16 results about "Nucleon" patented technology

The invention provides a relaxation time measuring method and system. The relaxation time measuring method comprises the following steps: heating an atomic gas chamber to be measured to a set working temperature, and applying a static magnetic field in a z direction to the atomic gas chamber to be measured; starting the pumping laser light source and the detection laser light source, and performing light path alignment adjustment; the pumping laser light source is used for polarizing alkali metal atoms in the atomic gas chamber to be measured; determining a relaxation time measurement mode according to a relaxation time measurement requirement, triggering a corresponding operation, and collecting a corresponding relaxation signal; the measurement mode comprises at least one of the following modes: an alkali metal electron spin transverse relaxation mode, an alkali metal electron spin longitudinal relaxation mode, an inert gas nucleon spin transverse relaxation mode and an inert gas nucleon spin longitudinal relaxation mode; and fitting the relaxation signal corresponding to the mode to obtain a corresponding relaxation time value. According to the invention, the transverse and longitudinal relaxation time of alkali metal electrons and the transverse and longitudinal relaxation time of inert gas nucleons can be measured on the same machine.

1. The name of this design product: Lateral detection passive nuclear level meter. 2. Application of this product: It is used to detect the material in the container by using the side of the crystal in the sensor without the need for a radioactive source. 3. The key point of the design of this product lies in its shape. 4. The picture or photo that best illustrates the key points of the design: Design 3 3D diagram. 5. Designate Design 3 as the base design.

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 method for calculating poison nucleon density of external circulation fuel spheres of a pebble-bed high-temperature gas cooled reactor. Firstly, in-pile multi-group neutron flux distribution is obtained; simplifying a burnup chain of the important poison, and establishing and solving a burnup equation of the simplified burnup chain to obtain the equilibrium concentration of batches of all areas of the bottommost layer of the pebble bed at the current stage, which can return to a reactor core, namely the initial fuel ball poison concentration; establishing a burnup equation after the fuel balls are unloaded out of the reactor, and deducing and solving the nuclear density of a batch of poison unloaded from a runner before the poison stays out of the reactor for a period of time and returns to the reactor core; until the variation of the poison nucleon density of each batch of each runner which will return to the reactor core is solved; performing volume weighted averaging on the same batch of poison nucleon densities of different flow channels decayed for a period of time outside the reactor according to the area ratio of the flow channels; and finally obtaining the poison nucleon density of the batch returned to the reactor core after out-of-reactor decay and uniform mixing. According to the method disclosed by the invention, the poison concentration is more reasonable after the fuel balls subjected to out-of-reactor circulation return to the reactor core again.

A reflective single-beam biaxial atomic spin gyroscope. A beam of elliptically polarized light is incident on an atomic gas cell to pump alkali metal atoms and inert gas nucleons to make them reach a polarized state. At the same time, a rotating modulation magnetic field is applied in a direction perpendicular to the pumping direction to modulate the electron polarization vector in the pumping direction and carry rotation information. The pumping light exiting the atomic gas cell is reflected by a mirror, passes through the atomic gas cell again, and finally enters a balanced differential module and realizes the extraction of rotation signals through a phase-locked amplifier signal acquisition module and decouples biaxial inertial signals by adjusting the phase shift of the reference signal. This is beneficial to the development of miniaturized SERF atomic spin gyroscopes, beneficial to enhancing the optical rotation angle signal, improving the signal-to-noise ratio and system sensitivity, and beneficial to improving the practicality of the gyroscope.

The invention discloses a system and method for determining the measuring range or measuring distance of a passive nucleon level gauge and a material level measuring method, and the system is used for determining the measuring range of the passive nucleon level gauge at a fixed position relative to a measured container or the measuring distance of the passive nucleon level gauge to a reference material. The system comprises a passive nucleon level gage, a material type identification correction instrument and a calculation control module, wherein the material type identification correction instrument is configured to detect nuclear radiation characteristic data released by materials in a measured container; the calculation control module calculates a measurement range or a measurement distance according to a preset algorithm in response to the condition that the material nuclear radiation characteristic data output by the material type identification correction instrument meets the condition; or the calculation control module controls the third-party equipment to execute measurement so as to obtain the measurement range or the measurement distance; or the calculation control module determines the measuring range or the measuring distance corresponding to the nuclear radiation characteristic data by inquiring a preset mapping relation.

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.

The invention provides a control method and device for 131I production equipment, and the method comprises the steps: determining a first nuclear number N1 (0) of 130Te in 130TeO2 target at an initial moment according to the enrichment degree of 130Te in the 130TeO2 target under the condition that the 130TeO2 target is irradiated with thermal neutrons with a thermal neutron fluence rate # imgabs0 # in the 131I production equipment, and determining a second nuclear number N1 (0) of 130Te in 1g of 130TeO2 target at an initial moment according to the enrichment degree of 130Te in the 130TeO2 target; and according to # imgabs 1 # and N1 (0), determining the irradiation duration required when the growth rate of the specific activity of the 131I generated in the irradiation process is less than a preset growth rate and the radioactive purity of the 131I reaches a preset purity after the target duration of irradiation ending, performing irradiation control on the 30TeO2 target according to the irradiation duration, and controlling the duration of irradiation ending according to the target duration. By means of the method, the 131I production equipment can obtain the 131I with the radioactive purity reaching the preset purity.

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.

A control rod burnup assessment method for advanced nuclear reactors first divides the control rods in the core into a fine burnup assessment rod group and a direct burnup assessment rod group, and then performs a burnup calculation analysis over the core life. In each burnup step, the average neutron flux density of each segment of the control rod assembly is obtained based on the results of the steady-state neutron transport calculation. Next, for the direct burnup assessment rod group, only the average neutron flux density of each segment is accumulated to calculate the total neutron flux. For the fine burnup assessment rod group, after obtaining the average neutron flux density, the absorber is immediately solved. 10 B's burnup equation, and the calculated control rod 10 The B nucleon density is fed back to the neutron transport calculation of the next burnup step. When all burnup step calculations are completed, the total neutron flux during the lifetime is used to calculate the direct burnup assessment rod group. 10 The burnup equation of B is used to obtain the material composition of this set of control rods after burnup.

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 invention discloses a liquid-flash double-nuclide simultaneous quantitative measurement method based on mixed spectrum unfolding. The method comprises the following steps: preparing a double-nuclide mixed sample; establishing a spectrum theory description model of a single nuclide; jointly solving the energy spectrums of the T tube and the D tube by using a nonlinear fitting method; performing spectrum unfolding on the energy spectrums of the T tube and the D tube based on the theoretical description model to obtain counting values of the T tube and the D tube; through the TDCR liquid flashing system with the T and D tube energy spectrum output function, a large amount of advanced calibration work and standard quenching series sources are not needed, dependence on calibration accuracy is avoided, compared with a function fitting spectrum stripping method, T and D spectrums are calculated at the same time in the spectrum unfolding process, and absolute measurement is achieved based on mutual constraint of parameters.

A method for in-situ magnetic field gradient measurement based on SERF inertial measurement, where SERF (Spin-Exchange-Relaxation-Free) is spin-exchange relaxation free. The total magnetic field gradient in the atomic gas chamber is obtained according to the quadratic relationship between the transverse (longitudinal) relaxation rate of nucleons and the longitudinal (transverse) magnetic field gradient. The polarization rate gradient and the static magnetic field gradient are measured by reversing the pumping light helicity and changing the magnitude of the static current. At the same time, the remanent magnetic gradient can be obtained, which is beneficial to analyzing the source mechanism of the magnetic field gradient, reducing the magnetic field gradient and increasing the transverse relaxation time of nucleons, thereby improving the magnetic noise suppression ability of the SERF inertial measurement system and ultimately improving the inertial measurement accuracy.

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.