43results about "Nuclear energy generation" patented technology

The invention relates to a large nuclear reactor molten pool natural-convection heat transfer test system and method. The system comprises a large molten pool natural-convection heat transfer test piece, a molten salt heating furnace supplying high temperature melt, a nitrogen source connected to the test piece and the molten salt furnace, and a cooling water loop. The test system also includes supporting power distribution equipment, instrument control equipment and data measurement and acquisition equipment. In the cooling water loop, a centrifugal water pump drives water in a cooling water tank to take away a decay heat source through a cooling channel of the test piece, heated cooling water restores to an initial water temperature through a plate heat exchanger and a cooling tower and then returns to the cooling water tank. When the molten pool temperature reaches a steady state, the test ends, and the waste liquid in the test piece is discharged into a waste liquid pool. The invention also provides a test method. By means of the large nuclear reactor molten pool natural-convection heat transfer test, molten pool heat transfer data under a reactor serious accident condition can be acquired for safety design.

The invention discloses a feedforward-feedback composite control method and a control system for the pressure and the liquid level of a nuclear power station voltage stabilizer. A voltage stabilizer liquid level set value is recalculated; a new voltage stabilizer liquid level set value is only relevant to the average temperature set value of a loop cooling agent at current power and zero power; mismatched signals of primary loop reactor power and a secondary loop stream turbine power are taken as feedforward signals, and are introduced into a pressure and liquid level control system of the voltage stabilizer, thereby forming a feedforward-feedback consistency control scheme; the liquid level and the pressure of the voltage stabilizer can be subjected to corresponding compensation control in advance, so that the control effect of the voltage stabilizer is enhanced, the voltage stabilizer can reach a stable state more rapidly, and the stability of a pressurized water reactor nuclear power unit during frequency and peak load modulation is further enhanced.

The invention discloses a control method of a nuclear power station safety level DCS. The control method includes the steps that two or more driving signals sent by equipment are received; the driving signals are subjected to priority ranking according to preset priority management logic; a first driving instruction is generated according to the ranked first driving signal so that an equipment driving device can execute operation according to the first driving instruction. According to the control method of the nuclear power station safety level DCS, in the control process of a nuclear power station safety level digital instrument control system, a multifunctional and intelligent control technology can be achieved. Besides, the invention discloses a multifunctional interface of the nuclear power station safety level DCS.

Process for treating spent nuclear fuel (SNF) to make mixed metal oxides of UO₃ and PuO₂ to prevent nuclear proliferation. The process comprises the steps of (1) dissolving spent nuclear fuel in an acidic solution in the presence of an agent that reduces Pu⁺⁶ to Pu⁺⁴ and an agent that oxidizes Pu⁺³ to Pu⁺⁴; (2) extracting U⁺⁶ and Pu⁺⁴ from acidic solution with an organic solvent comprising a ligand that binds U⁺⁶ and Pu⁺⁴ and which is soluble in the organic solvent; (3) jointly extracting U⁺⁶ and Pu⁺⁴ from the organic solvent with an acidic aqueous solution; and (4) precipitating a mixture of U⁺⁶ and Pu⁺⁴ by adding a carboxylic acid to the acidic aqueous solution. The U⁺⁶ and Pu⁺⁴ precipitate is then be calcined to form a mixed metal oxide of UO₃ and PuO₂. Additional steps can result in the formation of a mixed metal oxide of UO₃, PuO₂ and NpO₂ as well as the removal and isolation of technecium from the SNF.

The invention relates to a rod pulling system and process for a nuclear fuel assembly. The system comprises a rod pulling and preassembling box platform, a skeleton assembling and clamping platform and a rod pulling host machine, wherein the skeleton assembling and clamping platform is arranged between the rod pulling and preassembling box platform and the rod pulling host machine. According to the device, a moving mechanism and a lifting mechanism are arranged on the rod pulling and preassembling box platform and the rod pulling host machine, thereby improving the automation degree in the whole technical process. According to the process, each cylinder is further controlled through a PLC program, thereby realizing the control on each pull rod, ensuring more flexible rod pulling, and improving the quality and efficiency of the process.

A aluminum base alloy containing boron and manufacturing method thereof, said alloy exhibiting good mechanical properties (such as high-temperature strength and creep strength) over a long period of time and also having a neutron absorbing capacity owing to boron present therein in the form of a compound without segregation. The alloy contains 0.5–10 mass % of boron with an isotopic element satisfying a relation of ¹⁰B/(¹⁰B +¹¹B)≦30%. said boron being present in the form of a boron compound which is 300 μm or below in size. The alloy is obtained by melting at a temperature in excess of 950° C. and cast at a temperature in the range of 800° C. to 950° C., in such a way that the molten metal is kept for 60–180° seconds until it cools from 950° C. to the casting temperature.

The invention discloses a containment pit strainer overall performance experimental system and method; the system comprises: a containment pit simulation tank having a medium outlet and a medium reflow inlet; a strainer module mounted in the containment pit simulation tank to filter an experimental medium flowing out of the medium outlet; a circulating pump connected to the medium outlet through a pipeline; an experimental branch including a fuel component simulation provided with a fluid inlet at one end and a fluid outlet at the other end, wherein in the fuel component simulation, the fluid inlet is communicated with the fluid outlet, the fluid inlet is connected to the circulating pump through a pipeline, and the fluid outlet is connected to the medium reflow inlet through a pipeline. The containment pit strainer overall performance experimental system and method allow operating environment of a pit under long-term cooling recirculating to be simulated under different scrap quantities, chemical environments and temperatures, the behaviors, such as hydraulic characteristics and scrap blocking characteristics, of the containment pit strainer and reactor core fuel component are acquired, and the system and method are highly universal and comprehensive and are simple to control and perform.

A debris exclusion and retention device traps and retains foreign material within the lower tie plate of the fuel assembly utilizing the existing flow paths within the lower tie plate, and without redirecting coolant flow. Flow through the inlet nozzle of the lower tie plate into an enlarged lower tie plate housing creates strong jet impingement against the center of the lower tie plate grid or debris filter, if present, which has a tendency to push debris to the periphery of the lower tie plate. Low flow zones around the periphery of the lower tie plate allow debris to fall back toward the inlet nozzle. The retention device traps and retains debris in these low flow zones without impacting existing flow patterns in the lower tie plate. Thus, the retention device has minimal or no impact on lower tie plate pressure drop.

The invention discloses a testing device and method of an inclination detection instrument on a floating roof of a container in a nuclear power station and solves the technical problems of long alarm value testing time, big debug difficulty and poor precision of an inclination detection instrument in the prior art. The testing device comprises a foundation support (21), a base (23), a tray assembly (24), a lifting rod (24) and a feeler gauge (26), wherein the foundation support (21) and the base (23) are connected through supporting pieces (22); the tray assembly (24) is arranged on the base (23) and comprises a tray (241) and a connecting piece (242) connecting the first end (241-1) of the tray (241) with the first side (231) of the base (23); the lifting rod (25) is inserted into the second end (232) of the base (23); the feeler gauge (26) is inserted between the lifting rod (25) and the foundation support (21) when the inclination detection instrument body (100) is used for testing, so that the included angle of the tray (241) and the base (23) and the inclination angle of an inclination detection instrument body (100) on the tray (241) can be adjusted, and an alarm value can be determined in the adjustment process.

The invention relates to a test device for simulating a marine nuclear reactor fluid natural circulation loop. The test device comprises a swing table and a natural circulation loop device. The swingtable comprises a positioning platform and a driving assembly. The natural circulation loop device is arranged on the positioning platform, and the driving assembly supports and drives the positioningplatform to do multi-degree-of-freedom motion so as to drive the natural circulation loop device to swing to simulate ocean motion conditions. The natural circulation loop device comprises a heat source simulation body and a cold source simulation body communicated with the heat source simulation body through a circulation pipeline. A working medium in the heat source simulation body flows into the cold source simulation body through the circulating pipeline after being heated, and flows back to the heat source simulation body after being cooled. The natural circulation loop device is drivenby the swing table to swing through multi-degree-of-freedom motion so as to simulate ocean motion conditions, and reliable test parameters are provided for various natural circulation loops.

The invention discloses a plasma facing experimental part with a reference corner structure. The plasma facing experimental part comprises an experimental part and a reference corner arranged at one end of the experimental part, wherein the reference corner is an attenuation structure reserved on the experimental part in the event of processing the experimental part; one surface of the reference corner is used as the original surface; one surface of the experimental part is used as an experimental surface; and a mark for experiments is arranged on the original surface. According to the invention, corrosion, deposition, impurity migration and retention of materials are represented by cutting off the reference corner, taking related data of the surface, the side surface and the body of plasma as original data, and referring and comparing the original data with the data of the experimental part subjected to a plasma irradiation experiment before carrying out the plasma irradiation experiment. The plasma facing experimental part has the advantages of being simple and easy for design, convenient for processing and better in comparison and can be applied to testing of a plasma facing material in a nuclear fusion experimental device and an interaction experiment between the plasma and a wall material.

The invention relates to a neutron absorption ball preparation method which includes the following steps: the carbon material and neutron absorption material are mixed to form powder material, the powder material is added to the mixed water solution of PVA and PEG under stirring state, boric acid is added to the solution during kneading process to prepare the thickener; the neutron absorption ball is prepared after pre-pressing, extrusion forming, carbonization, cutting, grinding, high temperature treatment and surface packaging treatment. The invention adopts PVA as bonding agent, is environment-friendly and has low price. The extrusion forming technique has high efficiency, low equipment investment and meets the large-scale industrial production requirement.

A transient mitigation system for a reactor includes: a reactor core isolation cooling system; and a high pressure flooder system including a high pressure flooder pump and a flooder valve. When the water level of the reactor water in the reactor decreases to a first predetermined water level, the reactor core isolation cooling system is activated to supply the cooling water into the reactor. When the water level in the reactor decreases to the first predetermined water level, the high pressure flooder pump is activated. When the water level in the reactor decreases to a second predetermined water level lower than the first predetermined water level, the flooder valve is opened to inject the cooling water into the reactor.

The invention provides a primary loop heating and humidifying system and a primary loop heating and humidifying method for a high-temperature gas cooled reactor nuclear power station. The system comprises an evaporator inlet isolating valve, an evaporator, a main steam valve, a drain valve, a pressure vessel and an external steam charging valve unit, wherein the evaporator inlet isolating valve, the evaporator and the main steam valve are connected in sequence; the drain valve is arranged between the evaporator inlet isolating valve and the evaporator; and a pipeline between the evaporator andthe main steam is connected with the external steam charging valve unit. According to the method provided by the invention, external steam is charged to a secondary side of the evaporator via the external steam charging valve unit, and a working medium in a primary loop is heated inside the evaporator, so the temperature of the primary loop is increased, and the requirements of heating and dehumidification of the primary loop are met.

An embodiment of the present invention provides a tritium measurement system (100) for a pool reactor, comprising: an attenuation module (10) arranged to be connected with a coolant loop of the pool reactor, from which a coolant flows into the attenuation module (10), the attenuation module (10) attenuating the coolant; a measuring module (11) connected with the attenuation module (10) and used for measuring the tritium activity of the attenuated coolant flowing out of the attenuation module (10); and a circulating module (12) connected with the measuring module (11) and used for discharging the measured coolant into the coolant loop of the pool reactor. According to the tritium measurement system provided by the embodiment of the invention, the tritium measurement precision is improved, the measurement environmental protection property and safety are improved, the long-term measurement operation cost can be reduced, and the personnel investment is reduced.

The invention discloses a desktop type plasma ultrafast X-ray source, which comprises a vacuum cavity, a reaction cavity, a target belt, shielding belts, an X-ray CCD, a target belt transmission system, a shielding belt transmission system and an external light path system, wherein the reaction cavity is positioned in the vacuum cavity; the left side wall and the right side wall of the reaction cavity are each provided with two vertically-arranged shielding belt strip-shaped passing seams and a vertically-arranged target belt strip-shaped passing seam; the target belt penetrates through the two target belt strip-shaped seams in the reaction cavity and is driven by the target belt transmission system to move, the number of the shielding belts is two, the two shielding belts penetrate through the two shielding belt strip-shaped seams in the rear side of the reaction cavity and the two shielding belt strip-shaped seams in the front side of the reaction cavity respectively, and the shielding belt transmission system drives the shielding belts to move. The side wall of a cavity body of the vacuum cavity is provided with an optical window located on the front side of the reaction cavityand an X-ray window located on the rear side of the reaction cavity. When the desktop type plasma ultrafast X-ray source is applied, the photon yield is sufficient, the data acquisition period is short, the reliability of experimental data can be ensured, and the performance parameters and stability of equipment can be greatly improved.

This disclosure describes various configurations and components for bimetallic and trimetallic claddings for use as a wall element separating nuclear material from an external environment. The cladding materials are suitable for use as cladding for nuclear fuel elements, particularly for fuel elements that will be exposed to sodium or other coolants or environments with a propensity to react with the nuclear fuel.

In a method for heat treating a fuel assembly channel made of zircaloy, the channel is continuously moved relative to a heat-treatment device and, longitudinal sections of it are heated to the beta phase range in an inductive heating zone. The longitudinal section of the channel heated in this manner is than cooled in a cooling zone to a temperature within an alpha phase range. The heat treatment is effected by at least two heating devices, which are spaced apart from one another, operate independently of each other, and each contain at least one induction coil and together form a heating zone. The channel section is first heated using a first heating device and then heat-treated using a second heating device which has less power and in that cooling is effected using a stream of inert gas applied to the outer surface of the channel.

The invention relates to the field of intelligent fault diagnosis of rotating equipment, and especially relates to a lubricating monitoring system and method for important rotating equipment of a nuclear island. The lubrication monitoring system for the important rotating equipment of the nuclear island comprises: an environment temperature probe which is arranged in an environment around important rotating equipment and is connected with an important rotating equipment lubrication monitoring system control platform; and ultrasonic-temperature probes which are arranged at the driving end and the non-driving end of the important rotating equipment and are connected with the important rotating equipment lubrication monitoring system control platform. The monitoring method comprises the following steps: measuring the environment temperature; measuring temperature and ultrasonic values of the driving end and the non-driving end of the important rotating equipment; and comparing the temperatures of the driving end and the non-driving end with the environment temperature, comparing the ultrasonic values of the driving end and the non-driving end with the reference value, determining the condition of the important rotating equipment according to the comparison condition, and carrying out corresponding processing. According to the invention, ultrasonic monitoring is added on the basis of temperature monitoring, so that the monitoring effect is more sensitive and direct.

The invention relates to an electromagnetic adsorption sealing feeding device and method, and belongs to the technical field of environmental protection. According to the technical scheme, a moving soft connection (6) is arranged between a moving soft connection upper flange (4) and a moving soft connection lower flange (8), a thrust spring (7) is arranged between the moving soft connection (6) and an adsorption fit electromagnet (5), and a pneumatic inserting plate valve (13) can open and close a feeding channel at the top of a silo (15); and the gate position proximity switch (11) is arranged on the moving route of the pneumatic inserting plate valve (13) and located in the feeding channel at the top of the silo (15), a lower flange (8) of the moving soft connection at the discharging groove part is matched with a flange connection short section (9), and pressing fit and sealing are conducted. The electromagnetic adsorption sealing feeding device can realize full-closed discharging,and achieve the effect of zero spillover of dust, the convenience and fastness are achieved, the time and effort are saved during maintenance and repair, the accurate detection result is ensured, theoperation is facilitated, and the applicability is high.

The invention concerns a liquid metal-cooled fast-neutron nuclear reactor (1), comprising a system (2) for removing at least part of both the nominal power and the residual power of the reactor, which ensures, at the same time:

• • removal of the residual power in a totally passive manner from the initial instant of the accident;
  • removal of the heat through the primary vessel;
  • implementation of a final cold source (container with PCM) other than the sodium/air or NaK/air heat exchangers used in the prior art.

The present invention provides a method for early warning of an abnormality sign of a device, which includes device importance and warning validity determination, and a system therefor. The method for early warning of the abnormality sign of the device comprises: a first step of determining by an early warning processing apparatus whether a device monitoring signal value exceeds a normal operation range by using a weight value on the basis of monitoring-parameter-specific importance data which has been previously analyzed by an operator; a second step of generating a warning by the early warning processing apparatus when the device monitoring signal value exceeds the normal operation range; and a third step of determining by a warning determination apparatus whether the generated warning is a valid warning, which is subject to a warning analysis and to be traced.

The invention discloses an NNBI positive and negative ion beam deflection-ion phagocytosis integrated structure. The structure comprises a structural frame, a dipolar iron yoke electromagnet and magnetic circuit structure, an ion phagocytosis structure and neutral beam transmission channel, a magnetic circuit structure, a dipolar magnet excitation coil, an excitation coil non-magnetic stainless steel sealing box, an excitation coil hollow winding, an excitation coil excitation wire inlet and outlet sealing pipe, an ion phagocytic organ cooling water inlet main pipe, an ion phagocytic organ cooling water outlet main pipe, a negative ion beam phagocytic front plate, a negative ion beam phagocytic bottom plate, a negative ion beam phagocytic rear plate, a positive ion beam phagocytic front plate, a positive ion beam phagocytic top plate, a positive ion beam phagocytic rear plate, a beam transmission channel right side plate and a beam transmission channel left side plate. The integrated deflection and phagocytosis structure has the beneficial effects that the manufacturing difficulty of the beam deflection and phagocytosis structure with high particle energy is simplified, the beam interception rate of a positive and negative ion deflection magnet and an ion phagocytic organ is reduced, and particularly, the mounting difficulty of a large magnet and the deflection structure is greatly reduced.

The invention relates to the technical field of measuring instruments, and discloses a neutron measuring instrument for protection detection. The neutron measuring instrument comprises a device body,a chassis is fixedly connected with the bottom of the device body, a cross frame is fixedly connected with the bottom of the chassis, square boxes are movably inserted into the two ends of the outer surface of the cross frame, and threaded parts are fixedly connected into the square boxes; a threaded rod is in threaded connection with the interior of each threaded part in a sleeving mode, a rotating block is fixedly connected with the top of each threaded rod, a base is fixedly connected with the bottom of each threaded rod, and a second rotating column is fixedly connected with the outer surface of one side of each square box. Through the designed rotating blocks, the threaded parts, the base, the threaded rods and square blocks, the two ends of each square block can be conveniently inclined, and the two square boxes are driven to relatively move in the cross frame, so that the two bases can be in contact with the uneven ground more conveniently, and operation is convenient.