containment vessel peak pressure. The system equipment layout is compact, space occupation is small, arrangement is simple, and economical efficiency is high.

A pressurized water nuclear reactor (PWR) includes a pressure vessel having a lower portion containing a nuclear reactor core comprising a fissile material and an upper portion defining an internal pressurizer volume. A condenser is secured to, and optionally supported by, the upper portion of the pressure vessel. A condenser inlet is in fluid communication with the internal pressurizer volume. A heat sink is in fluid communication with the condenser such that the condenser operates as a passive heat exchanger to condense steam from the internal pressurizer volume into condensate while rejecting heat to the heat sink. A condenser outlet connects with the pressure vessel to return condensate to the pressure vessel. A single metal forging having a first end welded to the pressure vessel and a second end welded to the condenser inlet may provide the fluid communication between the condenser inlet and the internal pressurizer volume.

The present invention relates to a longitudinally divided emergency core cooling (ECC) duct in order to efficiently inject safety water to core of a pressurized light-water nuclear reactor. The ECC duct includes side supports for preventing the flow-induced vibration in the annular downcomer, and has structural stability while thermally expanding and contracting. A longitudinally divided ECC duct for emergency core cooling water injection of a nuclear reactor is provided on the periphery of a core barrel of a nuclear reactor, includes an emergency core cooling water inlet facing a direct vessel injection nozzle, and extends in a longitudinal direction of the core barrel. The longitudinally divided ECC duct is divided into a plurality of longitudinally-divided ducts in the longitudinal direction of the longitudinally divided ECC duct.

An emergency core cooling system directly injects emergency core cooling water, which is supplied from a high-pressure safety injection pump or a safety injection tank for a pressurized light water reactor, into a reactor vessel downcomer. A pipe connector is completely removed from between each direct vessel injection nozzle and each injection extension duct installed on an outer surface of the core barrel, which are opposite to each other. An emergency core cooling water intake port, through which the water is injected from each direct vessel injection nozzle, is formed on the surface of each injection extension duct facing an axis of each direct vessel injection nozzle. Thereby, a structure in which a jet of the emergency core cooling water flows into the injection extension ducts is adopted in a hydraulic connection fashion.

An equipment assembly includes a core cooling slot to manage thermal effects brought about by the generation of heat from components therein. The cooling slot is positioned within the equipment assembly so that only air that is external to the equipment assembly passes through the cooling slot to provide external convection-based cooling for components in a core section inside the equipment assembly. The cooling slot also acts as a thermal barrier for redistributing heat generated by the one or more components inside the equipment assembly.