34 results about "Nuclear system" patented technology

The invention discloses a method, a device and a system for scheduling in a multiprocessor nuclear system and relates to the field of the multiprocessor nuclear system. The method, the device and the system can meet real-time network input / output (I / O) processing requirements so as to promote efficiency of the whole multiprocessor nuclear system. The method for scheduling in the multiprocessor nuclear system comprises obtaining a first control parameter, a second control parameter, a third control parameter and a fourth control parameter in an operation period of the multiprocessor nuclear system; transmitting data packages of data streams entering the multiprocessor nuclear system to an idle processor nucleus for processing according to the first control parameter, the second control parameter and the third control parameter; and switching the processor nucleus in the multiprocessor nuclear system between a cutting-off mode and a polling mode according to the fourth control parameter. The method, the device and the system are mainly used for processor nucleus scheduling.

A logging system for measuring parameters of earth formation penetrated by a well borehole. Measurements made with the system are not adversely affected by varying pressure encountered a borehole environment. This is accomplished by the use of a main compensation element and a detector compensation element render source and detector geometry invariant to varying pressure. The system is particularly suited for nuclear LWD systems such as back scatter gamma ray density systems. The basic concepts of the system are, however, applicable to other types of nuclear measurement systems that comprise one or more radiation sources, and one or more axially spaced radiation detectors, where system response is a function of source-detector spacing. The basic concepts of the system are also applicable to other types of logging systems, such as electromagnetic and acoustic, where source (transmitter) and sensor (receiver) elements require invariant geometry in order to maximize accuracy of measurements.

The invention discloses a debug method suitable for a multiprocessor core system chip: a virtual main control processor core module (111) operating on a host machine is used to simulate a main control processor and a debugging control station program, take charge of sending and receiving commands, control the debugging of the multiprocessor core system chip, send a debugging command to a physical operation debugging service station module (131) of each processor core and receive responsive information to a software debugger (110) which runs on the host computer and is provided with a patterned interface. The debug method suitable for the multiprocessor nuclear system chip occupies small hardware resource, utilizes software to debug, has strong portability and is suitable for the network platform debugging of / on the multiprocessor nuclear system chip.

The present invention discloses a heterogeneous multi-nuclear system based on configurable processor and instruction set extension pertaining to the computer system technique field, including extension nucleus, a fundamental nuclear or an almightiness nuclear, wherein the fundamental nuclear includes a basic instruction set ISA1, for implementing the part that has not executed the instruction extension optimization in the operating system and the application program and being responsible for communicating control between nucleus, when the extension nuclear communicates with the fundamental nuclear, the FIFO is required to apply for open, the communication channels can be established after the fundamental nuclear authorizes the application. The extension nuclear contains a basic instruction set ISA1 and an extension instruction set, principally for the implementation of the part that has executed the instruction extension optimization in the application program, and also for the implementation of the part that has not executed the instruction extension optimization in the application program. The almightiness nuclear includes all the instruction set, which has functions of the fundamental nuclear and all the extension nucleus. The present invention has largely exerted the advantage of the extension instruction, simultaneously alleviates the burden on the fundamental nuclear, and effectively resolves the problem that the multithreading application program has low implementing efficiency.

An accelerator-driven subcritical breeding reactor is operated with a neutron multiplication coefficient as large as possible in order to require a small input power from the accelerator, reducing its dimension and hence its cost and complexity. The beam-generated spallation neutron yield then becomes comparable to the fraction of delayed neutrons from the fissioned elements. This can be exploited to ensure an accurate on-line determination of the reactivity. Resulting changes can be adjusted with the help of neutron absorbing control rods and / or variations of the proton current. In addition, the temperature variations during operation can be continuously monitored and adjusted in order to avoid that the subcritical systems approaches too closely the (delayed) criticality condition and that the neutron multiplication coefficient remains within acceptable limits.

This invention discloses one section memory space management method facing abnormal multi-nuclear system, which comprises the following steps: adopting sections; then realizes section page memory space management facing abnormal multi-nuclear system in page on program logic meaning; then dividing each section into same pages to keep section logic meaning as minimum unit in memory to avoid memory space chatter and to save memory space materials.

The present invention pertains to a method of controlling an accelerator coupled nuclear system comprising a nuclear reactor operating in subcritical mode and a neutron generator device using a beam of charged particles originating from an accelerator, said neutron generator supplying the quantity of neutrons necessary in order to maintain the nuclear reaction. Said method is characterized in that the operating point is determined by giving the energy Ep of the particles a value greater than or equal to the value EPMax, which maximizes the production of neutrons, and in that the number of neutrons is adjusted by acting on the energy of the particles originating from the accelerator, with constant beam intensity. The present invention also pertains to the accelerator coupled hybrid nuclear system used for same.

This invention discloses one imbed abnormal multi-nuclear buffer accordance method based on bus detection, which is based on one time strategy processor one degree high speed buffer accordance with main function to keep same data in multi-nuclear local one degree high speed buffer and sharing two degree high speed buffer multiple copy accordance. This invention is suitable for abnormal multi-nuclear system processor based on bus to combine two strategies advantages.

This invention discloses one section memory space management method facing abnormal multi-nuclear system, which adopts program and computer memory space design as one section structure composed of several sections, wherein, each program operation keeps self section list and uses list to record operation memory usage space; main process nuclear in abnormal system responds for total program operation for one list to realize system operation and its section list for integral management.

The invention provides a three-dimensional modeling method nuclear system combining a dome-screen camera and a depth camera, which relates to the technical field of three-dimensional imaging modeling.The system at least comprises the depth camera and a dome-screen camera. The method comprises eight steps that S1, a dome-screen camera lens and a depth camera lens are fixed at the same position inthe space; S2, photographing is carried out by using the dome-screen camera; S3, preliminary positioning is carried out through a VSSLAM algorithm; S4, the three-dimensional information and space information in the three-dimensional picture are adopted for calibration; S5, further accurate positioning is carried out; S6, a dense point cloud is formed; S7, the accurate dense point cloud is furtherobtained; S8 digital modeling is carried out to generate a three-dimensional model; S9 mapping of the three-dimensional model is automatically carried out according to the color information in the two-dimensional panoramic photo. The invention is advantageous in that the three-dimensional model has the advantages of the dome-screen camera and the depth camera at the same time, and the three-dimensional model is more accurate; the defects that the angle of the depth camera is single, the vision field is limited, and the dome-screen camera is prone to generating errors are solved.

The invention discloses a measured data acquisition method and a differential worth acquisition method for a reactor control rod. In the data acquisition method, pulsed neutrons are injected into a reactor by gradually inserting a tested control rod downwards, data acquired by a neutron detector is analyzed, and a leakage neutron attenuation curve is obtained. In the differential worth acquisitionmethod, differential worth of the control rod is obtained on the basis of the leakage neutron attenuation curve, and differential worth measurement of the control rod in a subcritical state is realized. In the processes, frequent rod switching is not needed, operation is simple and safe, measurement time is shortened, efficiency is improved, the defect that time and labor are consumed by frequentrod switching in a critical state in traditional differential worth measurement of the control rod is overcome, adverse influence factors in the measurement process are avoided, nuclear system safetyis facilitated, and accuracy of measurement results can be improved.

The invention discloses an airborne radioactivity diffusion prevention method for an underground nuclear power plant. An independent radioactivity monitoring system and an air supply and exhaust system are arranged in each underground grotto, and a pressure release grotto is arranged; a radioactivity processing system is arranged in the grotto; after a nuclear system in each underground grotto leaks, the radioactivity monitoring system sends a control signal to control isolation of the grotto, so that the grotto is isolated from surrounding grottoes; meanwhile, by comparison of a pressure monitoring signal of the grotto with a pressure monitoring signal of the adjacent grotto, air exhaust of the grotto adjacent to the leaking region is controlled, so that the negative pressure environment of the grotto with the leaking region relative to the surround grottoes is retained; a radioactive airborne object is discharged to the pressure release grotto for pressure release and temporarily storage according to a requirement of a radioactivity leakage condition and then is normally emitted after meeting the standard by radioactivity treatment. By construction of entity isolation and the negative pressure environment of the underground grottoes, the radioactive airborne objects in a nuclear accident of the underground nuclear power plant can be effectively isolated and treated, and release of the radioactive airborne objects in the nuclear accident to the atmospheric environment is avoided.

The invention discloses a novel ring-cavity multifunctional nuclear system, comprising a neutron source and a reactor; the neutron source is of cylindrical pipe structure, the center of the reactor is of ring cavity structure, the neutron source is extended through the center ring cavity of the reactor and fixed outside the reactor, a core is arranged in the reactor and around the wall of the center ring cavity of the neutron source, the core is radially supported by inner and outer barrels, the reactor is provided with an internal member, a diversion passage is formed between the internal member and the wall of the ring cavity, and the reactor has an independent reactor-target coupling boundary and is able to be compatible with various neutron source systems; the neutron source and the reactor do not share a common coolant boundary, and the requirement of structural materials for the compatibility of coolants is lowered; no liquid environment is provided outside the neutron source, and structural replacement reliability of the neutron source system is improved. By designing the inner and outer barrels for the reactor and using the coolant diversion scheme, the ring-cavity structure core fixation problem and the coolant stagnation problem are solved, and the safety of the reactor is improved.

The invention is suitable for the professional technical field of a million kilowatt level pressurized water rector nuclear power station and provides a method and a device for preventing a turbine control system of the nuclear power station from generating disturbance. The method comprises the steps of detecting the maximum acceleration of a rotor of the turbine in the nuclear power station when a power grid is subjected to a transient fault; setting the acceleration limitation of a high cylinder cutoff valve of the turbine in the nuclear power station to be larger than or equal to the maximum acceleration of the rotor of the turbine in the nuclear power station when the power grid is subjected to the transient fault; limiting a switch of the high cylinder cutoff valve of the turbine according to the acceleration of the high cylinder cutoff valve of the turbine in the nuclear power station. According to the method and the device for preventing the turbine control system of the nuclear system from generating disturbance, the high cylinder cutoff valve of the turbine is prevented from being subjected to the turbine locking phenomenon during the transient fault of the power grid.

An accelerator-driven subcritical breeding reactor is operated with a neutron multiplication coefficient as large as possible in order to require a small input power from the accelerator, reducing its dimension and hence its cost and complexity. The beam-generated spallation neutron yield then becomes comparable to the fraction of delayed neutrons from the fissioned elements. This can be exploited to ensure an accurate on-line determination of the reactivity. Resulting changes can be adjusted with the help of neutron absorbing control rods and / or variations of the proton current. In addition, the temperature variations during operation can be continuously monitored and adjusted in order to avoid that the subcritical systems approaches too closely the (delayed) criticality condition and that the neutron multiplication coefficient remains within acceptable limits.

The invention discloses a connecting material for being connected with a silicon carbide material and an application of the connecting material. The connecting material comprises any one or combination of two or more of lanthanide rare earth element, ternary layered rare earth silicide and a lanthanide rare earth element coated silicon carbide composite, wherein the chemical formula of ternary layered rare earth silicide is Re3Si2C2, and Re represents the lanthanide rare earth element. The invention further discloses the application of the lanthanide rare earth element, ternary layered rare earth silicide or the lanthanide rare earth element coated silicon carbide composite to connection with the silicon carbide material, and also discloses a connecting method of the silicon carbide material. The characteristic of high-temperature instability of layered rare earth silicide is utilized, and generation of a rare earth liquid phase facilitates densified sintering of joint interface silicon carbide; the obtained silicon carbide connecting structure is high in bending strength and excellent in high-temperature resistance, oxidization resistance and corrosion resistance and can be applied to extreme service environments such as aerospace, nuclear systems and the like.

The process of the present application facilitates the production of electric energy for spacecraft by the seizure of beta-minus particles and electrons present in the medium of space above and beyond the planet's atmosphere. The features of the subject process make each spacecraft independent from domestic energy sources as are typically required by other electrical systems. In terms of energy production, the subject process will outperform all of the traditional systems applied to spacecraft including photovoltaic setups, fuel cells, batteries and nuclear systems. Photovoltaic panels situated in space are quickly degraded by bombarding cosmic ray particles and solar wind emissions. Since fuel cells require very high operating temperatures, it exposes the craft, its instrumentation and occupants to constant danger. By utilizing the process of the present application, it is no longer necessary for spacecraft to carry large quantities of chemicals for batteries, fuels and oxidizers for fuel cell generators, hazardous nuclear generators or large bulky photovoltaic panels subject to frequent malfunction. It is an innovative process for the production of electric energy by the attraction and seizure of beta-minus particles and electrons emitted from the Sun's corona as part of the solar wind that permeates the heliosphere. Because it captures free electrons directly, it does not consume power to convert one form of energy into another. It functions continuously throughout and beyond the heliosphere. It can be scaled to accommodate the electric power requirements of all spacecraft, including satellites and space stations. The process will accommodate the electric needs of base stations and surface vehicles situated on various moons and asteroids throughout the solar system including the planets Mercury and Mars. Some of the terms that describe the advantages of the process of the present application are simplicity, efficiency, adaptability, versatility, low energy consumption, and high productivity. Consequently, a reliable, enduring and safe electric power source for space craft has not been available until the development of the process of the present application.

The invention relates to the technical field of nuclear safety and nuclear system detection, in particular to a pressurized water reactor nuclear power station primary circuit total gas content measuring device which comprises a shielding protective cover, and a sampling assembly and a sample measuring assembly which are detachably connected with the shielding protective cover. The sampling assembly comprises a sampling bottle; a valve I connected with a bottle opening of the sampling bottle through a pipeline; a valve II connected with the other bottle opening of the sampling bottle through apipeline; a first quick female joint connected with the valve I through a pipeline; a second quick female joint connected with the valve II through a pipeline; and a balance pipeline, wherein one endof the balance pipeline is connected with the pipeline located between the valve I and the first quick female joint, and the other end of the balance pipeline is connected with the pipeline located between the valve II and the second quick female joint. The total gas content measuring device is convenient to disassemble and assemble, convenient to carry, capable of rapidly sampling and accuratelymeasuring the total gas content of the primary loop, and can be effectively used for detecting the gas content of the coolant in the primary loop.

The present invention is a protection equipment to prevent reactor loop and other non-nuclear system from overpressure, and the valve includes pressure-resisting valve body, spring pressure system acting on clack to maintain sealing, movable piston sealed by metal diaphragm, spring, adjusting screw for pre-fastening spring,etc. The valve is opened and closed automatically under the direct action of pressure medium, or it may be also forced to open and close by means of gas source or electric power. It has no supplementary valve and is simpler and more reliable than available guide safety valve. Being good in performance and long in service life, it may be widely used in both nuclear and non-nuclear systems.

The invention relates to the technical field of nuclear safety and nuclear system detection, in particular to a method for measuring total gas content of a pressurized water reactor nuclear power primary circuit, which comprises the following steps: S01, sampling a primary circuit coolant through a sampling assembly; s02, measuring gas content measurement data in the sample coolant through a sample measurement assembly and a sampling assembly; and S03, calculating the total gas content of the sample coolant according to the gas content measurement data and a gas content measurement formula. The method for measuring the total gas content of the pressurized water reactor nuclear power primary loop is simple and convenient to operate, and can be used in cooperation with the measuring device to quickly and accurately measure the gas content in the primary loop, so that the degassing effect of a primary loop coolant is conveniently judged, and safe and efficient operation of a main pump isensured.

The invention relates to a method for evaluating keff uncertainty caused by nuclear cross section deviation, and belongs to the technical field of nuclear data evaluation. The method comprises the following steps: S1, selecting nuclides needing to be evaluated in a nuclear system to be analyzed; S2, selecting a nuclear cross section, which needs to be evaluated, of each nuclide; S3, respectively calculating the sensitivity of each nuclear cross section selected in the step S2; S4, selecting covariance data corresponding to each kernel cross section, and adjusting or estimating the covariance data; S5, respectively calculating the uncertainty Unck of each covariance matrix to the keff; and S6, calculating the uncertainty Unc of the keff caused by the nuclear cross section deviation of the nuclear system. According to the method provided by the invention, the influence of each covariance matrix on the keff uncertainty is calculated through the nuclear cross section sensitivity data and the covariance data, so that the uncertain value of the keff caused by the nuclear cross section deviation can be quantitatively obtained, and design, analysis and evaluation can be guided.

The invention relates to a data migration system and method based on a many-core system. In a many-core system, the CPU in the PE of the lower layer is connected to the SRAM in the PE of the upper layer through AHB; The SRAM performs read and write operations; the master / slave converter is set between the PE of the lower layer and the PE of the upper layer, and the slave interface of the master / slave converter is connected to the master interface of the CPU in the PE of the lower layer, and converted into a The master interface of the AHB protocol in the upper-layer PE is connected to the slave interface of the SRAM in the upper-layer PE through the AHB protocol, so as to control the SRAM in the upper-layer PE. The invention can perform inter-chip data migration with high performance and low energy consumption.

The invention relates to a method for evaluating the similarity of a nuclear system based on a sensitivity space included angle. By adopting the method provided by the invention, a correction value of an included angle of the sensitivity vectors of the two nuclear systems in the space is calculated through the nuclear cross section sensitivity data, the relative covariance matrix data and the uncertainty caused by the nuclear cross section deviation, so that the similarity index of the two nuclear systems is obtained; and a quantitative judgment standard can be provided for the similarity of the two nuclear systems. According to the method, the similarity of the nuclear system is quantified by adopting a method for quantitatively evaluating the similarity of the nuclear system, a powerful basis can be provided for analyzing and screening critical reference experiment data, then the nuclear safety characteristics of the nuclear system are evaluated, the accuracy of nuclear safety evaluation work is improved, and help is provided for nuclear critical safety evaluation workers.

A multi electrode sensor that provides in-situ, real time measurements for molten salts and other process fluids such as real-time concentration and salt level measurements for nuclear systems such as molten salt reactors, nuclear reprocessing facilities utilizing molten salts and concentrated solar power systems. The sensor has multiple electrodes with unique lengths which are connected to a potentiostat. Measurements are taken when the electrodes are immersed in the process fluid.

The invention relates to the technical field of nuclear safety and nuclear system detection, in particular to a device for measuring the total gas content of a pressurized water reactor nuclear power primary circuit, including a shielding shield, a sampling assembly and a sample measuring assembly detachably connected to the shielding shield ; The sampling assembly includes a sampling bottle; Valve one is connected to a mouth of the sampling bottle through a pipeline; Valve two is connected to another mouth of the sampling bottle through a pipeline; the first quick female connector is connected to a mouth of the sampling bottle through a pipeline It is connected with the valve one; the second quick female connector is connected with the valve two through the pipeline; the balance pipeline is connected with the pipeline between the valve one and the first quick female connector at one end, and the other end is connected with the pipeline located between the first quick female connector. The pipeline connection between the valve two and the second quick female joint. The total gas content measuring device of the present application is convenient to disassemble and carry, can take samples quickly, accurately measures the total gas content of the primary circuit, and can be effectively used to detect the gas content of the coolant in the primary circuit.