11 results about "Nuclear track" patented technology

The invention discloses a colorectal cancer Septin9 gene methylation detection kit based on a graded anchoring probe, and belongs to the technical field of molecular diagnosis. The graded anchoring probe is composed of a specific capture probe (F1), a precise anchoring probe (R1), a synergistic blocking probe (F2 / R2) and a short chain complementary sequence (S1) which are Septin9 methylation specific probes and can be fixed in a conical pore channel of a nuclear track membrane in a graded manner to form a capture-anchoring-blocking functional chain; during application, a general accumulation body is formed by combining with a Septin9 methylation target, a nuclear track membrane pore channel is blocked, current drop is caused, and detection is realized. Through cooperation of the probe, the nuclear track membrane and the electrochemistry, the problems of insufficient sensitivity, poor stability and poor specificity of traditional detection are solved, and the kit is suitable for ultra-early diagnosis of colorectal cancer.

[Problem] To provide a technique capable of visualizing, with high spatial resolution in neutron imaging, the internal structure of an object to be inspected, without performing chemical treatment that is required when a nuclear emulsion is used. [Solution] A neutron position recording device 10 is provided with a conversion film 1 and a fluorescent nuclear track detector 2 in order to generate an image representing the fine structure of an object T to be inspected. When each neutron that has passed through the object T to be inspected is incident, the conversion film 1 converts each neutron into a charged particle. The fluorescent nuclear track detector 2 has a surface 2a facing the conversion film 1, and records, due to the incidence of the charged particle from the conversion film 1, the track of the charged particle corresponding to the position of the neutron.

The utility model discloses a nuclear track membrane assembly splitting device, and relates to the technical field of nuclear track membrane assembly processing, the nuclear track membrane assembly splitting device comprises a bearing disc, a plurality of placing grooves are arranged at the upper end of the bearing disc in a circular array mode, the nuclear track membrane assembly is composed of a nuclear track membrane, an upper clamp and a lower clamp, a top box is arranged above a bottom box, and the top box is arranged above the bottom box. A splitting part, a diaphragm recycling part and a clamp recycling part are sequentially arranged between the bottom box and the top box in the rotating direction of the bearing disc. A plurality of placing grooves are formed in the upper end of a bearing disc in a circular array mode, a splitting part, a diaphragm recycling part and a clamp recycling part are sequentially arranged in the rotating direction of the bearing disc, a lower pressing cover and a jacking column move at the same time through a linkage mechanism, the moving directions are opposite, and a hinge rod drives a jacking rod to move through an installation sliding rod; and during actual machining, feeding, removal of nuclear track membranes, recovery of the nuclear track membranes, and recovery of the upper clamp and the lower clamp can be completed at the same time.

The invention discloses a marine container nuclear track membrane fresh-keeping method which comprises the following steps: S1, respiration characteristic analysis and parameter determination: respiration characteristic parameters of goods to be transported are obtained, and the respiration characteristic parameters at least comprise the respiration rate of the goods under the aerobic condition, the respiration rate of the goods under the anaerobic condition and the ethylene release rate; and determining a target gas regulation and control range and a nuclear track membrane aperture parameter matched with the cargo type based on the breathing characteristic parameter and in combination with a basic fresh-keeping temperature of the cargo. And through the collaborative design of breathing characteristics, aperture parameters and installation layout, the precision of gas regulation and control is realized. The aperture of the nuclear track membrane is customized on the basis of parameters such as the cargo breathing rate and the ethylene release amount, the high selectivity of the monodisperse aperture of the nuclear track membrane is combined, O2 in the container can be stably controlled to be 2%-8%, CO2 can be controlled to be 3%-12%, ethylene is smaller than or equal to 0.1 ppm, the gas fluctuation range of the container is narrowed by 60% compared with that of a traditional controlled atmosphere container, and the breathing effect and the ethylene ripening effect are remarkably reduced.

The utility model discloses a replaceable and detachable nuclear track membrane structure and an atomizer, and relates to the technical field of atomizers, the replaceable and detachable nuclear track membrane structure comprises a liquid bin, a boss is arranged in the middle of the liquid bin, an atomization groove is formed in the middle of the boss, a liquid storage cavity is formed between the liquid bin and the boss, a metal loading plate, an atomization nuclear track membrane and a piezoelectric ceramic ring are arranged in the atomization groove, and micropores are distributed in the center of the atomization nuclear track membrane. The boss is provided with a water drawing mechanism, the piezoelectric ceramic ring is connected with a power source, the atomization groove is provided with a clamping assembly matched with the atomization nuclear track membrane, the clamping assembly comprises a lifting pressing plate which is arranged in the atomization groove and connected with the piezoelectric ceramic ring, and the boss is provided with a displacement mechanism for promoting the lifting pressing plate to move in the vertical direction. A locking mechanism is arranged between the lifting pressing plate and the atomization nuclear track membrane and comprises an arc-shaped protrusion arranged on the atomization nuclear track membrane, and an arc-shaped groove is formed in the corresponding position of the lifting pressing plate. The atomization nuclear track membrane can be replaced conveniently, maintenance of the atomization nuclear track membrane is facilitated, the maintenance cost is low, and daily batch use is facilitated.

The invention discloses a composite nuclear track membrane as well as a preparation method and application thereof. The composite nuclear track membrane comprises a supporting base layer and a two-layer structure membrane formed on the supporting base layer through membrane scraping and finishing, wherein the thickness of the supporting base layer ranges from 50 micrometers to 120 micrometers, the thickness of the two-layer structure membrane ranges from 10 micrometers to 50 micrometers, and the two-layer structure membrane comprises a compact layer and a loose layer; the thickness of the compact layer is 100-200 nm, the aperture of the compact layer is 0-40 nm, the thickness of the loose layer is 10-50 [mu] m, and the aperture of the loose layer is 0.1-10 [mu] m; the composite nuclear track membrane is applied to the biological component separator. The composite nuclear track membrane as well as the preparation method and the application thereof aim at solving the problems of a dialysis membrane used by a biological component separator in the prior art so as to meet the requirement for accurate separation of biological substances in medical and biological experiments, and have important practical significance.

The invention discloses a full-automatic solid nuclear track detector chemical etching system, which relates to the technical field of chemical etching and comprises a clamp, a fuming cupboard, a chemical etching tank, a neutralizing tank, a cleaning tank, a drying assembly, a driving mechanism and a control system. The clamp is used for loading detector elements. The fuming cupboard is used for providing an installation foundation and a ventilation environment. The chemical etching groove is connected with the fuming cupboard and used for containing chemical etching liquid. The neutralizing tank is connected with the fuming cupboard and used for containing neutralizing liquid with the acid-base property opposite to that of the chemical etching liquid. The cleaning tank is connected with the fuming cupboard and used for water washing. The drying assembly is used for providing hot air. The driving mechanism is connected with the clamp and used for moving the clamp. The control system is at least electrically connected with the driving mechanism to control the moving path of the clamp. Compared with the prior art, unattended operation automation of chemical etching can be achieved, manpower consumption is reduced, and etching precision and efficiency are improved.

The utility model discloses a liquid quality adjusting device for a solid nuclear track etching experiment. The liquid quality adjusting device comprises a measuring water tank, a T-shaped fixing frame, a conductivity sensor, a water tank fixing plate, a water replenishing pipe and a water pumping pipe, the measuring water tank is arranged above the middle part of the water tank fixing plate; the water tank fixing plate is mounted at the top end of the etching water tank; the T-shaped fixing frame is connected with the top end of the measuring water tank, and the lower end of the T-shaped fixing frame extends into the measuring water tank; the conductivity sensor is positioned at the lower end in the T-shaped fixing frame; one end of the water replenishing pipe is externally connected with a water source, and the other end extends into the etching water tank; the other end of the water pumping pipe is connected with the measuring water tank; according to the utility model, the etching liquid is pumped into the measuring water tank through the water pumping pipe, the conductivity of the etching liquid is detected through the conductivity sensor in the measuring water tank, and the required water replenishing amount can be accurately calculated by comparing the original conductivity, so that the stability of the concentration of the etching liquid in the etching water tank is ensured, and the overall operation is convenient.

The invention discloses a manufacturing method of a fresh-keeping cabinet composed of a phase-change material and a nuclear track membrane, and the manufacturing method comprises the following steps: S1, preparing a plastic box body with a containing cavity which is used for placing articles to be preserved; s2, an interlayer is arranged in the wall body of the plastic box body or an independent phase change material unit is arranged in the containing cavity, and the containing cavity is filled with a paraffin phase change material; s3, according to the size of the plastic box body, one or more ventilation holes of 5-10 cm are formed in the side wall or the top of the plastic box body; and S4, a layer of nuclear track membrane is attached to each vent hole, and the nuclear track membrane has the preset hole diameter and hole density so as to regulate and control the micro-atmosphere environment. By utilizing the latent heat characteristic of the paraffin phase-change material, the temperature in the fresh-keeping cabinet can be kept relatively stable within a certain period of time without an external power supply, energy consumption is remarkably reduced, and the fresh-keeping cabinet belongs to an environment-friendly technology and is particularly suitable for being used in regions with unstable electric power, outdoor operation, short-distance transportation or occasions without power supplies.

The invention discloses a disposable electrochemical biosensor detection kit, and belongs to the technical field of in-vitro diagnosis. The kit is a disposable in-vitro diagnosis product and is divided into two product systems, namely a molecular detection system and an immunodetection system; the core components of the molecular detection kit are an integrated disposable H-type electrolytic cell, an isothermal amplification buffer solution, a positive control solution, a negative control solution and a blank control solution. The core components of the immunodetection kit are an integrated disposable H-type electrolytic cell, a detection reagent, a substrate reagent, a calibrator I, a calibrator II, a quality control product I and a quality control product II. The kit takes a functionalized nuclear track membrane as a core, the nuclear track membrane modifies corresponding target recognition probes in advance according to different detection targets, and the target recognition probes are pre-sealed and fixed in an H-shaped electrolytic cell to form a non-detachable integrated detection unit with the electrolytic cell; transmembrane transmission of a sample is realized through pressurization of a single inflation port, and high-precision detection can be realized by combining isothermal amplification or a double-antibody sandwich technology and an electrochemical sensing technology.

The invention provides a neutron directional detection device and method based on a solid nuclear track detector, and the device comprises a solid nuclear track detection part which is used for receiving secondary particles generated by the interaction of neutrons and forming observable track signals; the central base is used for reflecting thermal neutron information; and the shell is used for reflecting fast neutron information. The neutron directional detection method comprises the following steps: simulating by using Monte Carlo software to obtain secondary particle information under different incident angles; obtaining a response simulation data set of the neutron directional detection device under the condition of different incident angles by adopting a particle analysis and judgment algorithm; training an artificial neural network model based on the simulation data set; the actual response of the neutron directional detection device is obtained through etching and track reading during measurement; and substituting the actual response of the neutron directional detection device into the artificial neural network model to carry out direction detection. The device has the advantages of light weight, portability, accurate measurement, high detection efficiency, rapidness and simultaneous measurement of the thermal neutron direction.