8 results about "Sub critical" patented technology

A method for controlling a robotic apparatus. The method includes ascertaining a domain of observations made during subcritical events, from observations of controls from a control data database; ascertaining a criterion using which a limitation of the probability of occurrence of a critical event can be inferred from a limitation of the probability of occurrence of a subcritical event; ascertaining further observations when controlling the robotic apparatus, and ascertaining a relative frequency of those of the further observations that are in the ascertained domain; checking whether the ascertained relative frequency corresponds to a probability of occurrence of a subcritical event that is limited in such a way that a limitation of the probability of occurrence of a critical event can be inferred therefrom according to the criterion; and triggering a safety measure in response to the ascertained frequency not corresponding to a probability of occurrence of the subcritical event.

The embodiment of the invention relates to the field of data processing methods particularly suitable for matrix or vector calculation of specific functions, in particular to a method for determining a subcritical limit value of a target nuclear fuel cycle process scene. According to the method for determining the subcritical limit value of the target nuclear fuel cycle process scene provided by the embodiment of the invention, the reference experiment is screened according to the target nuclear fuel cycle process scene, so that the selected reference experiment data meeting the predetermined requirements are obtained, and the quality of the reference experiment data for verification is improved; correcting kernel data adopted by theoretical calculation of the selected reference experiment, so that the theoretical calculation is closer to a real physical scene; according to the corrected nuclear data, the offset and uncertainty of the calculation tool are determined, the uncertainty level caused by the calculation tool is reduced, unnecessary conservative assumptions are reduced, under the same safety level, the limiting conditions of the nuclear fuel circulation process are reduced, and the processing capacity of nuclear materials in nuclear fuel circulation process equipment is improved.

The invention discloses a frequency domain neutron noise problem subcritical degree diagnosis and parameter selection method, and belongs to the nuclear reactor physics field, and the method comprises the following steps: 1, modeling: based on reactor parameters, inputting reactor core geometry, cross section, material and kinetic parameters, a phase shift method and a pseudo-section method (different hyper-parameters) are adopted to construct neutron noise characteristic value problem physical models of different frequencies; 2, calculation: scanning calculation is carried out under different methods and frequencies, and the subcriticality set by different calculations under different frequencies is calculated through a power iteration method; 3, judging: sequentially judging subcritical states / supercritical states at different frequencies according to criticality, excluding supercritical calculation settings, and preferentially selecting the calculation settings with lower subcriticality; and 4, application: performing normal noise calculation by using the optimized calculation setting. According to the method, method selection and parameter optimization basis are provided for neutron noise calculation in different frequency ranges, the calculation power consumption of a reactor core noise analysis database is greatly reduced, and reactor safety diagnosis and operation state monitoring are supported.

The application provides a method and a device for monitoring subcriticality in a reactor physics startup process, which can be applied to the field of reactor physics technology. The method comprises the following steps: obtaining neutron count change data of a reactor in a physics startup process; processing the neutron count change data based on an inverse kinetics method to obtain a first criticality; processing the neutron count change data based on an extrapolation method to obtain a second criticality; and determining the subcriticality of the reactor according to the first criticality and the second criticality. Embodiments of the application can calculate the subcriticality of the reactor in the physics startup process by combining the inverse kinetics method and the extrapolation method through neutron count change data. By combining the inverse kinetics method and the extrapolation method, the subcriticality of the reactor can be more accurately measured.

The embodiment of the invention relates to the field of nuclear reactors, in particular to a method for determining a subcritical limit value of a target nuclear fuel cycle process scene. According to the method, kernel data is adopted to correct a selected reference experiment, so that the uncertainty of kernel data introduction is reduced; different subcritical limit values are respectively determined according to the corrected nuclear data, and the subcritical limit value of the target nuclear fuel cycle process scene is determined in combination with the different subcritical limit values, so that the correlation degree between the selected reference experiment and the target nuclear fuel cycle process scene is enhanced, and the uncertainty introduced by extrapolation of the selected reference experiment data is reduced. By combining the two technical means, the uncertainty generated by factors such as calculation, experiments and extrapolation considered in the operation process of the nuclear fuel circulation process is reduced, unnecessary conservative assumptions are reduced, under the same safety level, the limiting conditions of the nuclear fuel circulation process are reduced, and the safety of the nuclear fuel circulation process is improved. And the processing capacity of nuclear materials in nuclear fuel circulation process equipment is improved.

The present application belongs to the technical field of nuclear power plant core physics test, and particularly relates to a reactivity measurement method based on subcritical physics test. The method comprises the following steps: S10, critical physics test; S20, numerical simulation test; S30, data analysis and processing. The beneficial effect is that the critical state point obtained in the critical process is used to correct the model error in the core numerical simulation, the spatial correction factor, the 1 / M reactivity calibration curve are generated through the numerical model, the model error of each core state point is eliminated through the boron value equivalent method, and the experimental data are processed through the iteration method, so that the control rod value, the boron differential value or the moderator isothermal temperature coefficient and the like can be calculated from the obtained data, the physics test time can be shortened by about 8 hours, and the power generation efficiency of the unit is improved.

The present application belongs to the technical field of nuclear power plant core physics test, and particularly relates to a reactivity measurement method based on subcritical physics test. The method comprises the following steps: S10, critical physics test; S20, numerical simulation test; S30, data analysis and processing. The beneficial effect is that the critical state point obtained in the critical process is used to correct the model error in the core numerical simulation, the spatial correction factor, the 1 / M reactivity calibration curve are generated through the numerical model, the model error of each core state point is eliminated through the boron value equivalent method, and the experimental data are processed through the iteration method, so that the control rod value, the boron differential value or the moderator isothermal temperature coefficient and the like can be calculated from the obtained data, the physics test time can be shortened by about 8 hours, and the power generation efficiency of the unit is improved.