7 results about "Equivalent dose" patented technology

This invention discloses a method for detecting the toxicity threshold of a substance based on a rat drinking experiment. The method of this invention includes the following steps: First, a drinking preference experiment is conducted, and then the toxicity threshold is determined: the amount of substance water and pure water consumed in the drinking preference is compared to determine the time when the rat begins to significantly avoid substance water, the mass of the toxic substance in the rat's body at that time is calculated, and the toxicity threshold of the rat is calculated; (3) dose conversion from rat to human: based on the interspecies dose conversion of body surface area, the toxicity threshold of the rat is first converted into the equivalent dose for humans to obtain the acute exposure dose, and then the acute exposure dose is converted into the chronic exposure dose for humans to obtain the substance toxicity threshold. This invention can accurately determine the toxicity threshold: it achieves toxicity assessment of low-dose exposure through spontaneous recognition behavior; it is easy to operate; and it is applicable to the toxicity assessment and non-destructive threshold determination of various substances such as environmental pollutants, chemical substances, and drugs.

The invention discloses an energy-saving treatment method for a plasma activated packing rubber sealing element, and relates to the technical field of rubber surface modification, an equipment normalized dose scale is constructed by using an online emission spectrum and a laser-induced breakdown spectroscopy, and an equivalent dose density field and a circumferential surface energy map are established by combining a spin-revolution hit nucleus and a two-liquid contact angle array; cross-device unification and computable closed loop are realized; activation-deposition zero-time-difference non-exposure connection is achieved through an inert air curtain or a closed channel, an inner polar anchoring layer is polymerized in situ, curvature-attitude weight linkage scanning and duty are conducted, and the site density and the film thickness are stabilized; outer layer orientation ordered parameters are constructed in the non-destructive energy window, and in-situ reversible switching and circumferential consistency are achieved according to the coverage degree, overlapping scanning and trench bottom fixed-point compensation; logarithm-soft maximum fusion and an adaptive upper envelope threshold trigger low-energy old removal / redeposition, accumulated dose recursion and SPC recharge to realize online decision and traceability.

Neutron-induced radiation detectors (NiRDs) and radiation dosimetry systems containing the same are described. Examples of NiRDs can include numerous components based on location, function, dimension, and / or constituent materials. A NiRD can be configured to directly measure an absorbed dose (or rate) of particular ionizing reaction products induced by neutrons. The NiRD can utilize various detection schemes for measuring the deposited energy of the reaction products, such as gaseous ionization, semiconducting, scintillating, or homogenous versions of these detection schemes. The NiRD can measure the deposited energy of the reaction products in forward emission, backward emission, or both. Examples of radiation dosimetry systems can include one or more NiRDs, a gamma ray detector, and readout electronics coupled to each of the radiation detectors. Example implementations of the radiation dosimetry systems are described for determining an equivalent dose (or rate) of a neutron beam generated for boron neutron capture therapy (BNCT).

The application provides an exposure dose control method based on an exposure dose control system, which comprises the following steps: controlling a shutter to open; receiving an energy value collected by an energy sensor, determining an accumulated exposure dose value based on the energy value; determining whether the accumulated exposure dose value is not less than a target dose value; if the accumulated exposure dose value is not less than the target dose value, controlling the shutter to start to close; taking the accumulated exposure dose value corresponding to a shake delay end moment after the shutter is completely closed as an actual accumulated exposure dose value; determining an exposure dose error value based on the actual accumulated exposure dose value; determining whether the exposure dose error value meets a requirement; if the exposure dose error value does not meet the requirement, updating an equivalent dose value and returning to execute the first step; if the exposure dose error value meets the requirement, applying the equivalent dose value to an exposure system. Through the exposure dose control method based on the exposure dose control system, the problem of low exposure dose control precision is solved.

A control circuit accesses information representing radiation dose deposition as a function of time for a particular patient as well as at least one biological parameter for that particular patient. The control circuit then determines a biological equivalent dose for the particular patient as a function of both the information representing radiation dose deposition as a function of time and the at least one biological parameter to provide a determined biological equivalent dose for the particular patient.

The invention discloses a radioactive solid waste recycling method, which belongs to the technical field of radioactive waste treatment, and comprises the following steps: processing and forming radioactive solid waste into a ray source according to shape and size requirements, and measuring the energy and equivalent dose of rays on the surface of the ray source; an irradiation field is built, shielding measures are taken, an irradiation device used for placing an object to be irradiated is installed in the irradiation field, and a ray source is placed in the irradiation field; according to the irradiation purpose, a position meeting preset ray energy and equivalent dose rate is selected in the irradiation device, and the to-be-irradiated object is placed for irradiation; and after the to-be-irradiated object is irradiated to the target absorbed dose, taking out the irradiated object at a single time or in batches. Rays radiated in the radionuclide decay process are effectively utilized, a large amount of radioactive solid waste can be treated and repeatedly utilized, and the method is suitable for treatment of radioactive solid waste generated in reactors such as commercial reactors and research reactors and has important research value and application prospects.

This invention discloses a Monte Carlo deep learning method and system for modeling physical and biological doses in proton radiotherapy, belonging to the fields of medical physics, radiotherapy, and artificial intelligence. The method first utilizes Monte Carlo simulation to generate physical dose, linear energy transfer (LET), and relative biological effect (RBE) distribution data; then, it constructs an end-to-end deep learning framework including LSTM, Transformer, and 3D CNN to achieve rapid prediction from CT images to bioequivalent doses; through multi-scale feature extraction and multi-task learning, it simultaneously predicts physical dose and personalized RBE. This invention significantly improves the speed and accuracy of dose calculation, realizes personalized RBE assessment, and provides technical support for developing safer and more efficient proton therapy protocols.