12 results about "Nuclear data" patented technology

The invention discloses a fission yield experiment data screening method, and relates to the technical field of nuclear data evaluation.The method comprises the steps that S1, fission yield experiment data are obtained from an EXOR database, and the experiment data are grouped; s2, fitting each group of fission yield experimental data by adopting a Zp model, and determining model parameters; the fission yield is calculated according to the determined model parameters, so that a yield calculation value is obtained; s3, calculating the deviation between the fission yield experiment data and the fission yield calculation value obtained in the step S2; and S4, screening the experimental data according to the deviation obtained in the step S3. According to the method provided by the invention, the evaluation efficiency can be effectively improved, the research period is shortened, and technical support is provided for further establishing an experimental database.

This invention discloses a monolithic, high-performance integrated nuclear and chemical gas detector, belonging to the field of nuclear and chemical detection technology. The invention includes a nuclear radiation detection module, a chemical gas detection module, and a central control and processing module. The nuclear radiation detection module and the chemical gas detection module are integrated and both connected to the central control and processing module. The nuclear radiation detection module includes a sampling module and a nuclear data output module, while the chemical gas detection module includes a chemical gas sampling module, a gas analysis module, and a gas data output module. This invention achieves integrated detection of both nuclear radiation and chemical gases. Through modular design and central control coordination, it enables simultaneous acquisition and analysis of nuclear radiation and chemical gases, achieving efficient and integrated monitoring of nuclear and chemical substances. Simultaneously, the integrated detection modules significantly reduce size and power consumption, making it more suitable for portable applications and improving the efficiency and comprehensiveness of early warning in hazardous scenarios.

The application discloses a multi-nucleus neutron nuclear reaction data verification method and device based on deep learning, comprising the following steps: determining a target nucleus to be evaluated, and obtaining multi-dimensional physical characteristic data of the target nucleus from a preset evaluation nuclear database and an experimental database; performing physical perception preprocessing and feature splicing on the multi-dimensional physical characteristic data to obtain a physical characteristic vector of the target nucleus; constructing and training a nuclear data correction model with uncertainty quantification capability; determining evaluation cross-section data and uncertainty data of the target nucleus according to the nuclear data correction model and the physical characteristic vector, and encapsulating the evaluation data of the target nucleus according to the evaluation cross-section data and the uncertainty data; verifying the evaluation data based on particle transport simulation, and optimizing the evaluation nuclear database according to the verified evaluation data. The application improves the efficiency and reliability of neutron nuclear reaction data evaluation and verification, and can be applied to the technical field of data processing.

The invention discloses a critical parameter prediction method, a readable storage medium and a device, and belongs to the technical field of nuclear systems, and the prediction method comprises the steps: determining a to-be-predicted new nuclear system and a calculated value of an existing critical experiment; calculating sensitivity vectors of the new nuclear system and the critical experiments to the nuclear data; on the basis of the calculated value and the sensitivity vector, in combination with the relationship between the experimental value of the existing experiment, the experimental uncertainty and the critical experimental coefficient, constructing a calculation formula of the critical parameter predicted value and the predicted uncertainty of the new nuclear system; solving a coefficient of a critical experiment enabling the uncertainty of the prediction parameters to be minimum; and substituting the coefficient into the two calculation formulas to obtain a predicted value and the uncertainty thereof. The method is stored in the readable storage medium. The device comprises a terminal program for executing the steps of the method. According to the method, the information of a plurality of critical experiments can be effectively integrated, the critical parameters can be more reliably and accurately predicted under the condition of lack of very similar critical experiments, and the uncertainty of the prediction parameters can be more effectively compressed.

The present application relates to a kind of neutronics calculation uncertainty quantification method, system, equipment and medium, belong to neutronics calculation field.The method includes: based on the covariance information in nuclear data evaluation library making nuclear data covariance library;Using direct numerical perturbation method calculates the sensitivity coefficient of nuclear reaction cross section to spallation neutron source;According to the nuclear data covariance library and the sensitivity coefficient, the uncertainty of spallation neutron source is calculated;According to the nuclear data covariance library and the uncertainty of spallation neutron source, using Latin hypercube sampling method is sampled to generate calculation sample;Based on the calculation sample, the ADS neutronics calculation result is obtained by executing ADS neutronics calculation;The uncertainty of the ADS neutronics calculation result is determined by performing mathematical statistics analysis to the ADS neutronics calculation result.The present application improves the calculation efficiency and calculation accuracy of the uncertainty of ADS neutronics calculation.

The application discloses a kind of production methods of delayed photon ACE format database, first, the fission yield sublibrary and decay sublibrary of evaluation nuclear database are used to calculate the delayed photon production cross section;The delayed photon energy distribution can be obtained by processing the decay photon spectrum into the form of equal-probability energy band;To ensure that the average energy of the delayed photon obtained by calculation is the same as the average energy of the delayed photon given in the evaluation nuclear database, the delayed photon production cross section is corrected;Finally, the delayed photon production cross section, the delayed photon energy angle distribution information is stored in the ACE format database.The application proposes a kind of production method of delayed photon ACE format database, and the method has the advantages of high calculation accuracy and fast calculation speed in Monte Carlo program.

The invention relates to a separation device and method for fission products zirconium, niobium, molybdenum, antimony and silver, belongs to the technical field of fission product separation, and solves the technical problems that fission product separation cannot be synchronized and nuclear data test precision is low. The separation device comprises a liquid storage tank unit, a color layer separation unit, a waste liquid collector, a product collection unit, a valve and a delivery pump. Liquid in the liquid storage tank unit enters the color layer separation unit through the conveying pump, liquid flowing out of the color layer separation unit enters the product collection unit or the waste liquid collector, and the color layer separation unit is used for fission product separation. The separation method comprises the steps of preparation before separation, zirconium-niobium-molybdenum-antimony-silver adsorption, washing, zirconium separation and purification, molybdenum-niobium separation and purification, antimony separation and purification, silver separation and purification and zirconium-niobium-molybdenum-antimony-silver desorption. The device and the method are used for fission product synchronous separation and nuclear data test and analysis.

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 application discloses a kind of multi-parameter nuclear data adjustment methods of fast reactor, first, for the multiple critical measurement experiments of existing zero-power experimental device, control rod value measurement experiment and cavitation reactivity measurement experiment, the χ coefficient and IS factor of all experiments are calculated respectively, and with a certain experiment as benchmark experiment, the similarity coefficient of all experiments and benchmark experiment is calculated, according to the screening criterion corresponding to similarity coefficient, χ coefficient and IS factor, select the experiment that can be used for nuclear data adjustment, second, using the measurement results of the experiment screened out, including effective neutron multiplication factor, control rod value and cavitation reactivity, based on Bayes theorem, nuclear data is adjusted, finally, three judgment criteria are used to screen the adjusted nuclear data, and the unreasonable nuclear data is discarded or limited range, finally, the adjusted nuclear data is obtained.The more accurate nuclear data is obtained, so as to improve the core physical calculation precision and confidence of fast reactor.

The invention discloses a multi-nuclide neutron nuclear reaction data verification method and device based on deep learning, and the method comprises the steps: determining a to-be-evaluated target nuclide, and obtaining the multi-dimensional physical feature data of the target nuclide from a preset evaluation nuclear database and an experiment database; performing physical perception preprocessing and feature splicing on the multi-dimensional physical feature data to obtain a physical feature vector of the target nuclide; constructing and training a kernel data correction model with uncertainty quantification capability; determining evaluation cross section data and uncertainty data of the target nuclide according to the kernel data correction model and the physical feature vector, and packaging according to the evaluation cross section data and the uncertainty data to obtain evaluation data of the target nuclide; and verifying the evaluation data based on particle transport simulation, and optimizing the evaluation kernel database according to the verified evaluation data. The efficiency and reliability of neutron nuclear reaction data evaluation and verification are improved, and the method can be applied to the technical field of data processing.

The present application relates to a kind of statistical and physical combination (n, alpha) reaction cross section experimental data evaluation method, belong to nuclear data evaluation technical field, the method includes the following steps: investigation and collection existing (n, alpha) reaction cross section experimental data, and collect the relevant information of experimental data, determine the experimental method of experimental data, experimental purpose, detector information, to experimental data is mathematically and physically analyzed, understand the distribution law of experimental data, find implicit variable;According to implicit variable, experimental data is classified and analyzed to obtain experimental data evaluation result;And with the experimental data after evaluation as the basis, obtain recommended excitation function by mathematical fitting etc..The method of the present application starts from two aspects of mathematics and physics, finds the "implicit variable" that influences the accuracy of data in Simpson paradox, from the angle of experimental data evaluation, can effectively avoid the occurrence of PPP problem, effectively improve the accuracy of evaluation data and the efficiency of evaluation work.

A method for calculating multi-group data of nuclear fuel considering resonance upscattering effects includes: 1. For nuclides in the nuclear fuel with resonant scattering cross-sections, a nuclear data processing program generates a resonance upscattering correction factor table for their total cross-section, fission cross-section, and absorption cross-section; 2. A fuel assembly calculation program performs resonance calculations to obtain the average multi-group cross-section of the nuclides, and interpolates the average multi-group cross-section in a traditional multi-group cross-section table that does not consider resonance upscattering to obtain the corresponding dilution cross-section; 3. Using the dilution cross-section, interpolation in the resonance upscattering correction factor table yields a correction factor, which is used to correct the average multi-group cross-section, resulting in a nuclear fuel multi-group cross-section considering resonance upscattering effects. This method solves the problem that fuel assembly calculation programs using ultrafine group methods for resonance calculations cannot consider resonance upscattering effects, providing accurate multi-group data for neutron transport calculations and improving the calculation accuracy of nuclear reactor safety parameters such as the effective multiplication coefficient and fuel temperature coefficient.