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.

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.

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 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.

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 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 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.