13 results about "Radioactive decay" patented technology

The invention relates to a method for separating heavy metal cations and radionuclides from aqueous solutions. The method according to the invention can be used to separate dissolved and / or suspended naturally occurring ions or radioactive ions produced by radioactive decay, nuclear transformation reactions such as nuclear fission, or, for example, by activation with neutron radiation, from aqueous solutions.

The invention relates to the technical field of science popularization demonstration, in particular to a half-life period demonstration device and a half-life period demonstration method. The device comprises a base body, a plurality of vertically-arranged demonstration cavities are formed in the table top of the base body, magnetic jumping blocks are arranged in the demonstration cavities, the visual states of the top faces and the bottom faces of the magnetic jumping blocks are different, and the magnetic pole directions of the top faces and the bottom faces of the magnetic jumping blocks are opposite; an electromagnet is arranged under each magnetic jumping block, all the electromagnets can be controlled by a controller to switch the magnetic pole direction, and when the controller controls part of the electromagnets to switch the magnetic pole direction, the part of the electromagnets and the bottom faces of the magnetic jumping blocks are magnetically repelled to drive the magnetic jumping blocks to jump and turn over. Therefore, radioactive decay of part of atomic nucleuses in the elements is demonstrated. According to the invention, by combining the action of a mechanical structure, the nuclear decay process and rule can be dynamically and visually displayed, so that the double problems of non-visual teaching and weak science popularization display can be solved.

This invention discloses a nuclear battery based on a three-dimensional through-hole structure and its fabrication method. The nuclear battery includes a three-dimensional through-hole PIN junction semiconductor transducer unit, a radiation source, and an electrode layer. The unit, from top to bottom, consists of a P-type semiconductor layer, an intrinsic semiconductor layer, and an N-type semiconductor layer. The radiation source is filled in the intrinsic semiconductor through-holes, while the P-type and N-type semiconductor through-holes are filled with electrically insulating materials. The method includes: obtaining a PIN structure on a semiconductor substrate; etching a three-dimensional through-hole array; fabricating a metal seed layer at the bottom of the array; filling the N-type semiconductor through-holes with conductive materials; filling the intrinsic semiconductor through-holes with radiation source material; filling the P-type semiconductor through-holes with electrically insulating materials; and converting the conductive materials in the N-type semiconductor through-holes into electrically insulating materials. This invention improves the energy deposition of radioactive decay particles within the intrinsic layer and the conversion efficiency of radioactive decay energy to electrical energy, thus achieving the fabrication of a high-output performance nuclear battery.

A system is provided that utilizes radiation emitted by radioactive technetium produced by the radioactive decay of radioactive molybdenum. [Solution] The system comprises a radioactive molybdenum production unit that produces radioactive molybdenum by irradiating a molybdenum solution with neutrons using a small accelerator neutron source, and a radioactive technetium extraction unit that extracts radioactive technetium, a daughter nuclide produced by radioactive decay of the radioactive molybdenum produced in the radioactive molybdenum production unit. The radioactive technetium extraction unit is integrated with the radioactive molybdenum production unit and applies ultrasonic vibrations to rod-shaped activated carbon immersed in the molybdenum solution containing the radioactive molybdenum and the radioactive technetium, thereby selectively adsorbing the radioactive technetium onto the surface of the activated carbon, thereby extracting the radioactive technetium, which has a short half-life, so that it can be used at the point of use.

The present application relates to a kind of gamma-ray measurement method, to solve the problem of low efficiency or the demand equipment complexity or timeliness and safety is poorer existing gamma spectrum method measurement low-energy characteristic peak, and provide a kind of low-energy gamma-ray spectrum measurement method based on the law of radioactive decay.The present application includes the following steps:1) using three-dimensional position sensitive cadmium zinc telluride detector to carry out gamma-ray detection to radioactive sample;2) according to the anode signal intensity and electron carrier drift time in three-dimensional position sensitive cadmium zinc telluride detector, obtain the three-dimensional coordinates (x, y, z) of the position where gamma-ray and three-dimensional position sensitive cadmium zinc telluride detector interact;3) calculate the attenuation amount ΔR curve of gamma-ray at different depths of three-dimensional position sensitive cadmium zinc telluride detector;4) energy statistics is carried out to the gamma-ray deposited in all depths corresponding to the attenuation amount ΔR less than the set threshold value, and low-energy gamma-ray spectrum is obtained.

Devices for the radiation detection and analysis, in particular to portable alpha particle sensors adapted for the identification and quantification of radioactive decay products—alpha particles including a battery-powered pulse ionization chamber alpha particle sensor comprising at least one electric battery, at least one switch S, a voltage converter DC / DC, a capacitor C, a processor MCU, a current pulse amplifier A, an ionization chamber K with an electrode of zero potential placed therein. The ionization chamber K is designed with the possibility of placing a source of alpha particles in it. Furthermore at least one electric battery is electrically connected to the voltage converter DC / DC by means of a switch S, the operation of which is controllable by the processor MCU. The voltage converter DC / DC is electrically connected to the capacitor C and the ionization chamber K. The electrode of the ionization chamber K is electrically connected to the processor MCU through the current pulse amplifier A. The processor MCU furthermore is adapted to execute the instructions: (i) count electrical pulses N, which coming from the K electrode of the ionization chamber and which are amplified by the amplifier A; (ii) by means of at least one switch S, controllably periodically electrically connect the supply of electric energy from at least one electric battery to the voltage converter DC / DC and further in the circuit; (iii) determine the voltage value on the capacitor C and, upon reaching the previously set maximum value of the voltage, by means of the switch S, electrically disconnect the supply of electric energy from the electric battery to the voltage converter DC / DC and further in the circuit.

The application belongs to the technical field of radiation protection, and particularly relates to a method and device for obtaining radioactive aerosol data in a closed space. The method comprises the following steps: obtaining a pre-established aerosol diffusion model and an aerosol deposition model; the aerosol diffusion model and the aerosol deposition model are obtained according to the properties of radioactive aerosol and the environmental parameters and ventilation system parameters of the closed space, and the radioactive decay, physical deposition and chemical deposition factors of the radioactive aerosol are considered; and the space radioactive aerosol concentration and the ground radioactive aerosol concentration in the closed space are obtained according to the aerosol diffusion model, the aerosol deposition model, the parameters of the closed space and the properties of the radioactive aerosol. The method solves the problem of dependence of radioactive aerosol on sampling measurement, and provides data for on-site radiation protection.

A method for ranking the hazard of radionuclides, which ranks the hazard of radionuclides by calculating the total effective dose produced by different radionuclides within a certain geographical range in the spread of radioactive contamination, and then screens and controls the types and quantities of radionuclides; wherein the calculation of the effective dose comprehensively considers the influence of radioactive decay, radionuclide deposition, air immersion external exposure, ground deposition external exposure, inhalation internal exposure and other factors. The method can realize the rapid ranking of radionuclides, and achieves a good balance between calculation efficiency and accuracy.

The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation.

The invention relates to radiation detection and analysis devices, in particular, to portable alpha particle sensors adapted for the identification and quantification of radioactive decay products - alpha particles. The proposed low-intensity alpha particle detection device ionization chamber with an electric current pulse amplifier contains an electrode placed in the ionization chamber with zero potential and a protective ring placed around the electrode. The electric current pulse amplifier is placed inside the ionization chamber with the possibility of being electrically connected to a power source, as well as with the possibility of being electrically connected to a processor for supplying an amplified electric current pulse to the processor. This design allows avoiding interference caused by an external electric field without additional shielding of the amplifier.

To provide a radiation image photographing device, a program, an information processing device, and a radiation image photographing method capable of identifying a lesioned part during the operation.SOLUTION: In one embodiment, a radiation image photographing device is provided. This radiation image photographing device includes a first detector, a second detector, and an information processing device. The first detector is a portable type and is configured to be able to detect one of a pair of radiations emitted in different directions from a subject by radioactive decay. The second detector is a stationary type and is configured to be able to detect the other of the pair of radiations. The information processing device includes a first detection processing unit and a second detection processing unit. The first detection processing unit is configured to be able to generate first detection information including positional information of an emission source of a radiation on the basis of the detection result from the first detector. The second detection processing unit is configured to be able to generate second detection information including the positional information of the emission source on the basis of the detection result from the first detector and the detection result from the second detector.SELECTED DRAWING: Figure 3

The application discloses an ecological environment pollution risk assessment method and system, comprising the following steps: collecting radioactive monitoring data of a target area and performing pretreatment; constructing a radioactive pollution space-time distribution observation field of the target area and generating a pollution observation field matrix; coupling a nuclide decay process with a diffusion migration process to form a radioactive decay-diffusion coupling evolution model; constructing a pollution digital twin evolution field, simulating and calculating the pollution diffusion state of the target area under a continuous time sequence; constructing a pollution source assumption set and forming a pollution source parameter vector set; iteratively updating and optimizing the pollution source parameter vector set; calculating the radioactive risk value of each spatial unit of the target area, dividing the risk level, and generating an ecological environment pollution risk assessment result. The application realizes radioactive pollution risk assessment by using the decay diffusion coupling and digital twin inversion method, and has the advantages of high accuracy and strong space-time characterization.

This invention relates to a device and method for providing a radiotherapy source that, in addition to supplying alpha rays, also supplies beta rays at a significant level through diffuse alpha radiation therapy (DaRT) in radiotherapy using an implantable radioactive source. [Solution] An interstitial radiation source (21) comprising a base (22) suitable for implantation in a tumor and alpha-emitting atoms (26) attached to the base (22) having a concentration of at least 6 μCi per centimeter length. The alpha-emitting atoms (26) attach to the base with a radioactive decay desorption probability of 30% or less.