4 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 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 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.