153 results about "Doses rate" patented technology

Decision information systems, methods, and computer programs for better informing decisions to use multiple drugs in drug delivery devices, including implantable devices, for drug administration. Executable computer programs and logic embodying methods of the invention can calculate consistent multiple drug mixture amounts and drug delivery flow rates. One program accepts user input indicating a desired first drug dose rate, an initial first drug concentration, a desired second drug dose rate, an initial second drug concentration, and the reservoir size of the drug delivery device. The program method calculates a first drug amount and a second drug amount to combine in a mixture as well as a first drug true concentration in the mixture. The drugs can be mixed consistent with the physician's instructions using the program output. The first drug true concentration can be entered into a programmer device as the only drug concentration entered. Another program calculates a consistent first drug, second drug, and diluent amount to be added to a mixture for injection into a fixed flow rate, implantable drug delivery device. Methods preferably output true concentrations and dose rates for all drugs to be added and most preferably show all calculations used to arrive at the flow rate and mixture amount calculations. Yet another program receives a new desired drug dose rate for a previously filled device. The program accepts the existing mixture volume and true drug concentrations for a partially depleted device and calculates a new mixture flow rate to achieve the desired dose rate using the existing mixture. The methods can be implemented as executable computer programs in programmer devices, general purpose computers, servers, handheld computers, and personal digital assistants.

The invention discloses a miniaturized flash radiotherapy device. The device comprises a grid-control electron gun, a normal-temperature radio-frequency linear accelerator, a time domain synthesis radio-frequency power source, an X-ray target and a collimator; the grid-control electron gun transmits the electron beam to the normal-temperature radio-frequency linear accelerator through a first transmission line; the time domain synthesis radio-frequency power source provides microwaves for the normal-temperature radio-frequency linear accelerator; the normal-temperature radio-frequency linear accelerator transmits electron beams to the X-ray target through the second transmission line; and the electron beams bombard the X-ray target to generate X-rays, and the X-rays irradiate the target through the collimator. According to the miniaturized flash radiotherapy device, long macro-pulse high-dose-rate X-rays can be provided, a very high irradiation dose is given to a target area in a shorttime, the requirement of flash radiotherapy is met, and a better radiotherapy effect is achieved.

The invention discloses a flash radiotherapy device. The device comprises a direct-current photocathode electron gun, a superconducting linear accelerator, an X-ray target and a collimator, wherein the direct-current photocathode electron gun transmits electron beams to the superconducting linear accelerator through the first transmission line; the superconducting linear accelerator transmits theelectron beams to the X-ray target through the second transmission line; and the electron beams bombard the X-ray target to generate X-rays, and the X-rays irradiate the target through the collimator.According to the flash radiotherapy device, the direct-current photocathode electron gun and the superconducting linear accelerator are adopted, long-macro-pulse high-dose-rate X rays can be provided, a very high irradiation dose can be given to a target area in a short time, and the requirement of flash radiotherapy is met. And the energy of the ray can be adjusted by adjusting the energy of theelectron beam, the time length of the ray is adjusted by adjusting the pulse length of the electron beam, and the dosage rate is adjusted by adjusting the flow intensity of the electron beam, so thata better radiotherapy effect on the target is achieved.

The invention discloses a verification and calibration device of an environment and protection level dosage (rate) instrument, and particularly relates to a protection level gamma ray air kerma standard device. A source compartment (1) mainly comprises a lead jar (11), a source rod (12) and an air cylinder (13), wherein the air cylinder (13) is arranged below the lead jar (11); the source rod (12) is vertically arranged in the lead jar (11); two attenuator systems (3) are arranged on two side walls of the lead jar (11) respectively; two collimators (2) are arranged in the lead jar (11), one ends of the collimators (2) are connected with the source rod (12), and the other ends of the collimators (2) are respectively connected to the two attenuator systems (3); and two three-dimensional testing platforms (4) are arranged on the side edges of the two attenuator systems (3). According to the protection level gamma ray air kerma standard device, two protection instruments can be simultaneously verified, the efficiency is doubled, and the detection efficiency is greatly improved.

The invention discloses a power VDMOS threshold voltage remote online automatic test system, which comprises a control computer, a data acquisition card, a test development board and a DUT plug-in development board in an irradiation source. The invention also discloses a VDMOS threshold voltage remote online automatic test method. The adoption of the method realizes VDMOS threshold voltage remote online accurate measurement in the irradiation environment which the experimenters can not enter, including total dose irradiation, dose rate irradiation, single particle and neutron irradiation, in addition, real-time display of a testing curve on the computer screen is realized and real-time display and processing of test results and the threshold voltage are realized.

The disclosure relates to a method for partial discharge testing of an insulation component, wherein at least one X-ray pulse is applied to the insulation component, an AC voltage is applied to the insulation component and the partial discharge induced by the at least one X-ray pulse is measured, wherein the dose rate of the at least one X-ray pulse is at least about 10⁻² Gray/s. The disclosure relates further to a system for partial discharge testing of an insulation component which includes a flash X-ray source for generating at least one X-ray pulse, an AC voltage source, a voltage sensor, a partial discharge sensor and a partial discharge detection device for evaluating the measured partial discharge.

The invention discloses a fixed radiation monitoring system. The system comprises a control part, at most eight detectors and an ionization chamber, the detectors are located on the ionization chamberand connected with the control part, and the detectors are one or more selected from a low-range gamma detector, a wide-range gamma detector, a NaI gamma detector, a high-range gamma detector and a neutron detector. Thus, the structure is simple, the stability is high, the energy response is sound, the dose rate range is wide, the angular response and cosmic ray response are sound, and the mechanical property is reliable; and the system can work for a long time, does not reduce the monitoring performance due to the working time, and can be applied to measurement and real-time alarm of the environment X-gamma external irradiation air absorption dose rate and neutron dose equivalent, dose rate monitoring alarm of a radiation diagnosis and treatment workplace, monitoring of a medical X-ray machine and an industrial radioactive source, dose rate monitoring of an underground radiation environment, and the like.

A method for in-situ monitoring both the balloon/cavity and the radioactive source in brachytherapy treatment utilizing using at least one pair of miniature gamma cameras to acquire separate images of: 1) the radioactive source as it is moved in the tumor volume during brachytherapy; and 2) a relatively low intensity radiation source produced by either an injected radiopharmaceutical rendering cancerous tissue visible or from a radioactive solution filling a balloon surgically implanted into the cavity formed by the surgical resection of a tumor.

The invention discloses a radiation field visualization system and a method thereof. The system comprises a robot device, an ultra-wideband positioning module, a wireless transmission module, a videoimaging module which is used for receiving and presenting video information collected by the robot device, a human-computer interaction module, a data pre-processing module, a database module, an interpolation calculation module and a visualization module. The particle dose rate information detected by the robot device and the positioning information determined by the ultra-wideband positioning module are preliminarily processed by the data pre-processing module, and then are stored in the database module. The interpolation calculation module uses an interpolation method to inverse the entireradiation field according to the dose rate information and positioning information, which are processed by the data pre-processing module, of each point of a plant space, and the radiation field is stored in the database module. The visualization module is used for presenting the radiation field in the forms of a thermodynamic chart and a contour map. According to the invention, a UWB positioningtechnology and the interpolation method are used; the radiation field visualization system and the method thereof have the advantages of accurate positioning and simple calculation; and radiation field visualization is realized.

The invention discloses a gamma absorption dose rate instrument having soil moisture correction. The gamma absorption dose rate instrument comprises a detector and a host. The detector comprises a shell and a detection head arranged in the shell. The detection head is vertically downward, and the top part is provided with a photomultiplier and a pre-amplification circuit in turn. The two sides of the detector are respectively provided with a supporting rod. The bottom part of the supporting rod exceeds the bottom part of the detector. The supporting rod is provided with a slide rod. A soil hygrometer is fixedly connected on the lower surface of the slide rod. The output end of the soil hygrometer is connected with the host. The actually measured data of the detector can be corrected in real time according to the moisture so that the data are enabled to be more accurate and reliable after moisture correction, and the requirements that the samples require to be used for comparison and judgment under the dry condition can be met.

The invention discloses a self-correcting multi-cure-fitting digital dosage monitoring method and a system. The method comprises that data fitting is conducted in advance according to acquisition values, a fitting function is a piecewise function, an actual nonlinear relationship between ionization chamber output signals and actual dosage rate is established and the relationship is not a simple linear relationship. Thereby, the monitoring system of the invention can obtain accurate actual dosage rate and large deviation between the monitored dosage and the actual dosage is not caused even though the dosage rate is greatly changed.

The invention discloses a detector device rapidly and accurately locating a radioactive source as well as a location method. By virtue of the device, the radioactive source can be rapidly and accurately located, and the device is mainly used for finding a lost radioactive source. By virtue of the device, the aims of improving efficiency of handling a radioactive source loss accident and reducing damage of radiation on workers are achieved. The device comprises a circuit electronic module, a fixed bolt, a circular ring provided with a threaded hole, an end cover shielding structure, a radioactive detector, a fixed seat for the radioactive detector, a main body shielding structure and a base shielding structure. The device performs accurate measurement on dosage rates in different directionsby virtue of reasonable combination of multiple detectors and shielding structures, a circuit electronic system is adopted for calculating the dosage rates in different directions, and finally a location of the radioactive source is accurately obtained. By virtue of the device, the aims of improving the efficiency of handling the radioactive source loss accident and reducing the damage of the radiation on the workers are achieved.

A method for electron beam nanolithography without the need for development step involves depositing a film of a resist comprising functionalized fullerenes on a substrate, and writing features by exposure to an electron beam with an accelerating voltage and dose rate sufficient to promote heating or thermal degradation of the functionalized fullerene in the irradiated volume such that a pattern is generated without a subsequent development step or with an aqueous developer. Lithographic features of about 1 nm or greater can be formed.

The present invention relates to a system and method for fluid flow control, for particular user in a hay baler. The system involves calculating or inputting a preferred flow rate (the Set Point), measuring the “actual” flow rate of liquid through the system, and controlling the speed of a pump used to move the liquid through the system to ensure that the flow rate is maintained as close as possible to the Set Point flow rate at all times during operation. The flow rate Set Point can be calculated using one or more user or sensor inputs, including the dose rate, the mass flow rate of fodder, the moisture content, etc.

The invention belongs to the technical field of counting tube devices (G01T1/18), and relates to a method for realizing wide-range radiation detection by using a single-GM counting tube. The method comprises two parts of high pressure control and dosage rate calculation on the basis of a dead time correction principle, and range expansion of the GM counting tube is realized by respectively adopting a method of combining hardware dead time elimination and software piecewise interpolation correction. Due to the piecewise interpolation, nonideal factors can be reduced, and especially, the influence to a measurement result by inconsistency of parameters of elements is reduced. Testing results of dosage apparatus prototype manufactured according to the invention prove that the measurement linear range and the detection upper limit of a J305 low-range counting tube made in China can be improved by 1000 times, and the detection range is 0.1uGy/h-300Gy/h. By adopting the invention, the single-GM counting tube can meet use requirements of most of radiation detection occasions.

The invention discloses a safe monitoring method for a radioactive source during flaw detection. The method comprises the following steps: (1) when an automatic control instrument sends out a radioactive source working signal, comparing and analyzing by a central processor to obtain a result that the radiation dose rate of the radioactive source acquired by a radiation dose rate signal acquisition module is increased based on the background radiation dose rate and reaches the radiation dose rate of a source storage device, and obtaining that the radioactive source works normally; (2) when the automatic control instrument sends out a radioactive source storage signal, comparing and analyzing by the central processor to obtain a result that the radiation dose rate of the radioactive source acquired by the radiation dose rate signal acquisition module is reduced to be less than 30% of the radiation dose rate of the source storage device, and judging that the radioactive source works normally; comparing and analyzing by the central processor to obtain a result that the radiation dose rate of the radioactive source acquired by the radiation dose rate signal acquisition module is still not reduced to be less than 30% of the radiation dose rate of the source storage device, judging that the radioactive source is not recovered in the source storage device and the radioactive source works abnormally, and giving an alarm by an alarm module to finish the safe monitoring process.

The invention relates to a radiation detection device and a chip, through a radiation detection circuit configured with a gamma ray detection probe and a neutron detection probe, detection of gamma rays or neutrons is completed at the same time, and detection of various particles is realized. Meanwhile, when the dose rate is smaller than or equal to a dose limit value, a detection signal of the radiation detection circuit is obtained through a pulse mode circuit, the output pulse number is the same as the particle number corresponding to the detection signal, and an external processor calculates to obtain a detection result; and when the dose rate is greater than the dose limit value and exceeds the upper limit of the counting rate of the pulse mode circuit, the current mode circuit is adopted to convert the measured current into voltage, and the detection result is calculated through an external processor. On the basis, through cooperative work of a pulse reading mode and a current reading mode, wide-range detection of radiation detection is realized.

Embodiments of the present invention provide an integrated solution to radiotherapy treatment planning that enables accurate recording and accumulation of physical parameters as input (e.g., dose, dose rate, irradiation time per voxel, etc.). User-defined functions are evaluated to correlate the input parameters with 4D biological outcomes. The resulting biological parameters can be visualized as a biological outcome map to evaluate decisions, support decisions, and optimize decisions regarding the parameters of the radiotherapy treatment plan, for example, for supporting clinical trials and related clinical research.

The invention discloses low-medium level radioactive waste barrel surface dose rate detection equipment and an application thereof, and relates to the technical field of nuclear power station solid waste treatment. The equipment comprises a waste bin rotating assembly, a waste bin surface dose rate detection device and a waste bin surface activity measurement device; the waste bin surface dosage rate detection device comprises a lifting support assembly, a lifting power assembly and a mechanical arm assembly. The mechanical arm assembly comprises a limiting transmission sliding block, a mechanical arm upper arm, an electric telescopic rod, a mechanical arm lower arm, an upper and lower arm torsional elastic piece, a detector assembly and a detector position adjusting elastic part. A dose rate detection device is arranged on one side, far away from the mechanical arm lower arm, of the detector assembly; rollers are respectively arranged at two ends of one side, far away from the mechanical arm lower arm, of the detector assembly; the dose rate distribution, maximum dose rate detection and activity detection of different heights and distances of the waste bin are implemented by adopting one detector assembly, so the use is very convenient.

The invention discloses a nuclear power radiation environment simulation system based on a UWB technology, and the system comprises: a server which can receive a given simulation dose rate inputted bya user; at least one simulation radioactive source which is internally provided with a first UWB module, wherein the server is in communication connection with the first UWB module through the Ethernet; and at least one simulated personal dosimeter which is internally provided with a second UWB module, a timing module and a display screen, wherein the second UWB module is in signal connection with the first UWB module, the second UWB module, the timing module and the display screen are electrically connected in sequence, the timing module is used for timing the residence time of the positionwhere the simulated personal dosimeter is located, the second UWB module is configured to obtain a distance measurement value between the simulated personal dosimeter and the simulated radioactive source, calculate a simulated dose rate of the position where the simulated personal dosimeter is located based on the distance measurement value and a given simulated dose rate, and calculate a simulated dose of the position where the simulated personal dosimeter is located based on the simulated dose rate and a time value of the timing module, and a display screen is used for outputting and displaying the simulated dose rate and the simulated dose.

The invention belongs to the field of nuclear power station radiation prevention, and particularly relates to a simulation radiation field intensity and dose measurement method for training, which comprises the following steps: arranging a simulation source and a radiation intensity measurement instrument; positioning and ranging the simulation source and the radiation intensity measuring instrument to obtain the distance between the simulation source and the radiation intensity measuring instrument, and finally determining the dose rate H. Dose simulation measurement is given, accurate simulation of the inverse square rule of the radiation horizontal distance is achieved, and an operator can rapidly measure and know the influence of distance protection on external radiation protection. A simulation field radiation field working environment is established at a place far away from a field through a simulation source and a measuring instrument, and the intensity and dose of a simulated radiation field are measured according to the calculation of the intensity and dose of the radiation field.