102 results about "Power reactor" patented technology

In a method of producing isotopes in a light water power reactor, one or more targets within the reactor may be irradiated under a neutron flux to produce one or more isotopes. The targets may be assembled into one or more fuel bundles that are to be loaded in a core of the reactor at a given outage. Power operations in the reactor irradiate the fuel bundles so as to generate desired isotopes, such as one or more radioisotopes at a desired specific activity or stable isotopes at a desired concentration.

A set of alloy formulations is disclosed to use with thorium based nuclear fuels in a fast spectrum reactor; with thorium based nuclear fuels in existing thermal spectrum power reactors; for medical isotope production in the epithermal, the fast, the fission spectrum and the thermal spectra; and to use as fuel in test and experimental reactors that are non proliferative. The alloys form inert metal matrixes to hold fine particles of dispersed thorium containing fuel. The formulations also are useful for the production of medical and commercial isotopes in the high energy, fast and epithermal neutron spectra.

A process to safely convert about 95% of the nuclear waste into a usable fuel source is disclosed. The process, involving a sub-critical power reactor and a proliferation-resistant fuel cycle, consumes depleted uranium or thorium fuel with fissionable fuel, including reactor or weapons-grade plutonium. The reactor is comprised of coaxial neutron and energy-amplifying regions separated by moderating and thermal neutron absorbing layers. Control of the water or gas-cooled reactor is provided by plutonium-helium loops with a variable volume flow rate and an external source of neutrons that quickly reacts to any fluctuations of the reactor parameters. A second embodiment of the invention is a compact sub-critical propulsion reactor utilizing fission electric cell and thermo-acoustic technology for electrical power generation.

A telescoping guide for extraction and reinsertion support handling of in-core instrument thimble assemblies in the area above the upper support plate in the upper internals of a pressurized water reactor. The telescoping guides extend between the upper ends of the upper internals support columns and an axially movable instrumentation grid assembly which is operable to simultaneously raise the telescoping guides and extract the in-core instrument thimble assemblies from the reactor fuel assemblies.

The invention belongs to a process for treating oil field produced water and belongs to the field of oil field produced water treatment, in particular relates to the process for treating the oil field produced water. In the process, at least a regulating water tank, an air flotation device, a pipeline mixer, a nitrogen power reactor, a sedimentation tank and an ultrasonic filter are adopted and the oil field produced water is treated by adopting a mode of combining air flotation oil and suspended matter removal, nitrogen preparation and ultrasonic filtration. The process for treating the oil field produced water has good treatment effect, high oil removing efficiency, corrosion resistance and low cost and has good effect in the actual application.

A system and method of passively monitoring nuclear fuel coolant conditions is disclosed, and includes a passive (non-electrically powered) gamma thermometer(s) located in nuclear fuel coolant area(s) (e.g., in the reactor vessel and / or in the facility spent fuel pool) and in electrical communication with millivolt meter(s) to facilitate passive monitoring of nuclear fuel coolant levels, nuclear fuel coolant temperatures, and / or heat transfer conditions in the nuclear fuel coolant area(s) during a station blackout (SBO) or prolonged station blackout (PSBO) event.

The invention relates to an online monitoring device for a turn-to-turn insulation fault of an air-core power reactor, which is characterized by comprising a method for judging a turn-to-turn insulation fault of the air-core power reactor through changes in value of a loss factor. The online monitoring device is composed of a signal extraction portion, a signal conversion control portion, a computer operation portion and a display and alarm portion, and is characterized in that terminal voltage and current signals of a monitored reactor are extracted by applying a voltage transformer and a current transformer, the terminal voltage and current signals are zoomed so as to conform to a processing range of an AD converter, a single-chip microcomputer controls the AD converter to perform processing on analog voltage and current signals, the processed analog voltage and current signals are sent to a computer to perform analysis and calculation on a loss factor, active power and reactive power are calculated through current and voltage signals, and the loss factor is calculated; changes of the loss factor tan<delta> is monitored online in real time, the loss factor tan<delta> is compared with a loss factor tan<delta> threshold under normal power reactor running, a running state of the reactor is displayed, and an alarm is given out when the loss factor tan<delta> exceeds the threshold. The online monitoring device realizes online monitoring for the air-core power reactor; a detection objective is realized via the proposed method of being according to changes of the loss factor, thereby promoting and expanding a new direction of online monitoring for the air-core power reactor; and the running reliability of the air-core power reactor is improved.

An air core, dry type, power reactor (10) of the type having multiple concentrically positioned winding layers (12) extending along a central axis and above arms (24) of a first spider unit (16) when the reactor is horizontally positioned with respect to a horizontal ground plane, the winding layers (12) arranged in spaced-apart relation providing air gaps (20) between the winding layers allowing air to flow along the winding layers. A deflector (40) is positioned between the winding layers (12) and the ground plane to receive air from wind blowing toward the reactor (10) and guide the air in an upward direction from the deflector (40) and along the gaps (20).

Cylindrical inertial confinement fusion reaction chambers are disclosed according to some embodiments of the invention. These chambers can include neutron moderating / absorbing material, radiation absorbing material, and debris collection material. These chambers can also include various injection ports, nozzles, beam ports, sacrificial layers, absorbers, coolant systems, etc. These chambers can be used with directional and / or omni-directional targets.

A device for the electrical heating of a liquid with high thermal flow, according to which the resistor in tubular form and supplied with direct current can indirectly heat the liquid by conduction through an electrically insulating and thermally conductive intermediate element that surrounds it with direct mechanical contact, the assembly consisting of tubular resistor and intermediate element being jacketed by a sheath intended to be immersed, over at least a major part of the length thereof, in the liquid to be heated. The preferred application is the electrical simulation of nuclear fuel rods intended to be assembled in power reactors, of the PWR but also RNR-Na type.

The invention provides an online monitoring device for power reactor vibration. The device includes a monitoring parameter sensor used for monitoring vibration and voltage and current signals of the power reactor in a work state; a signal processing module used for receiving signals monitored by the monitoring parameter sensor and performing amplification, filtering and synchronous digital-analog conversion processing after performing synchronous acquisition on the signals; a signal data reading module used for real-time reading of vibration and voltage and current signals which undergo the amplification, filtering and synchronous digital-analog conversion processing; a GSM data communication module used for monitoring information, which is read by the signal data reading module in a real-time manner, and forming vibration waveforms and current and voltage waveforms through the information for transmission so as to perform map display and data analysis; and an analysis display and alarm module used for obtaining waveform data of the vibration and waveform data of the current and voltage from the GSM data communication module for rapid anti-aliasing Fourier transform processing and continuous real-time display.

A method for laying and changing material of reactor core fuel component on light water small power reactor includes setting reactor core in enclosed cylinder and dividing it to be central region and external region, laying fuel component in central region and setting idle component at external region when initial load is carried out, laying component unloaded from central region at external region to replace idle component when material of reactor core is changed, repeating said operation in following material change till burn up depth required by design is reached by unloaded component.

The invention discloses an upper reactor internal suitable for a floating type reactor, and relates to the field of marine nuclear power facilities. The upper reactor internal comprises a support cylinder, a guide cylinder and an accelerating energy storage device, wherein a horizontally arranged fixed bearing plate is fixedly arranged on the top of the support cylinder; the fixed bearing plate isprovided with a through hole, and reactor control rod assemblies can pass through the through hole; the guide cylinder is arranged in the support cylinder, and one end of the guide cylinder is embedded in the through hole of the fixed bearing plate; the accelerating energy storage device is arranged on the top of the fixed bearing plate and is used for providing additional kinetic energy for thereactor control rod assemblies when rod drop is performed by the reactor control rod assemblies. The upper reactor internal suitable for the floating type reactor comprises the accelerating energy storage device; the accelerating energy storage device is arranged in the upper reactor internal in a reactor pressure vessel, so that the accelerating energy storage function of the control rod assemblies in the reactor pressure vessel can be realized, and accelerated rod drop of the control rod assemblies of the floating type reactor is further realized under the marine environment conditions.

A completely passive cooling system for a post-incident reactor core of a large-scale pressurized water reactor nuclear power plant, comprising a shielded plant (4), a water tank (5), a cooling water distribution plate (8), a sprinkler water pipe (6), and an air deflector panel (9). A chimney (7) is arranged on the top part of the steel-concrete composite structured shielded plant (4). The water tank (5) is arranged above the shielded plant (4) and around the chimney (7). The cooling water distribution plate (8) is arranged above the top part of a safety housing (3) within the shielded plant (4). The sprinkler water pipe (6) is arranged on the inside of the top part of the shielded plant (4). A water inlet-end of the sprinkler water pipe (6) is connected to the bottom part of the water tank (5). A water outlet-end of the sprinkler water pipe (6) is extended above the cooling water distribution plate (8). A through air inlet (13) is provided on the top part of an outer wall of the shielded plant (4). The air deflector panel (9) is arranged between the shielded plant (4) and the safety housing (3). The upper end of the air deflector panel (9) is connected to the inside of the top part of the shielded plant (4). A double-layered top part is formed on the upper end of the cylindrical shielded plant (4), while a cylindrical air flow passage (16) is formed on the top part, where the double-layered steel-concrete top part constitutes the water tank (5). The cooling system employs the integrated modular design of the shielded plant (4) and the water tank (5), and enlarges the volume of the water tank (5), thus implementing long-term completely passive discharge of reactor core residual heat.

The invention provides a double-reactor-core zero-power device comprising a water reactor ad a lead reactor, the water reactor comprises a first fuel element, a first reactor core, a first control rodsystem and a water circuit system, the first reactor core is a pool structure, and is connected with the first control rod system and the water circuit system, the first fuel element is used for a nuclear fuel in the first reactor core, the first control rod system is used to control the first reactor core for zero power experiments, and the water circuit system is used for supplying deionized water to the first reactor core; the lead reactor comprises a first fuel element, a second fuel element, a second reactor core, a second control rod system and a safety block system, the second reactorcore is coupled to the second control rod system and the safety block system, the first fuel element and the second fuel element are used for a nuclear fuel in the second reactor core, and the secondcontrol rod system and the safety block system are used to control the second reactor core for zero power experiments. The device has the characteristics of being inherent in safety, flexible and variable in reactor core loading, convenient in operation, stable and reliable, accurate in measurement and good in repeatability.

The invention discloses an online monitoring device for an inter-turn short-circuit fault of a dry-type air-core power reactor and a monitoring method thereof, and relates to an online monitoring device for an inter-turn short-circuit fault of a reactor and a monitoring method thereof. The invention provides an online monitoring device and a monitoring method thereof that can accurately measure, have high sensitivity, and have a small workload even for small turn number faults. In the invention, collected data are transmitted to an upper computer for storage, and an initial loss factor of a monitored reactor system is calculated; an online monitoring system performs real-time sampling on signals of the reactor system; a current loss factor is divided by the initial loss factor, and if thequotient is less than a preset threshold, the current loss factor is repeatedly calculated; if the quotient is greater than the preset threshold, the current reactor has an inter-turn short-circuit fault, and the upper computer stores and displays the current data. The online monitoring device and the monitoring method thereof in the invention are mainly used for online monitoring of the inter-turn short-circuit fault of the dry-type air-core power reactor.

The invention relates to an encapsulating method of a large power reactor, which is characterized in that polyurethane encapsulating material is used for pouring a device to be encapsulated. The encapsulating method is mainly suitable for heating and filling air gaps in a multi-conductor wire and cable core or gaps between cable elements with any structure. The polyurethane encapsulating material not only has favorable insulation performance, mechanics property and chemical property of the epoxy resin, but also overcomes the weakness that the epoxy resin is fragile, has poor impact resistance and non-uniform strength at the high temperature and the epoxy resin is fractured at the low temperature; and at the same time, the polyurethane encapsulating material is toxic-free and resists the fire, and is free from containing the composition which is harmful to the human body and the environment.

The invention discloses a differential power reactor fault on-line monitoring instrument which comprises current transformers, proportional amplification units and data acquisition and processing units. Each bus aluminium bar branch of a reactor is provided with one current transformer for measuring a current of the branch. One group is formed by two current transformers. The two current transformers in each group have opposite secondary outlet polarities and are connected with the corresponding proportional amplification unit. Amplified current differential values are input into the corresponding data acquisition and processing units to be analysed and judged. Under the condition that the reactor does not have a fault, the amplified differential value output by each set of proportional amplification unit is close to zero; and when the reactor has faults of winding disconnection or turn-to-turn insulation discharge and the like, the differential value of the current transformer group connected with a fault winding is changed, and when the differential value exceeds a certain preset value, the data acquisition and processing unit outputs a reactor fault alarm signal. The monitoring instrument can be used for detecting the faults of power reactor disconnection or turn-to-turn partial discharge and the like and is reliable and rapid to respond.

An air core power reactor (10) having a noise mitigating sound shield (40). In one embodiment the sound shield includes a plurality of sound absorbing panels (42p) configured for positioning about an outermost reactor layer (12′) so that the panels reduce radiation of acoustic energy when the reactor coil layers carry current. One or more flexible members (48) are attached along the first side of each sound absorbing panel for contact with the outermost reactor layer. Sound barrier material (44) is positioned along the second side of each panel. When the flexible members are attached to a panel and the panel is installed about the outermost first layer of the reactor, the flexible members are positioned against the outermost first layer and the flexible members provide a gap between the first side of the panel and the outermost first layer of the reactor.

A method of fabricating metallic fuel from surplus plutonium may include combining plutonium oxide powder and uranium oxide powder to obtain a mixed powder with reduced proliferation potential. The mixed powder may be electroreduced in a bath of molten salt so as to convert the mixed powder to a first alloy. The first alloy may be pressed to remove a majority of the molten salt adhered to the first alloy to form a pressed alloy-salt mixture. The first alloy may be isolated from the salt by melting the pressed alloy-salt mixture. The first alloy may be further processed to fabricate a fuel rod. Accordingly, the metallic fuel produced may be used in a fast reactor system, such as a Power Reactor Innovative Small Module (PRISM).

The invention discloses a flue gas desulfurizing device, belongs to the field of non-ferrous metal production, and particularly relates to the field of sulfur-containing waste gas treatment in copper production. Aiming at the problem that the conventional desulfuration method cannot deal with the greater flue gas fluctuation of sulfur-containing flue gas, the invention provides the device which is more suitable for flue gas fluctuation performance and can effectively perform desulfuration. The flue gas desulfurizing device comprises a sulphuric acid tail gas absorption tower, a flue gas absorption tower, a medicine adding part and a separating part, wherein the liquid outlet in the bottom of the sulphuric acid tail gas absorption tower is externally connected with a clean liquid tank; the outlet of the clean liquid tank is communicated with a pipeline reactor; a medicine adding device is arranged at the inlet of the reactor; the outlet of the pipeline reactor is externally connected with a power reactor and a solid-liquid separator which are connected in series; the solid outlet of the solid-liquid separator is externally connected with filter pressing equipment; the liquid outlet of the solid-liquid separator is externally connected with the spray pump inlet of the flue gas absorption tower; the spray pump outlet attached to the flue gas absorption tower is further connected with the spray pump inlet attached to the sulphuric acid tail gas absorption tower; the flue gas absorption tower is communicated with the clean liquid tank. Through the adoption of the device, desulfurized products are easy to treat, and the flue gas desulfurizing device is has a higher property suitable for flue gas fluctuation.

An injection system designed to deliver a chemical solution into a reactor through feedwater system taps during normal operating condition of a power reactor is disclosed. The process of delivery is via positive displacement pumps. Injection of chemical is in a concentrated solution form, which is internally diluted by the system prior to discharging from the skid. The injection system minimizes chemical loss due to deposition on the transit line, enables a higher concentrated solution to be used as the injectant, eliminates the time consuming laborious process of chemical dilution, raises chemical solution to the pressure required for injection, prevents solid precipitations out of solution at the injection pump head through the use of a flush solution, and deposits fresh chemical on new crack surfaces that develop during a power reactor start-up, shutdown and operation.

The invention discloses a reactor actuation area for a traveling wave reactor. The reactor actuation area comprises fertile nuclides, fissile nuclides and simulated nuclides, wherein the concentration of the fertile nuclides is gradually increased along a direction from the front end part of the reactor actuation area to a novel fuel area, and the concentration of the fertile nuclides at the rear end of the reactor actuation area is the same as that of the fertile nuclides in the novel fuel area; along a direction from the front end part of the reactor actuation area to a combustion area, the shape of a concentration distribution curve of the fissile nuclides in the reactor actuation area corresponds to that of a concentration variation curve of the fissile nuclides at a certain point when breeding waves and combustion waves in the combustion area sequentially pass through the point in the combustion area; the concentration of the simulated nuclides is gradually decreased along a direction from the front end part of the reactor actuation area to the novel fuel area. The reactor actuation area has the advantages that the requirements of actuation of the traveling wave reactor for running are met, the production of reactive fluctuation is avoided, and the safety, economy and controllability of the reactor are improved. The invention also discloses a manufacturing method for the reactor actuation area.

The invention discloses a method for calculating the heat power of a pressurized water reactor in a nuclear power station. The pressurized water reactor comprises a four-loop EPR (European pressurized reactor) core, wherein the heat power value of each loop is calculated at first, and then the heat power values of the four loops are added to obtain the heat power value of the EPR core. The method for calculating the heat power of the loops comprises the following steps: comparing actual rotary speed of a pump with theoretical rotary speed of the pump to obtain the pump efficiency; subtracting cold-section liquid-phase enthalpy from hot-section liquid-phase enthalpy to obtain enthalpy rise value of each loop; multiplying the enthalpy rising value by the rated flow of the pump within unit time to obtain an actual volume flow value in each loop; multiplying each actual volume flow value by cold-section liquid-phase water density value to an obtain actual mass flow value in each loop; multiplying the pump efficiency by each actual mass flow value so as to obtain a result and dividing the result by 1000 to obtain a heat power value of each loop. According to the method, the heat power calculation of three loops is expanded to the heat power calculation of the four loops on the basis of a heat power calculation principle, and an existing heat power calculation method can be completely substituted. Therefore, the method can be well suitable for being used for calculating the EPR heat power.

The invention relates to a long-distance-disassembling-assembling sword-type mechanical arm. The long-distance-disassembling-assembling sword-type mechanical arm is used for a sampling cabinet of a power-reactor fuel-short-after-treatment middle test plant and sampling operation of a plutonium tail-end discharging working box. The inside of a clamp is connected with a nut rod through a rivet, the outside of the clamp is connected with a first sleeve through a countersunk head screw, and the outside of the countersunk head screw is covered with a polytetrafluoroethylene ring; one end of a guiding rod is provided with a screw rod and connected with a nut rod, and the other end of the guiding rod is connected with a core shaft through a pin; the first sleeve and a second sleeve rotate and are pressed through a nut and are connected through a cross recessed pan head screw; a compression spring is arranged at the tail portion of the core shaft and fixed through a spring base, and the spring base is connected with the second sleeve through a thread; a locking screw is arranged on the second sleeve; a trigger is connected with a connecting rod through a rivet, the connecting rod is connected with a rocking rod through a rivet, one end of the rocking rod is fixed at the lower end of a handle, and the other end of the rocking rod goes deep into a square trough at the tail of the core shaft. By means of the long-distance-disassembling-assembling sword-type mechanical arm, the problems that a sword-type mechanical arm trigger falls off, operation is heavy and arduous, the clamp faults, and the spring is lapsed and difficultly replaced are solved.

The invention discloses an MMC topology-based distributed hybrid energy storage and power compensation system. A single-star topological structure is adopted; sub-modules comprise energy storage medium parts and power level parts; each energy storage medium part comprises at least one energy storage battery and a capacitor; the batteries and the capacitors are connected to a main circuit loop through power-level different ports; and each power level part comprises a bridge arm module structure or a T-shaped module structure comprising power switches and power diodes. By the system, a high-current power reactor does not need to be used on the basis of not significantly increasing the number of the sub-modules; the power levels of the sub-modules are multiplexed; two kinds of energy storage mediums of the energy storage batteries and the capacitors are dispersedly distributed into various sub-modules to facilitate power balance on various energy storage mediums; and cooperative work of multiple mediums is conducive to technological economy consideration and optimization of an energy storage technology in multiple dimensions of the lifetime, the response speed, the conversion efficiency and the like.

An air core, dry type, power reactor (10) of the type having multiple concentrically positioned winding layers (12) extending along a central axis and above arms (24) of a first spider unit (16) when the reactor is horizontally positioned with respect to a horizontal ground plane, the winding layers (12) arranged in spaced-apart relation providing air gaps (20) between the winding layers allowing air to flow along the winding layers. A deflector (40) is positioned between the winding layers (12) and the ground plane to receive air from wind blowing toward the reactor (10) and guide the air in an upward direction from the deflector (40) and along the gaps (20).

The invention discloses a distributed control system (DCS) frame for a nuclear power reactor. The frame includes a safety-level DCS and a non-safety-level DCS; the non-safety-level DCS includes a non-safety-level monitoring device, a monitoring network, a non-safety-level gateway, a real-time server, a system network, a first control station, a diversified drive system and the like on an operationstation, wherein the non-safety-level monitoring device, the monitoring network, the real-time server, the system network and the first control station are connected in sequence; and the safety-levelDCS includes a plurality of protection groups, a specially-arranged safety facility drive cabinet, a data transmission cabinet, a safety-level bus, a safety-level gateway, a device interface cabinet,a safety-level monitoring device on a backup disk and the like, wherein the safety-level bus, the safety-level gateway, the non-safety-level gateway and the monitoring network are connected in sequence. By implementing the frame, a compact layout scheme of a main control room can be constructed on the premise of ensuring the basic functions of the main control room.

The invention belongs to a nuclear power plant reactor coolant system process measurement technology, and specifically discloses a nuclear power plant over-temperature and over-power protection temperature difference signal processing method. According to the present invention, a main circuit temperature difference signal requiring calibration is collected, the average value and the power average value are utilized to obtain a temperature difference calibration gain coefficient so as to calibrate the measured main circuit temperature difference signal; and during debugging, when a heat power is increased to 75%F-100%FP, a temperature difference signal calibration channel sets a calibration factor, such that operators can easily and visually compare the temperature difference signal values before and after calibration, accuracy of channel calibration is ensured, effectiveness of the over-temperature and over-power reactor trip protection function is ensured, and safety and economy of the nuclear power plant are increased.