38 results about "Dose conversion" patented technology

The invention belongs to the field of radiation measurement, and particularly relates to a plastic scintillator doped with the neutron-sensitive material lithium and a method thereof for measuring thermal neutrons. According to the invention, lithium-contained raw materials are added into the plastic scintillator. The lithium-doped plastic scintillator and a photomultiplier tube are connected and are sealed inside an opaque housing so as to form a probe. The probe is placed in a measurement environment and the nuclear reaction occurs between incident neutrons and the lithium-contained raw materials in the plastic scintillator, so that the materials are in an excited state. During de-excitation, photons are sent out. The number of photons is proportional to the number of incident neutrons. Meanwhile, through recording the electrical impulses semaphore of the photomultiplier tube per unit time, the neutron fluence can be calculated, so that the measurement of the neutron fluence is realized. The neutron fluence is multiplied by a fluence-dose conversion coefficient to obtain the neutron dose equivalent. The plastic scintillator and the method are low in cost, wide in application range and high in detection efficiency.

A remmeter includes two or more different-sized hydrogenous moderators, each incorporating a hydrogenous spectroscopic fast neutron detector and a thermal neutron detector to provide more accurate neutron dosimetry across a wide range of neutron energies (thermal neutrons to >15 MeV) in a form factor that is lighter than conventional remmeters. The remmeter utilizes the principle of spectral dosimetry, where the energy or energy distribution of the incident neutrons is first measured and then this energy information (along with the measured fluence) is used to establish the dosimetric quantity using the various fluence-to-dose conversion curves (e.g. H*(10) (ICRP(1997)), NCRP-38(1971)). Using the method of spectral dosimetry, the large variation in response in these curves as a function of neutron energy (especially over the region 1 keV to 1 MeV) is largely mitigated through the use of the energy and fluence information, and the appropriate fluence-to-dose conversion curve to calculate the dose.

The invention relates to a method for calculating the short-half-life daughter nucleus bank deposit external irradiation dose of long-lived radioactive nuclide. The method includes the steps of judging a balance relationship built by a mother nucleus and a daughter nucleus according to an emission source item of a liquid effluent of a nuclear facility, determining a radioactivity factor A and a decay constant factor lambda of the daughter nucleus on a deposit site and a surface deposit external irradiation dose conversion factor DCF of the daughter nucleus, and calculating the surface bank deposit external irradiation dose of the deposit site. The method can be used for calculation of various kinds of surface deposit external irradiation caused by discharge of the liquid effluent of the nuclear facility, and solves the technical problem in relevant evaluation calculation in the prior art.

The invention relates to the technical field of radiation dose measurement, in particular to an energy spectrum acquisition-based portable radiation dose measuring device, which comprises a CZT detector module, a signal shaping amplifying circuit, a high-speed AD conversion circuit and a digital signal processing module, wherein the CZT detector module is used for converting particle energy information of a to-be-measured radiation field to corresponding electrical signals; the signal shaping amplifying circuit is used for amplifying the amplitude of the electrical signals outputted by the CZTdetector; the high-speed AD conversion circuit is used for continuously sampling pulse signals outputted by the signal shaping amplifying circuit and converting the pulse signals to a digital quantity for being outputted; and the digital signal processing module is used for performing amplitude information extraction and energy spectrum accumulation on the digital signal waveform outputted by thehigh-speed AD conversion circuit, and after energy spectrum accumulation is completed, based on an energy spectrum dose conversion function, the incident particle type and the radiation dose information of the to-be-measured radiation field are calculated and obtained. In comparison with the prior art, the detailed information of the particle type, the energy and the radiation dose of the to-be-measured radiation field can be provided, the circuit structure is simple and reliable, and popularization is convenient.

The invention belongs to the field of risk assessment of radioactive material transportation, and in particular relates to a calculation method for collective dose in radioactive material transportation dispersion accidents. This method fully divides the area of ​​arbitrary shape concerned in the leeward direction in dispersion accidents into at least one regular-shaped sub-area, calculates the average nuclide concentration of each regular-shaped sub-area, and then further calculates the average nuclide concentration of this area, and then According to the parameters such as shielding factor, dose conversion factor, immersion external exposure time, the number of packages released due to damage, the population density of the area and the area of ​​the area, the collective dose of the area is obtained. The area of ​​collective dose considered in this method is arbitrarily shaped, which is closer to the real situation.

The invention relates to a method for calculating the dosage conversion factor of aquatic organisms, comprising the following steps: determining the relationship between the relevant parameters of aquatic organisms and the dosage conversion factor according to the analysis of the dosage conversion factor; using the Monte Carlo method to calculate the relevant parameters under different irradiation conditions The dose conversion factor value below; use the fitting formula to fit the data for the above dose conversion factor value; conduct error analysis on the fitting formula; obtain the aquatic organisms dose conversion factor. By adopting the method of the present invention, the dose conversion factor can be calculated quickly and accurately without considering the type of aquatic organisms, only by considering the size of the organism, the density of the organism, the energy of the incident particles, and the irradiation path; the method does not need to rely on a large number of databases , which is easy to implement.

The invention relates to the field of radiation protection, and provides a method for evaluating the radiation dose of experimental animal organs by external irradiation of particles. The organ dose conversion factor can be obtained by using the digital model of the experimental animal and the simulation calculation of particle transportation, and then measuring the air kerma to determine the radiation dose of the organ. Assessment; solves the difficult problem of direct measurement of organ dose, and achieves the technical effect of improving the convenience and accuracy of organ dose assessment.

The invention belongs to the radiation measurement field and relates to a neutron-sensitive substance plutonium-doped plastic scintillator and a thermal neutron measurement method thereof. According to the neutron-sensitive substance plutonium-doped plastic scintillator and the thermal neutron measurement method thereof of the invention, a plastic scintillator is doped with a plutonium-containing raw material; the plutonium-doped plastic scintillator is connected with a photomultiplier tube, and the plutonium-doped plastic scintillator and the photomultiplier tube are sealed in an opaque shell, so that a probe can be formed; the probe is arranged in a measurement environment; incoming neutrons and the plutonium-containing raw material in the plastic scintillator are subjected to a nuclear reaction, so that the material is in an excited state; after the material is de-excited, photons are released; the number of the photons is proportional to the number of the incoming neutrons; the quantity of the electric pulse signals of the photomultiplier tube in unit time is recorded, so that the fluence of the neutrons can be obtained, and therefore, the measurement of the fluence of the neutrons can be realized; and the fluence of the neutrons is multiplied by a fluence-dose conversion coefficient, so that the equivalence of the dose of the neutrons can be obtained. The neutron-sensitive substance plutonium-doped plastic scintillator of the invention has the advantages of low cost, wide application range and high detection efficiency.

The invention belongs to the radiation measurement field and relates to a neutron-sensitive substance cadmium-doped plastic scintillator and a thermal neutron measurement method thereof. According to the neutron-sensitive substance cadmium-doped plastic scintillator and the thermal neutron measurement method thereof of the invention, a plastic scintillator is doped with a cadmium-containing raw material; the cadmium-doped plastic scintillator is connected with a photomultiplier tube, and the cadmium-doped plastic scintillator and the photomultiplier tube are sealed in an opaque shell, so that a probe can be formed; the probe is arranged in a measurement environment; incoming neutrons and the cadmium-containing raw material in the plastic scintillator are subjected to a nuclear reaction, so that the material is in an excited state; after the material is de-excited, photons are released; the number of the photons is proportional to the number of the incoming neutrons; the quantity of the electric pulse signals of the photomultiplier tube in unit time is recorded, so that the fluence of the neutrons can be obtained, and therefore, the measurement of the fluence of the neutrons can be realized; and the fluence of the neutrons is multiplied by a fluence-dose conversion coefficient, so that the equivalence of the dose of the neutrons can be obtained. The neutron-sensitive substance cadmium-doped plastic scintillator of the invention has the advantages of low cost, wide application range and high detection efficiency.

The invention discloses a method and system for converting multi-mode low-dose CT into high-dose CT based on a GAN, and a medium. The method comprises the steps: inputting low-dose CT in any mode; performing two-dimensional discrete wavelet transform on the low-dose CT to obtain a plurality of decomposition results; and inputting the low-dose CT and a plurality of decomposition results into a trained encoder in the GAN network, encoding, and decoding the encoding result through a decoder in the GAN network to obtain a corresponding high-dose modal image. The method is based on the wide development of GAN in multi-domain conversion and the decomposition capability of traditional wavelet transform, the low-dose CT and the wavelet transform result are inputted into the trained encoder in theGAN network together for encoding, the encoding result is decoded through the decoder in the GAN network to obtain the corresponding high-dose modal image, and low-dose CT image conversion in any modeis conveniently converted to the high-dose CT image.

The invention belongs to the field of medical detection, and particularly relates to a method, device and equipment for calculating average glandular dose of mammary gland. The average glandular doseof the mammary gland is calculated by acquiring a backscatter factor and combining an exposure tube voltage, a current time product, a backscatter factor, a gland compression thickness of a target mammary gland, a source image distance, a mammary gland average dose conversion factor, a mammary gland component correction factor and a filter combination correction factor, so that whether the currentexposure parameter can generate excessive radiation or not can be more accurately evaluated according to the obtained average glandular dose of the mammary gland.