17 results about "Beta particle" patented technology

The application discloses a water body radioactivity online monitoring system and a monitoring method, and relates to the technical field of water body radioactivity monitoring. The monitoring system comprises a probe device, a probe driver and signal processing device and a data processing device. The probe device comprises a beta particle detector and a gamma ray detector, and is used for detecting beta particles and gamma rays in a water body and outputting detection signals. The probe driver and signal processing device is electrically connected with the beta particle detector and the gamma ray detector, and is used for receiving the detection signals, processing the detection signals and outputting detection data. The data processing device is electrically connected with the probe driver and signal processing device, and is used for receiving the detection data and analyzing the detection data to obtain a monitoring result. The system provided by the application can realize online real-time monitoring of water body radioactivity, and can realize monitoring of water body nuclide content and identification of nuclides.

Disclosed are compounds represented by the following structural formula (I): or a pharmaceutically acceptable salt thereof. The variables of structural formula (I) are described herein. The compound of the invention can be attached to chelating groups for radionuclide binding and are therefore suitable for radioimaging and / or radiotherapy applications, for example the disclosed compounds can be radiolabeled with a positron emitter such as 18F, 68Ga or 64Cu, and used for positron emission tomography (PET). Alternatively, the compounds can be radiolabeled with an alpha particle emitter such as 223 Ac, a beta particle emitter such as 67Cu or 177Lu, or an Auger electron emitter (e.g. 111In, 67Ga, 99mTc, 195mPt, 125I, 123I and 161Tb) for use as a radiotherapeutic.

The embodiment of the invention relates to a radioactive gas measuring device, comprising: a chamber body, in which a gas chamber for accommodating gas to be measured is formed, and the chamber body is provided with a mounting port communicated with the gas chamber; the detector is arranged at the mounting opening, the detection surface of the detector faces the interior of the air chamber, and the detector blocks the mounting opening to form a sealing boundary of the air chamber; wherein the chamber body or the detector is provided with an air inlet channel and an air outlet channel which are communicated with the air chamber. The PIPS detector directly blocks the mounting port and forms a sealed boundary, so that the direct contact between the detection surface and the detected gas is realized, the attenuation of a window material to alpha particles or low-energy beta particles is eliminated, the measurement sensitivity is improved, and the limitation that the detector in the traditional measurement device needs to be placed in an independent sleeve or measured through a protection window is overcome; meanwhile, the detector serves as the top wall of the cavity body and is matched with the air inlet channel and the air outlet channel which are integrated on the cavity body or the detector, so that the whole device is more compact in structure.

The invention discloses a tritium monitor for realizing alpha, beta and gamma background deduction and a tritium activity concentration detection method.The tritium monitor comprises a detector I, a detector II and a signal processing unit, and the detector I is used for detecting alpha particles, beta particles and gamma particles; wherein the beta particles comprise tritium decay beta particles and high-energy beta particles with energy higher than that of the tritium decay beta particles, and the detector II is used for detecting alpha particles, gamma particles and high-energy beta particles and outputting signals II corresponding to counting rates of the particles. The signal processing unit is electrically connected with the detector I and the detector II, and the signal processing unit is configured to be used for receiving the signal I and the signal II, calculating a background equivalent current jointly generated by the alpha particles, the gamma particles and the high-energy beta particles based on the signal II and a preset calibration coefficient, and calculating the total ionization current based on the difference value of the total ionization current and the background equivalent current. And obtaining a net tritium current, and determining the tritium activity concentration based on the net tritium current.

The embodiment of the present application provides an isotope battery, comprising: a shell; an isotope light source arranged in the shell, the isotope light source is used for radiating photons outward, the isotope light source comprises a radioactive isotope film, wherein the photons are emitted outward from the circumferential side of the isotope light source, and the circumferential side is substantially perpendicular to the radioactive isotope film; and at least one photoelectric conversion device arranged in the shell, the at least one photoelectric conversion device faces the circumferential side of the isotope light source and is used for receiving the photons to convert into electric energy. Since the photons are emitted outward from the side of the isotope light source which is substantially perpendicular to the radioactive isotope film, and meanwhile each photoelectric conversion device faces the side of the radioactive isotope film, on the one hand, the photoelectric conversion device can receive a large number of photons, and on the other hand, the number of beta particles generated by the radioactive isotope decay entering the photoelectric conversion device can be greatly reduced, so that the photoelectric conversion body can be prevented from causing a significant irradiation dose.

The utility model relates to a radionuclide treatment patient urine collection and temporary storage device which comprises a funnel-type collector arranged on a portable pedestal pan, a urine temporary storage tank is arranged below the funnel-type collector, the urine temporary storage tank is composed of an inner barrel body and an outer protective sleeve, a funnel opening in the lower end of the funnel-type collector can be inserted into the inner barrel body, and the outer protective sleeve can be inserted into the funnel opening in the lower end of the funnel-type collector. Urine of a patient subjected to nuclide treatment is collected in the inner barrel body, protection of different radionuclides in the urine is achieved through the outer protection sleeve, the upper face and the lower face of the outer protection sleeve are provided with structures capable of being connected and positioned respectively, and multiple urine temporary storage tanks can be stacked up and down in multiple layers. The temporary storage tank is suitable for temporarily storing treatment nuclides emitting pure beta particles, such as 90Y, or treatment nuclides emitting beta particles accompanied by low-energy gamma rays, such as 177Lu and 161Tb. According to the utility model, a new treatment project can be carried out under the environment-friendly condition for a medical unit for developing radionuclide tumor treatment when the capacity of the decay pool is insufficient or no decay pool exists, so that the number of treated patients is increased.

The invention relates to a real-time monitoring device and method for beta radioactive activity in fluid, and the device is connected with a radioactive waste liquid decay pool through an extraction pump, and is used for extracting the fluid in the radioactive waste liquid decay pool; the solid scintillation cell is installed at the downstream of the draw-off pump, solid scintillation particles are placed in the solid scintillation cell, the solid scintillation cell is a quartz glass cavity, the scintillation particles are of a spherical structure with the particle size of 50-300 micrometers, and beta particles in the fluid emit scintillation light through the solid scintillation particles; the triple photomultiplier is arranged around the side wall of the solid scintillation cell and is used for capturing scintillation light from three directions and converting the scintillation light into three electric signals; and the coincidence counting module is connected with the triple photomultiplier and is used for receiving the three electric signals for coincidence counting and determining the beta radioactivity. The probability of interaction between the beta particles and the scintillation material is improved, synchronous detection of the triple photomultiplier is realized, the detection precision is improved, and online monitoring of the fluidity of fluid is realized.

The invention discloses a leakage self-display all-metal corrugated pipe valve based on beta particle excitation fluorescence, and relates to the technical field of special valves. The valve comprises a valve body, a valve rod, a corrugated pipe, an executing mechanism and a connecting sleeve arranged on the outer side of the corrugated pipe in a sleeving mode. The core improvement is that a window is arranged on the pipe wall of the connecting sleeve, and the inner surface of the window is coated with a fluorescent material layer which can be excited by beta particles released by tritium decay to emit visible light; meanwhile, the sealing surface of the valve rod head at the lower end of the valve rod is coated with a metal coating. According to the invention, on-line and real-time self-display and rapid positioning of trace leakage are realized by utilizing the radioactivity of tritium; by adopting a full 316L austenitic stainless steel main body structure and a valve rod head gold-plated sealing surface, excellent tritium compatibility, embrittlement resistance and high sealing reliability are ensured; the whole structure is compact, an external complex detection module is not needed, and the device is particularly suitable for gas conveying control in tritium-related systems such as controllable nuclear fusion.

The technical scheme of the present application provides a kind of beta radioactive source film and its preparation method and beta radiation isotope battery, first polyimide powder is dissolved in organic solvent, and polyimide solution is obtained;Then, beta radioactive source and dispersing agent are dissolved in polyimide solution, and mixed solution is obtained;Finally, mixed solution is placed into mold, and mixed solution is dried and solidified and demoulded, to obtain beta radioactive source film.Because polyimide will occur imidization reaction in the process of drying and solidification, to form dense network structure, and network structure has high strength and high elasticity, so that beta radioactive source film has self-supporting property and improves the mechanical strength and flexibility of film.Again, because beta radioactive source film has supporting property, therefore beta radioactive source film does not need to be additionally set supporting base, so that beta radioactive source film realizes the double-side emission of beta particle, and further significantly improves the output power and energy conversion efficiency of battery using the beta radioactive source film.

The invention provides a PING monitor prototype radon chamber test method, device and equipment and a storage medium, and aims to solve the technical problem of poor performance evaluation accuracy of a PING monitor prototype. The test method comprises the following steps: extracting gas to be tested; S10, acquiring the activity concentration of radon gas and the equilibrium equivalent concentration of radon daughters in the gas to be tested; a gas detection step S20, detecting to obtain an alpha particle net counting rate and a first beta particle net counting rate; s30, determining a radon daughter response coefficient, and determining a radon daughter response coefficient and compensation coefficient curve; s40, the response coefficient of the radon daughters is compensated, and the response coefficient of the radon daughters after compensation is obtained; a second beta particle net counting rate detection step S50, obtaining a second beta particle net counting rate; a radon gas response coefficient detection step S60, determining a radon gas response coefficient; and a monitor prototype evaluation step S70, evaluating the performance of the monitor prototype according to the compensated radon daughter response coefficient and the radon gas response coefficient.

The invention relates to an intraoperative probe for guiding an excision tool, the intraoperative probe comprising a detection head configured to detect beta particles and / or gamma radiation, the detection head comprising: • a single continuous scintillator (10) able to interact with beta and / or gamma particles and to emit, in response to the interaction, scintillation photons; • a plurality of photodetectors (30), and wherein the intraoperative probe is associated with a signal processing system configured to analyze the signals delivered by the photodetectors (30), the signal processing system comprising: • means for time-coincidence analysis of the signals delivered by a plurality of photodetectors (30), in order to discriminate actual interaction events from thermal noise of the photodetectors; • processing means configured to reconstruct an interaction position of the particles in the continuous scintillator (10) from the relative spatial distribution of the light signals detected by the plurality of photodetectors (30).

The present disclosure belongs to the technical field of nuclear medicine, and provides a dose calculation method for radiopharmaceuticals. The method adopts organ-cell geometric mapping and S-value index to accurately calculate the self-dose of alpha particles and the cross-fire dose of gamma rays / beta particles; based on the LQ model, dynamic RBE and hypoxic OER correction are realized, and the dose results directly usable in clinics are output, which greatly improves the dose calculation accuracy and efficiency of targeted alpha therapy.

A method filters noise from measured data obtained by a muon detector. The method comprises: obtaining a measured distribution of path-length-adjusted energy data for a plurality of detection events associated with the measured data: providing a first baseline distribution of deposition energy per unit path length obtained from a first baseline environment with a high concentration of muon particles relative to beta particles; providing a second baseline distribution of deposition energy per path length obtained from a second baseline environment with a high concentration of beta particles relative to muon particles; fitting the measured distribution to the first and second baseline distributions wherein fitting the measured distribution to the first and second baseline distributions comprises determining a plurality of distribution fitting parameters; and filtering the measured data obtained by the detector based at least on the determined distribution fitting parameters to thereby obtain noise-filtered measured data.

The utility model relates to the technical field of nuclear radiation monitoring, and provides a probe module based on PIPS low background alpha and beta counters, which comprises a probe shell, a probe shell cover, a probe ring, a PIPS detector, a preamplifier and the like. The probe shell and the cover form a copper box shielding body, the probe ring is arranged at the bottom of the shell, the PIPS detector is fixed on the probe ring through the probe pressing plate and the combined screw, and the preamplifier and the PIPS detector are integrated in the copper box shielding body so as to shorten the transmission distance. The probe ring is designed in a detachable mode and is suitable for different types of PIPS detectors. One end of the probe shell is provided with a captive screw, an aviation circular connector and a BNC coaxial connector which are respectively used for supplying power to the preamplifier and outputting signals. The module also includes a signal acquisition and processing system for receiving, processing the signal and determining a total count or activity of alpha and beta particles in the sample. The utility model also provides a low background alpha and beta counter using the probe module.

The application provides a CZT radiation detection device based on a three-dimensional electrode and a particle discrimination method, aiming at discriminating alpha, beta and gamma from the source. The CZT radiation detection device adopts a cathode as a radiation incident window, and shallow layer induction electrodes and deep layer collection electrodes are arranged on the side of the crystal, and an anode is arranged on the surface opposite to the cathode, thereby forming a three-dimensional electrode system. The application utilizes the essential difference in the action depth of alpha, beta and gamma rays in the CZT crystal, and the unique'strong / weak' combination characteristics of the electrode signals, and realizes high-fidelity discrimination of alpha, beta and gamma in the mixed radiation field through the signal distribution characteristics that alpha particles generate strong signals in the shallow layer induction electrodes, the energy deposition depth of beta particles in the CZT crystal has low dispersion, and the energy deposition depth of gamma rays in the CZT crystal has high dispersion.

Disclosed is a compound represented by the following structural formula (I): or a pharmaceutically acceptable salt thereof. The variables of structural formula (I) are described herein. The compound of the inventon can be attached to chelating groups for radionuclide binding and are therefore suitable for radioimaging and / or radiotherapy applications, for example the disclosed compounds can be radiolabeled with a positron emitter such as 18P, 68Ga or MCu, and used for positron emission tomography (PET). Alternatively, the compounds can be radiolabeled with an alpha particle emitter such as 225 Ac, a beta particle emitter such as 67Cu or 177Lu, or an Auger electron emitter (e.g. niIn, 67Ga, "mTc, 195mPt, 125I and 1231). The compounds can also be attached to a cytotoxic agent for targeted delivery of the cytotoxic agent to tumors, for example conjugated to gemcitabine or doxycycline, or a venom. Likewise, the compounds can be conjugated to compounds having physiological effects, such as TLR agonists to stimulate the immune response of a recipient.

The invention relates to an automatic measuring device for activity of medical radioactive waste water, a filter is installed at the downstream of a medical radioactive waste liquid decay pool, a draw-off pump is installed between the filter and the medical radioactive waste liquid decay pool, and a negative pressure degassing piece is installed on the filter and used for discharging gas in the filter; the plastic scintillation pool is installed at the downstream of the filter, the plastic scintillation pool is completely filled with plastic scintillation balls and used for exciting scintillation light of decay particles in the medical radioactive waste water, the plastic scintillation pool is communicated with the medical radioactive waste liquid decay pool, and the medical radioactive waste water passing through the plastic scintillation pool flows back to the waste liquid decay pool; the detector is mounted on the outer edge of the plastic scintillation cell and is used for acquiring scintillation light of decay particles in the medical radioactive wastewater and generating a pulse signal. The technical effects of increasing the contact area of the beta particles and the scintillator, enhancing the detection signal and improving the detection efficiency are effectively achieved, and the effects of improving the automation degree and reducing the labor cost are further achieved.