7 results about "Nuclear science" patented technology

The application discloses a neutron irradiation sample box convenient for remote operation and a dismounting tool thereof, and belongs to the cross field of nuclear science and technology application and equipment manufacturing. The sample box comprises a sample cover, a sealing sheet, a sample inner grid and a cavity. The sample cover is in threaded connection with the cavity. The sealing sheet is sealed by plastic deformation. The sample inner grid is divided into partition compartments for placing samples. The dismounting tool comprises an installation base, a screwing handle, a lower jaw, a circular arc knife edge, a sample box separation nut and an arched sample box positioning block and the like. The sample box is convenient for remote operation of adding and removing samples by special design. The non-welding sealing is adopted to guarantee sample irradiation conditions. The dismounting tool can be remotely operated in the whole process. The application further increases innovative features such as radiation-resistant adhesive, a pressure sensor and a fine adjustment device, improves sealing stability and operation accuracy, and solves the problems of inconvenience in remote operation, sealing and sample adding and removing of the traditional sample box.

This invention discloses a method for selecting measurement locations of flow heat transfer parameters in a thermal-hydraulic experimental device, relating to the field of nuclear science and technology. The method includes an initial screening stage: dividing the axial computational domain of the channel into several continuous regions, selecting possible measurement points within each region, and summing the segments to obtain an initial screening set containing n measurement points; and a final screening stage: analyzing the correlation of the measurement points using the Pearson correlation coefficient matrix, retaining only key measurement points with weak correlations, and obtaining a final optimized sparse measurement point set. This scheme achieves high-precision reconstruction of the temperature field under limited measurement point conditions through these two stages. Specifically, combining a correlation intelligent analysis algorithm with a segmented screening strategy enables effective parameter field inversion with low error using only a few measurement points, significantly reducing monitoring costs while ensuring monitoring accuracy. This scheme provides an efficient and reliable technical means for parameter field monitoring in engineering practice.

The invention provides a safety factor profile measurement system and method based on magnetofluid instability, relates to the technical field of nuclear science, and solves the problem of measurement of safety factor distribution of a Tokamak device in the prior art. A magnetic probe array in the system is used for measuring a circumferential modulus and a polar modulus of magnetofluid instability in plasma, and an electron cyclotron radiometer is used for measuring a spatial position of magnetofluid instability; a central processing unit of the system is used for determining the numerical value of a corresponding safety factor according to the circumferential modulus and the polar modulus of the magnetofluid instability, determining the spatial position of the corresponding safety factor according to the spatial position of the magnetofluid instability, and determining the position of the corresponding safety factor based on the determined numerical value and spatial position of the safety factor. And performing numerical fitting in combination with the boundary safety factor to obtain the safety factor distribution of the plasma full profile in the device. According to the method, the safety factors of different space points can be determined, the distribution of the safety factors can be obtained, and the reliability and robustness of measurement are improved.

The present invention belongs to the field of nuclear science and technology, specifically to a plasma density limit disruption warning and mitigation system. The system comprises: a plasma, a disturbance quantity measurement and diagnostic system, a balance quantity measurement and diagnostic system, a spectrum analyzer, a general fishbone mode dispersion relation solver, a central processing unit, a gas supply control system, a tokamak gas supply system, an electron cyclotron heating control system, an electron cyclotron, a radio frequency antenna, and a warning light. The system addresses the experimental phenomenon of plasma disruption that is prone to occur during high electron density operation in magnetic confinement fusion devices. By measuring the dynamic spherical ball model excited under high-density conditions as a warning signal, the system mitigates density limit disruption by reducing the electron density or controlling the dynamic spherical ball model through external means such as the gas supply system and the electron cyclotron heating system.

The invention discloses a kernel data multi-modal knowledge graph construction method, and relates to the technical field of knowledge graphs. The kernel data multi-modal knowledge graph construction method comprises the following steps: S1, acquiring multi-modal data in the field of kernel science and technology, wherein the multi-modal data comprises text modal data and image modal data; s2, constructing a multi-modal knowledge graph ontology of the kernel data; s3, integrating target detection, relation prediction and character recognition technologies for the image modal data to realize automatic extraction of entities, relations and attributes; s4, extracting structured knowledge from the text modal data by adopting a rule-based method; and S5, realizing fusion of the image knowledge and the text knowledge through entity alignment, and storing a fusion result into a graph database to complete construction of the kernel data multi-modal knowledge graph. By adopting the multi-modal knowledge graph construction method for the kernel data, deep fusion and knowledge mining of the kernel data can be realized, and data support is provided for multi-modal question answering, retrieval and recommendation application of the kernel data.

The invention discloses a neutron irradiation sample box convenient for teleoperation and a disassembly and assembly tool thereof, and belongs to the crossing field of nuclear science and technology application and equipment manufacturing. The sample box comprises a sample cover, a sealing piece, a sample inner grid frame and a cavity, the sample cover is in threaded connection with the cavity, the sealing piece is sealed by plastic deformation, and the sample inner grid frame is provided with partition compartments for placing samples; the disassembling and assembling tool comprises a mounting base, a screwing handle, a lower jaw, an arc knife edge, a sample box separating nut, an arched sample box positioning block and the like. Through special design, the sample box is convenient for teleoperation and sample addition and reduction, non-welding sealing is adopted to guarantee sample irradiation conditions, a dismounting tool can be subjected to full-flow teleoperation, innovative characteristics such as an irradiation-resistant adhesive, a pressure sensor and a fine adjustment device are added, the sealing stability and the operation accuracy are improved, and the sample box is convenient to use. The problems of inconvenience in remote operation, sealing, sample increase and decrease and the like of a traditional sample box are solved.

The present application relates to the technical field of Monte Carlo particle transport calculation and radiation safety analysis in nuclear science, and particularly relates to a method and system for determining shutdown dose rate of nuclear facilities, the method comprising: S1, calculating the generation rate of each photon generated by the decay of each secondary radionuclide and summing up to obtain the total generation rate of all photons corresponding to each collision when each collision occurs; according to the ratio between the generation rate of each photon at each collision and the total generation rate at the collision, sampling photons from all the photons generated at each collision, taking the total generation rate corresponding to each collision as the weight of the sampled photons corresponding to each collision, and performing photon transport calculation to count the photons in the target region, and combining the photon flux-dose conversion factor to obtain the shutdown dose rate distribution of the photons in the target region. The shutdown dose rate can be quickly and accurately calculated to provide accurate data support for subsequent processing of nuclear facilities.