7 results about "Radiation hazard" patented technology

The present application relates to a combined inner core for nuclear medicine, comprising inner core assemblies, each of which is provided with at least one aperture of a hot spot hole; the inner core assemblies can be combined at will so that the combined inner core has at least six apertures of hot spot holes. A phantom structure is also provided, comprising a barrel body, the above-mentioned combined inner core and a barrel cover. An automatic bubble-free perfusion method for the phantom structure by means of an automatic perfusion device is also provided. The combined inner core of the present application is flexible to use, and can obtain the required resolution information in a single resolution evaluation. The cumbersome process of replacing the inner core and re-perfusion is avoided. The inner core assemblies of the present application are easy to process, saving production cost and time cost. The perfusion method enables the operator to minimize the risk of possible radiation hazards.

This utility model discloses an automatic drug delivery device, relating to the field of reagent injection technology. The automatic drug delivery device includes: a shielded housing forming a first shielded cavity; and a reagent injection assembly, at least a portion of which is disposed within the first shielded cavity. The reagent injection assembly is adapted to connect to a reagent bottle and an infusion device, serving to connect the reagent bottle and the infusion device, and also driving the reagent within the reagent bottle to flow along the reagent injection assembly. This simplifies the injection process and reduces injection costs. The fact that at least a portion of the reagent injection assembly is disposed within the first shielded cavity provides shielding, thereby reducing the radiation hazards of the reagent within the assembly to staff and patients, and effectively protecting their safety.

The utility model discloses a special tool for the quick cleaning of the top sealing surface of a nuclear power plant annular container, comprising an annular frame, an annular groove is formed in the interior of the annular frame, a rotating gear ring is movably connected in the interior of the annular groove, a rotating drive assembly is installed on the annular frame to drive the movement of the rotating gear ring, a first electric telescopic rod is installed at the bottom end of the rotating gear ring, and a rotating assembly is installed at the telescopic end of the first electric telescopic rod. In the utility model, the special tool can realize remote cleaning, and the cooperation of multiple components maintains a certain working distance from the sealing surface, greatly shortens the irradiation time of personnel, liberates the working personnel from the high radiation environment, effectively reduces the radiation hazard, and guarantees the life and health of the working personnel. The special tool can precisely fit the complex profile of the sealing surface through a precision mechanical structure, and the cleaning efficiency is several times higher than that of manual cleaning.

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 discloses a method for assessing the radiation hazard of a vacuum interrupter based on spectral distortion correction, belonging to the field of high-voltage testing and radiation detection protection technology. It includes the following steps: Step S1, obtaining the geometric parameters of the vacuum interrupter and calculating the spatial reference measured energy spectrum; Step S2, calculating the equivalent penetration thickness factor of X-rays within the main shield of the vacuum interrupter based on the spatial observation angle, and constructing a spatially related shield self-absorption attenuation matrix based on the equivalent penetration thickness factor of X-rays within the main shield of the vacuum interrupter. This invention provides a method for assessing the radiation hazard of a vacuum interrupter based on spectral distortion correction. Through external energy spectrum measurement and spectral reconstruction, and direct table lookup calculation of human tissue doses based on international standard conversion coefficients, it achieves a three-dimensional, accurate, and rapid quantitative assessment of the actual radiation hazard to the human body under specific high-voltage operating conditions.

This invention discloses a plutonium-containing material measuring device, relating to the technical field of radioactive element measuring devices. The device includes a measuring chamber, a lower cover assembly, and an automatic feeding structure. A gamma detector is installed above the measuring chamber, and a neutron detector is installed inside. The automatic feeding structure includes a horizontal transmission mechanism and a synchronous lifting mechanism. The synchronous lifting mechanism is a symmetrical structure driven by a single power source. The lower cover assembly, which carries the material to be measured, is placed on the horizontal transmission mechanism and can be conveyed horizontally to the lifting position. The synchronous lifting mechanism then conveys the lower cover assembly along with the material to be measured vertically into the upper measuring chamber, and the lower cover assembly seals the bottom of the measuring chamber, thus forming a closed measuring space. The device provided by this invention can simultaneously perform neutron and gamma measurements on materials, reducing measurement time, minimizing transport time, reducing radiation hazards to personnel, reducing equipment size, and increasing measurement accuracy.