22 results about "Neutron activation" patented technology

The invention provides a neutron dose evaluation method and system based on mobile phone neutron activation product analysis, and the method comprises the steps: constructing an equivalent medium model for replacing a real mobile phone, and carrying out the neutron energy spectrum solving through the mobile phone activation product. The neutron energy spectrum can be reconstructed on site in daily scenes without professional equipment, such as villages, streets and shopping malls, so that the uncertainty of individual dose is reduced to a level equivalent to that of a laboratory spectrometer, the dependence on a multi-ball spectrometer, a TOF spectrometer and professionals is thoroughly eliminated, rapid and accurate measurement of the neutron energy spectrum and large-scale population dose evaluation are realized, and the accuracy of the neutron energy spectrum is improved. And a basis is provided for delimiting the influence range of the nuclear event, judging the event level of the nuclear event and formulating a hierarchical medical rescue scheme.

The application provides a pulse neutron element scanning and analyzing system for extraterrestrial exploration, which comprises a shell, a support, a neutron generator, a shielding body and a gamma spectrometer, the support is installed in the shell, the neutron generator, the shielding body and the gamma spectrometer are all installed on the support, and the shielding body is located between the neutron generator and the gamma spectrometer. The neutron generator, the shielding body and the gamma spectrometer are integrally installed on the support, the controllable neutron source is combined with the gamma spectrometer, the stratum is activated by the controllable pulse neutron generator, the element components are detected by gamma analysis, or the gamma generated by the natural radioactive nuclides and the cosmic background radiation is directly detected, element component analysis is carried out, the element measurement precision is improved, the detection time is shortened, more kinds of elements can be measured, and the application provides strong support for the measurement of more kinds of elements, and is suitable for lunar geology and resource exploration.

The invention discloses a neutron activation detection station system for rapidly detecting the element content of a material. The system can be used for rapidly detecting the element content of solid bulk materials in industrial production processes of building materials, coal, metallurgy, mines and the like. The system is composed of an element analyzer, a mechanical arm, a weighing scale, a coding sample barrel, a coding card reader, an electric roller conveyor and a PLC control system. The measurement time of a single sample is 30-300 seconds, the weight of the single sample is 1-10 kg, and a plurality of samples can be continuously and automatically measured. The method expands the application process points of the neutron activation technology, breaks through the traditional material detection mode, and has the advantages of wide application range, convenience in operation, high measurement precision, effective improvement of the detection efficiency and the like.

The application provides a direct-current high-voltage pulse strong-current pulse neutron generator, and relates to the technical field of neutron generators, comprising a main arc power module (3), a high-voltage accelerating power module (9) and a neutron tube (12). The neutron generator of the application is a strong-current pulse neutron generator working and driven in a direct-current high-voltage accelerating and pulse mode, can realize adjustable pulse parameters, is simpler to realize, widens the neutron pulse width from sub-microsecond to several milliseconds, and is helpful to widen the application field of the strong-current pulse neutron generator. For example, the ms-level strong-current pulse neutron source can be applied to the mass flow rate and component measurement based on neutron activation.

The utility model relates to the technical field of radiation detection, in particular to a shielding structure and a neutron activation analyser, the shielding structure comprises an outer shell and a partition plate, a hollow cavity is formed in the outer shell, the partition plate is arranged in the hollow cavity to divide the hollow cavity into two shielding cavities arranged along the length direction of the outer shell, and the shielding cavities are arranged in the outer shell. Each shielding cavity is filled with the shielding filler, the hollow cavity is divided into the two independent small shielding cavities through the partition plate, and by means of the arrangement, when the shielding structure is subjected to external physical interference, offset of the shielding filler is limited in each independent shielding cavity through the physical blocking effect of the partition plate; and the filler void ratio of the shielding filler of each shielding cavity only slightly fluctuates without obvious difference, so that the shielding effectiveness of the shielding structure is improved.

This invention discloses a gas purification device for neutron-activated argon isotope dating based on a D-D accelerator, belonging to the field of rare gas isotope mass spectrometry analysis and geological dating technology. Addressing the limitations of traditional gas purification systems, which suffer from large internal volumes and high static release rates, making them unsuitable for the efficient purification and enrichment of trace argon isotopes generated by the D-D accelerator neutron activation method, this invention employs an integrated 316L stainless steel substrate, internally integrating a main gas flow channel and multiple branch channels. The substrate houses a sample gas injection module, a primary purification module, a secondary purification module, a tertiary purification module, a vacuum preparation and monitoring module, a standard gas injection module, and a gas enrichment module. Each module is connected to the main gas flow channel via branch channels, achieving multi-stage purification of the mixed gas and low-temperature enrichment of trace argon isotopes. This device is used for gas purification in D-D accelerator neutron-activated argon isotope dating, meeting the requirements for efficient purification and enrichment of extremely small amounts of argon gas.

The present invention discloses an encrypted ray detection system based on a new mean hash identification algorithm, comprising a neutron activation encryption analysis component and an encrypted mean hash identification algorithm module. The neutron activation encryption analysis component comprises a neutron source, a non-uniform mask, and a detector. The non-uniform mask is disposed to the right of the neutron source, and the detector is disposed to the right of the non-uniform mask. Compared with traditional ray detection methods, the technology proposed in the present invention achieves dual encryption of sensitive information in both the physical and electronic fields. While protecting the sensitive information of the tested items, it also achieves high-precision identification. This technology has great application prospects in nuclear disarmament verification, border nuclear material security inspections, and various scenarios where sensitive information needs to be encrypted for detection. This invention effectively overcomes the difficulties in encrypted ray detection for certain special projects and greatly improves the application capabilities of ray detection technology.

The present application relates to the technical field of nuclear power plant radiation protection, and discloses a kind of space dose rate radiation protection method based on irradiation supervision sample item calculation, comprising: step 1: the source item analysis is carried out to the supervision sample and scrap taken out, obtain the different nuclide species, quantity produced in unit volume of target material due to neutron activation at irradiation stop moment, step 2: the activity of different radioisotopes produced in unit volume and unit mass of target material due to activation at different irradiation time stop irradiation is calculated, step 3: a Monte Carlo calculation model is established, and the space dose rate caused by unit mass of supervision sample under different scenarios is carried out, step 4: the dose rate distribution of supervision sample is calculated, step 5: according to the dose rate distribution of supervision sample calculated in step 4, the kind and thickness of radiation protection material in different scenarios and positions are arranged, combined with the dose rate requirement of place, and reasonable radiation protection measures are formulated, and the present application can assist in reducing the dose of personnel during the overhaul of power station.

A kind of miniature neutron detector conical surface light-concentrating heat-resistant probe, its characteristics include luminous body, light-concentrating cylinder, light-concentrating lens, armored shell, fixing sleeve, compression spring, set screw and optical fiber;Flasher material is made into cylindrical luminous body by using capillary glass tube, the volume of flasher material increases, the neutron activation reaction of flasher material is more sensitive, the light-emitting surface area increases, effectively improve the number of photons generated by flasher material, then light emitted by luminous body is collected, refracted and converged by light-concentrating cylinder and light-concentrating lens, compared with traditional detector probe, effectively reduce the light attenuation of light signal in the process of optical fiber transmission due to random angle incidence, different energy level photon distribution is more uniform and concentrated, the signal strength after conversion is strong, signal pulse accumulation is less, it is easier to be read, greatly improve the detection efficiency of detector, have good enlightenment effect on the technical problems faced by the field, have good popularization and application value.

The invention discloses a neutron activation detection station for rapidly detecting the element content of a material. The equipment can be used for rapidly detecting the element content of solid bulk materials in industrial production processes of building materials, coal, metallurgy, mines and the like. The equipment consists of an element analyzer, a mechanical arm, a weighing scale, a coding sample barrel, a coding card reader, an electric roller conveyor and a PLC (Programmable Logic Controller) control system. The measurement time of a single sample is 30-300 seconds, the weight of the single sample is 1-10 kg, and a plurality of samples can be continuously and automatically measured. The method expands the application process points of the neutron activation technology, breaks through the traditional material detection mode, and has the advantages of wide application range, convenience in operation, high measurement precision, effective improvement of the detection efficiency and the like.

The utility model discloses an ore pulp pretreatment device suitable for a neutron activation ore pulp element on-line analysis technology, which is an ancillary facility of a neutron activation ore pulp element on-line analyzer and mainly comprises a pneumatic valve, a blending barrel, a stirrer, a circulating pump, a concentration meter and the like, the device described by the utility model is combined with a neutron activation ore pulp element on-line analyzer to realize automatic switching detection of ore pulp in two flow channels; the device can be used for adjusting the concentration of the ore pulp, the ore pulp with large concentration difference is adjusted to the same concentration, and the detection error of the neutron activated ore pulp on-line element analyzer caused by the difference of the concentration of the ore pulp is eliminated.

A first aspect of the invention relates to a system for the in-line preparation of a vitrifiable mixture having a target composition, the system comprising: - a unit for dispensing raw materials, which is able to provide a premix comprising cullet, preferably at least 20% by weight of cullet; - a conveyor which is able to move the premix; - a unit for the in-line measurement of the composition of the premix by neutron activation, the in-line measurement unit comprising: • at least one neutron emission source configured to irradiate all or part of said premix; • at least one gamma ray detector configured to detect the gamma rays emitted by the premix when it is irradiated by the neutron emission source; and • a digital processing device configured to calculate, from the signal of the gamma ray detector, the content of chemical elements present in the premix, and optionally configured to estimate the water content and / or the content of organic compounds in the premix; and - at least one means for adjusting the premix to obtain the vitrifiable mixture having the target composition. The invention also relates to a method for the in-line preparation of a vitrifiable mixture having a target composition.

According to a first aspect, the invention relates to an online preparation system for a vitrifiable mixture of target composition, the system comprising: - a raw material distribution unit capable of supplying a premix comprising cullet, preferably at least 20% by mass of cullet; - a conveyor capable of moving the premix; - an online measurement unit for the composition of the premix by neutron activation, the online measurement unit comprising: • at least one neutron emission source configured to irradiate all or part of said premix; • at least one gamma ray detector configured to detect the gamma rays emitted by the premix when it is irradiated by the neutron emission source;and • a digital processing device configured to calculate, from the gamma ray detector signal, the chemical element content present in the premix, and optionally configured to estimate the water content and / or the organic compound content in the premix; and at least one means for adjusting the premix to obtain the vitrifiable mixture of target composition. The invention also relates to a method for preparing a vitrifiable mixture of target composition online. Figure 1.

The invention discloses a corrosion product source item deposition characteristic on-line monitoring device and method based on neutron source activation. The corrosion product source item deposition characteristic on-line monitoring device comprises a water storage tank, a corrosion sample activation test section, a simulation reactor core test section, a main pipeline heat pipe section simulation body, a steam generator simulation body and a main pipeline cold pipe section simulation body. A neutron source is arranged in the corrosion sample activation test section and is used for performing irradiation activation on a corrosion product in a test solution; and gamma-ray energy disperse spectrums D1, D2, D3 and D4 are respectively arranged beside the simulation reactor core test section, the main pipeline heat pipe section simulation body, the steam generator simulation body and the main pipeline cold pipe section simulation body. According to the method, deposition behaviors of corrosion products in a pressurized water reactor primary loop coolant after being activated by neutrons on the surfaces of a fuel element, a steam generator heat transfer pipe and a main pipeline are simulated in a laboratory environment, and deposition radioactive characteristics of the corrosion products on the surfaces of all parts after a neutron source is activated are detected on line through a gamma energy disperse spectroscopy; and online measurement of source item deposition characteristics of surface corrosion products of different parts is realized.

The application relates to the technical field of gamma spectrum analysis, and particularly provides a gamma detector activation analysis method and a PGNAA detection system, which aims to solve the technical problem that the gamma rays obtained by detecting the existing gamma detector include rays generated by the activation and decay of crystals in a neutron field, thereby causing the component detection result of a to-be-detected sample to be inaccurate. For this purpose, the gamma detector activation analysis method comprises the following steps: irradiating a to-be-detected sample by using a neutron source; repeatedly collecting multiple groups of gamma spectra of the to-be-detected sample by using a gamma detector; constructing a spectrum signal matrix based on the gamma spectra of the to-be-detected sample, wherein the spectrum signal matrix is a mixed signal composed of prompt gamma rays generated by the neutron activation of the to-be-detected sample, environmental background gamma rays and interference signals generated by the activation of crystals in the gamma detector; and obtaining effective prompt gamma rays based on the spectrum signal matrix. The self-interference influence of the detector is effectively reduced, and the evaluation precision of the target element content of the to-be-detected sample is improved.

A neutron activator for neutron activation of a material, the neutron activator being configured to produce neutrons by interaction with a proton beam (7), the neutron activator comprising: - a neutron source comprising a metal target (1), and - a beryllium first reflector-slower (4) located at the periphery of the neutron source and comprising a neutron activation zone (10) configured to house the neutron source and the material to be activated, the neutron activation zone (10) of the first reflector-slower (4) comprising an aperture configured to house the neutron source.

The present application provides a neutron dose measurement method in one aspect, comprising: determining a to-be-corrected unit corresponding to a dose monitoring system; determining a first correction factor based on the number of rays emitted after neutron activation of a to-be-activated non-metal unit and the to-be-corrected unit corresponding to the dose monitoring system; and correcting the dose monitoring system based on the first correction factor, thereby determining the real-time neutron dose of a patient. The present application corrects the sensitivity of the dose monitoring system by determining the first correction factor, thereby determining the real-time neutron dose of the patient, avoiding measurement errors caused by the reduced sensitivity or position change of the dose monitoring system, and improving the accuracy and reliability of the measurement results. The present application provides a neutron dose measurement device corresponding to the method.

The present application relates to the technical field of neutron activation and discloses a power supply based on neutron activation and a preparation method thereof, the power supply comprising a to-be-activated radioactive source layer and a transduction layer, the to-be-activated radioactive source layer having to-be-activated particles capable of being activated into radioactive particles by neutrons, and the transduction layer being arranged on the to-be-activated radioactive source layer in the thickness direction of the to-be-activated radioactive source layer. The power supply can overcome the technical problem of how to avoid radiation hazards in the process of preparing the power supply, a non-radioactive (non-source) power supply is prepared first, and then activated into a source battery through neutron irradiation, so that the risk of radioactive substances can be avoided.

This invention relates to the field of transient gamma neutron activation analysis and non-destructive testing technology for industrial materials, and particularly to a multi-element gamma spectral quantitative inversion algorithm based on polynomial forward modeling and Newton's iteration. The technical solution includes the following steps: acquiring the gamma spectrum obtained from neutron activation measurement, extracting gamma detection feature values ​​corresponding one-to-one with each element; establishing a primary polynomial forward model based on the primary gamma detection feature values ​​and the true mass fraction of the corresponding element; and establishing a primary direct polynomial inverse model based on the gamma detection feature values ​​and the true mass fraction of the element. This invention effectively improves the accuracy of multi-element gamma spectral quantitative inversion, enhances the robustness and convergence stability of the algorithm under complex materials, improves the model's generalization ability to different matrix environments, and possesses good engineering practicality.

The invention discloses a corrosion product release rate on-line monitoring device and method based on neutron source activation. The corrosion product release rate on-line monitoring device comprises a water storage tank, a corrosion sample activation test section, nuclear-grade hydrogen type cationic resin and a gamma energy disperse spectroscopy, the water storage tank is used for storing a test solution and introducing the test solution into the corrosion sample activation test section; a corrosion sample and a neutron source are arranged in the corrosion sample activation test section; the nuclear-grade hydrogen type cationic resin is used for trapping an activated corrosion product released into the test solution by the corrosion sample; and the gamma energy disperse spectroscopy is used for measuring gamma ray characteristics of the activated corrosion product. According to the invention, the release behavior of the corrosion product after the pressurized water reactor primary circuit structure material is activated by neutrons is simulated in a laboratory environment, and the radioactive characteristics of the activated corrosion product released in a test solution by a corrosion sample activated by a neutron source are detected on line through a gamma energy disperse spectroscopy, so that the on-line measurement of the release rate of the corrosion product is realized; the method can be used for continuous and online acquisition of corrosion product release rate data under the shutdown condition and the variable power operation condition.

Method for analyzing a specimen by neutron activation. This method comprises: - activating (110) several samples of the specimen using, for each sample, a traversed thickness of moderator material different from the traversed thickness used to activate the other samples, and - for each activated sample, establishing (132) a Ni(R) concentration of a radioisotope of the component sought in that activated sample using only the ionizing radiation measured from that sample, where the exponent i is an identifier of the traversed thickness used to activate that sample and R is an identifier of the radioisotope of the component sought.then - the determination (134) of an Nc(C) concentration of the target component in the specimen from the various established Ni(R) concentrations and predetermined fluences of thermal neutrons and fast neutrons for each of the thicknesses of the moderator material used to activate the samples. Fig. 4,

The present application relates to the technical field of prompt gamma neutron activation analysis and non-destructive testing of industrial materials, and particularly relates to a multi-element gamma spectrum quantitative inversion algorithm based on polynomial forward and Newton iteration. The technical scheme comprises the following steps: obtaining a gamma spectrum obtained by neutron activation measurement, and extracting a plurality of gamma detection characteristic values corresponding to a plurality of elements; based on the plurality of gamma detection characteristic values and the true mass fraction of the corresponding sample elements, a polynomial forward model is established, and based on the gamma detection characteristic values and the true mass fraction of the elements, a direct polynomial inverse model is established. The present application effectively improves the accuracy of multi-element gamma spectrum quantitative inversion, enhances the robustness and convergence stability of the algorithm under complex materials, improves the generalization ability of the model to different matrix environments, and has good engineering practicability.