7 results about "Nucleon" patented technology

The invention discloses a passive nucleon level gage and a level output control method and a monitoring system thereof in a nuclear radiation flaw detection period. The level output method comprises the following steps: judging that nuclear radiation flaw detection interference exists in a measurement environment in which the passive nucleon level gage is positioned; executing at least one of the following output guarantee operations: setting an output switch of the passive nucleon level gage to be in a preset guarantee state, wherein the preset guarantee state is a switch-on state or a switch-off state; or the output switch of the passive nucleon level gage is maintained in the on-off state before it is judged that nuclear radiation flaw detection interference exists; or the normal material level value of the passive nucleon level gauge is replaced with the alternative material level value, or the on-off state of an output switch of the passive nucleon level gauge is determined based on the alternative material level value, and the alternative material level value is used for replacing the normal material level value when flaw detection interference is detected. The normal material level value is a material level value generated on the basis of the real-time measurement data in the state that the guarantee operation is not executed. The device realizes material level output guarantee control during nuclear radiation flaw detection.

The application provides a neutron equivalent modeling method and device for high filling rate dispersion particles, and the method comprises the following steps: calculating the maximum outer radius of the equivalent particles; under the premise of keeping the core diameter of the particles unchanged, calculating the maximum compression ratio of the cladding layer of the particles; according to the set compression ratio, calculating the filling rate of the equivalent fuel element after the size of the cladding layer of the particles is compressed, wherein the set compression ratio is less than or equal to the maximum compression ratio; adjusting the density of the cladding layer material and the density of the matrix material to ensure the conservation of nucleon number of the cladding layer and the matrix material before and after the equivalent; and using a traditional modeling method to perform geometric modeling and neutron calculation on the equivalent fuel element. The application can effectively avoid the filling rate limitation of the random sequence increasing method, meet the modeling demand of random distribution of high filling rate dispersion particles, and realize reactivity equivalence and ensure the neutron calculation accuracy.

The invention discloses a main magnetic field error suppression method of a nuclear magnetic resonance atomic gyroscope, which comprises the following steps: constructing a nuclear magnetic resonance atomic gyroscope inertial measurement system, applying a main magnetic field, a carrier magnetic field and pumping light in a z-axis direction, and applying detection light and a nucleon resonance magnetic field in an x-axis direction, enabling the nuclear magnetic resonance atomic gyroscope inertial measurement system to be in a stable working state; carrying out electron frequency sweeping to obtain electron spin relaxation time; carrying out closed-loop processing on the nucleons, and carrying out precession frequency measurement on the double nucleons; according to the electron spin relaxation time and in combination with the parameters such as the nucleon precession frequency, an optimized carrier signal frequency is calculated through a carrier frequency selection formula provided by the invention; based on the optimized carrier signal frequency, accurate measurement is carried out on the nuclear precession frequency, and angular velocity information is obtained. By selecting the optimal carrier signal frequency, the nuclear precession frequency detection error caused by the main magnetic field fluctuation error is compensated, and the measurement error of the nuclear magnetic resonance atomic gyroscope is reduced.

The application discloses a neutron flux measurement method and device and a neutron flux calibration method and system, and relates to the technical field.The measurement method is applied to a neutron flux measurement system, and the neutron flux measurement system comprises a fuel rod sleeve of a micro reactor core critical device; M grooves are arranged on the fuel rod sleeve, and the grooves are used for accommodating detection activation sheets; M is a positive integer; the method comprises the following steps: acquiring a first correction factor, a first nuclear density, a first detection efficiency and M first information corresponding to the M grooves; and determining M absolute neutron fluxes corresponding to the M grooves according to the first correction factor, the first nuclear density, the first detection efficiency and the M first information.According to the embodiment of the application, the method not only meets the structural requirements of a compact reactor core, but also avoids the disturbance of carriers and supports to the neutron field in the reactor core, and the number of times of starting the reactor can be reduced.

This invention provides a method and system for measuring the activity of low- and intermediate-level radioactive waste bins using gamma scanning based on neural networks, comprising: Step S1: The waste bin is vertically divided into several segments; Step S2: Radioactive point sources within each segment are assumed to be ring-shaped line sources, and all ring sources within the same segment are equivalent to one equivalent ring source relative to the detector; Step S3: A segment is scanned at the same height and three different eccentricity positions using a gamma spectrometer to obtain the corresponding count rates at the three detection positions; Step S4: The equivalent ring source radius and its detection efficiency are calculated using the count rates at the three detection positions combined with a neural network algorithm; Step S5: The nucleon activity of the current segment is calculated based on the equivalent ring source radius and its corresponding detection efficiency; Steps S1 to S5 are repeated to obtain the nucleon activity of each segment; Step S6: The total activity of the waste bin is obtained by summing the nucleon activities of each segment.

The application discloses a passive nuclear material level meter, a material level output control method thereof during nuclear radiation detection, and a monitoring system. The material level output method comprises the following steps: determining whether there is a nuclear radiation detection interference in a measurement environment of the passive nuclear material level meter; and performing at least one of the following output guarantee operations: setting an output switch of the passive nuclear material level meter to a preset guarantee state, wherein the preset guarantee state is an on state or an off state of the switch; or maintaining the output switch of the passive nuclear material level meter in a switch state before the determination that there is the nuclear radiation detection interference; or replacing a normal material level value of the passive nuclear material level meter with a replacement material level value, or determining a switch state of the output switch of the passive nuclear material level meter based on the replacement material level value, wherein the replacement material level value is used to replace the normal material level value when the detection interference is detected, and the normal material level value is a material level value generated based on real-time measurement data in a state without performing the guarantee operation. The application realizes the guarantee control of the material level output during the nuclear radiation detection.

The application discloses a kind of liquid scintillation double-nucleus simultaneous quantitative measurement methods based on mixed spectrum, comprising preparing double-nucleus mixed sample;Establish the spectrum theoretical description model of single nucleon;T pipe, D pipe energy spectrum is solved by using nonlinear fitting method jointly;T pipe and D pipe count value are obtained by being based on the theoretical description model to the T pipe, D pipe energy spectrum and being solved spectrum;The TDCR liquid scintillation system with T, D pipe energy spectrum output function in the application does not need a large number of pre-calibration work and standard quenching series source, does not depend on the accuracy of calibration, compared with function fitting stripping method, T, D spectrum is calculated simultaneously in the process of spectrum analysis, and absolute measurement is realized based on the mutual constraint of parameters.