48 results about "Cumulative dose" patented technology

An ultraviolet area sterilizer or disinfector is incorporated into a building structure where concern exists regarding the presence of pathogenic bacteria on environmental surfaces. Ultraviolet C (UV-C) generators generate UV-C that is directed to architectural partitions of an enclosed area. The architectural partitions reflect UV-C to kill pathogens in the enclosed area. The device transmits a calculated dose of UV-C from a fixture mounted to an architectural partition in the enclosed area. Once an effective cumulative dose of UV-C has been reflected to radiation sensors, as measured by the sensors, the device shuts down.

An ultraviolet area sterilizer or disinfector is incorporated into a building structure where concern exists regarding the presence of pathogenic bacteria on environmental surfaces. Ultraviolet C (UV-C) generators generate UV-C that is directed to architectural partitions of an enclosed area. The architectural partitions reflect UV-C to kill pathogens in the enclosed area. The device transmits a calculated dose of UV-C from a fixture mounted to an architectural partition in the enclosed area. Once an effective cumulative dose of UV-C has been reflected to radiation sensors, as measured by the sensors, the device shuts down. The device allocates power to specific UV-C emitters so as to direct UV-C radiation more uniformly throughout the area, as measured by the sensors.

An ultraviolet area sterilizer or disinfector is incorporated into a building structure where concern exists regarding the presence of pathogenic bacteria on environmental surfaces. Ultraviolet C (UV-C) generators generate UV-C that is directed to architectural partitions of an enclosed area. The architectural partitions reflect UV-C to kill pathogens in the enclosed area. The device transmits a calculated dose of UV-C from a fixture mounted to an architectural partition in the enclosed area. Once an effective cumulative dose of UV-C has been reflected to radiation sensors, as measured by the sensors, the device shuts down.

Methods and systems are provided for protecting a critical structure during the administration of radiation treatment to a patient. A register receives proposed positions for one or more radiation beams with respect to a critical structure. A processor predicts a cumulative dose volume for the critical structure based on the dose distribution, and determines if the cumulative dose volume exceeds a tolerance value. If the cumulative dose volume exceeds the tolerance value, the dose distribution may be translated at least in part based on a relationship between the cumulative dose volume and the dose distribution position.

An AEC unit of an electronic cassette sets a dose target value and a short-circuited pixel used for AEC based on a radiographing condition. When a control unit of the electronic cassette detects start of irradiation of X rays, the AEC unit starts integration of a cumulative dose of X rays which are incident to a target region based on a dose detection signal output by the short-circuited pixel. The AEC unit predicts a stop timing at the time point t1, waits until the time point t2 which is a predetermined time earlier than a scheduled stop time, and sends a stop timing notification to an X-ray generation device at the time point t2. When the stop timing notification is received, a X-ray source control device immediately inputs an irradiation stop command so as to stop an operation of an X-ray source.

A device modeling method in relation to total dose radiation, wherein firstly, an original electronic device is designed and undergoes testing and model extraction to obtain the model of the original device, secondly, the obtained original device undergoes radiation at different target cumulative doses and model extraction to obtain the device model after radiation at all target cumulative doses, and lastly, the obtained original device model and the device model that has received radiation at all target cumulative doses jointly constitute the device model in relation to total dose radiation. Through testing and parameter extraction of the original device and the device that has received radiation at all target cumulative doses, the present invention provides a method for accurate modeling of hardened devices and unhardened devices. Meanwhile it adds radiation dose as a variable into the realization method of device model so that the performance of the circuit that has received radiation at different doses can be accurately predicted through simulation, thus raising the design efficiency and success rate of the circuits.

There are provided a radiation detector and a radiological image radiographing apparatus capable of improving the quality of an obtained radiological image while suppressing the deterioration of the sensitivity of a phosphor layer according to the cumulative dose of radiation. In the radiation detector, a second scintillator which absorbs lower radiation energy than radiation energy absorbed by a first scintillator and whose deterioration of sensitivity according to the cumulative dose of radiation is larger than that of the first scintillator is provided at the downstream side of the first scintillator in the emission direction of the radiation. In addition, two substrates of a first substrate, which mainly acquires electric charges corresponding to light generated by the first scintillator, and a second substrate, which mainly acquires electric charges corresponding to light generated by the second scintillator, are provided.

The present invention relates to the radiation environment detection technology field, and relates to the system and method of ionization total dose detection based on an SOI (Silicon-On-Insulator) structure. The detection system comprises a probe module, a constant flow source module, a data collection module and a control module. The input end of the control module is connected with a PC, the output end of the control module is connected with the constant flow source module, the data collection module and the probe module; the constant flow source module is connected with the probe module; the input end of the data collection module is connected with the probe module, and the output end of the data collection module is connected with the PC; and the probe module comprises a radiation sensor of the SOI structure. The system and method of the ionization total dose detection based on the SOI structure realizes the sensor nationalization of a satellite PMOS dosimeter, improves the sensitivity, and can be used for the test for lower dosage accumulation; and the detector is portable, flexible and easily used based on the structure, and is suitable for the space environment monitoring, the semiconductor device ionization effect assessment and the life prediction.

A light pattern exposure method is by irradiating ArF excimer laser light to a resist film through a halftone phase shift mask. The mask includes a transparent substrate and a pattern of halftone phase shift film of a material comprising a transition metal, silicon, nitrogen and oxygen and having an atomic ratio (Met / Si) of 0.18-0.25, a nitrogen content of 25-50 atom %, and an oxygen content of 5-20 atom %. The mask may be irradiated with ArF excimer laser light in a cumulative dose of at least 10 kJ / cm2.

The invention discloses a measuring system for nuclear radiation cumulative dose based on a memristor. The measuring system comprises a nuclear radiation sensor, an amplifier, a measuring switch S1, acurrent limiting resistor, a parallel memristor module, an information processing circuit for a resistance value of the memristor and a reset circuit module of the memristor. The nuclear radiation sensor is connected to the parallel memristor module through the amplifier, the measuring switch S1 and the current limiting resistor. The information processing circuit for the resistance value of thememristor is connected to the parallel memristor module. The reset circuit module of the memristor is connected in parallel with the parallel memristor module. The parallel memristor module comprisesn reverse series memristor branches connected in parallel, each of the reverse series memristor branches comprises a forward memristor and a reverse memristor connected in series, wherein n is a natural number greater than or equal to 2 and less than or equal to 8.

A light pattern exposure method is by irradiating ArF excimer laser light to a resist film through a photomask. The photomask includes a transparent substrate and a pattern of optical film of a material comprising a transition metal, silicon, nitrogen and oxygen, with contents thereof falling in a specific range. The photomask may be irradiated with ArF excimer laser light in a cumulative dose of at least 10 kJ / cm2.

The invention provides a voxel-based body external irradiation dose simulation method. According to the method, 3dsMax software is used to establish a virtual human model with a skeleton animation; dose distribution data in a virtual nuclear radiation field is initialized; according to a body structure and a skeleton structure of a virtual human, a body voxel model is established; body modules areallocated, and weights of all the modules and a body effective dose calculation formula are defined; an interpolation method is utilized to calculate an instant exposure dose rate and an accumulateddose of the virtual human; a body exposure dose is calculated based on the skeleton animation; and all the modules perform parallel calculation. Through the method, voxelization is not directly performed on a three-dimensional model of the virtual human, the steps are easier and more convenient, the voxel model can move along with human skeletons, and real-time dose evaluation is realized.

A stochastic patient movement model and a dosage delivery plan are used to determine probabilities of dosages received by a target volume during a radiation treatment. The stochastic patient movement model is created by identifying possible sequences of patient positions during the treatment with probabilities specified for each. The dosage delivery plan specifies dosage levels and radiation locations over time. Accumulated dosages are calculated for each sequence of patient positions and the dosage delivery plan. The specified probability for each sequence is then correlated to the accumulated dosage for that sequence.

The invention discloses a biological effect-guided self-adaptive radiotherapy system. The system comprises an information input module, a three-dimensional dose distribution calculation module, a deformation field calculation module, a cumulative dose distribution calculation module, a biological effect feedback calculation module, a treatment plan generation module and an information output module; the information input module isused for inputting required data information,the three-dimensional dose distribution calculation module is used for calculating three-dimensional dose distribution completing fractionated irradiation and calculating the dose distribution of the current fractionated irradiation, the deformation field calculation module is used for calculating a deformation field, the cumulative dose distribution calculation module is used for calculating cumulativedose distribution completing fractionated irradiation, the biological effect feedback calculation module is used for constructing the total dose model,calculatingtotal dose distribution and calculating the biological effect feedback of each organ in a patient, the treatment plan generation module is used for generating a current fractionated irradiation plan, and the information output module is used for outputting the current fractionated irradiationplan. Accordingly, the biological effect feedback is utilized for guiding the fractionated irradiationplan optimizing process, and on the condition that fractionated irradiation has irradiation errors, the influence of repair and multiplication of cells amongfractionated irradiation on the radiotherapy quality is comprehensively considered.

The invention discloses a method for modifying a printing and dyeing paste. The printing and dyeing paste is a natural paste; and the natural paste is irradiated with an electron beam generated by an electron accelerator. The natural paste is guar gum or tamarind seed gum, and the cumulative dose of the irradiation is 5-70kGy. According to the invention, the electron accelerator is utilized to irradiate and degrade the printing and dyeing paste for textile-natural paste, so that the viscosity of the paste is lowered to the viscosity number beneficial to textile printing and dyeing, and the optimal irradiation dose of the viscosity number can be obtained. The invention is simple to operate, and has the advantages of high processing efficiency and low cost.

The invention relates to the technical field of nuclear radiation detection and provides time sequence control logic and signal processing algorithm suitable for pulsed optically stimulated luminescence technique-based quasi-real-time dose rate measuring devices. The time sequence control logic provided by the invention has the beneficial effects that a same reference clock is adopted as a reference to generate input pulse signals of a laser, a shutter, a photomultiplier and a counter; and the precise time sequence control of the laser, the shutter, the photomultiplier and the counter can be realized by each pulse signal through setting the number of skipped reference pulses and the relative time delay relative to the reference clock. The signal processing algorithm provided by the invention has the beneficial effects that various dynamic and static backgrounds are considered; the relationship between cumulative dose and count value is given by linear fitting results of experimental data; the cumulative dose loss caused by each dose rate measurement is compensated; and therefore, the quasi-real-time dose rate can be accurately given.

The invention discloses a pharmaceutical composition for prevention of rectal carcinoma radioactive skin damage and an application thereof; the pharmaceutical composition is prepared from an active component and auxiliary materials; the active component is prepared by water extraction and alcohol precipitation of the following traditional Chinese medicine raw materials in parts by weight: 13-20 parts of potentilla fulgens wall, 12-18 parts of tribulus terrestris, 12-18 parts of mandarin orange seed, 13-20 parts of abelmoschus crinitus wall, 21-30 parts of herba lycopi, 21-30 parts of white atractylodes rhizome, 6-12 parts of fructus amomi, and 10-20 parts of herba hyperici. The pharmaceutical composition not only can delay the generation of radioactive skin damage, ensure smooth performing of radiation therapy and improve tolerability of patient skins on the cumulative dose of radiation, but also can promote healing of radioactive skin damage wound surfaces.

The invention discloses an irradiation-resistant camera which is composed of an external protection assembly and an internal function assembly. The external protection assembly is composed of an outercylinder assembly, an upper cover assembly and a lower cover assembly. The internal function assembly is composed of a lens assembly, a filtering assembly, an image information acquisition device, ashielding plate, an image information processing device, a left supporting plate, a right supporting plate and a heat dissipation plate. The irradiation-resistant camera has high irradiation resistance, and the cumulative dose can reach 103 Gy; high definition can still be ensured in a strong irradiation environment; the guiding device is arranged, so that the imaging positive direction of the radiation-resistant camera can be quickly determined; all the modules are reasonable in structural layout, and the radiation resistance of the camera is high.

The invention relates to a special silicone sealant for the internal structure of a nuclear power plant, which comprises the following components in mass-number ratio: 100 parts of 50000cs hydroxyl silicone oil; 5-10 parts of dimethyl silicone oil; 1-5 parts of KH550 coupling agent ; 1-5 parts of KH560 coupling agent; 10-35 parts of flame retardant powder; 10-20 parts of heavy alumina; 15-30 parts of inorganic filler; 5-10 parts of dibutylketoxime silane; 0.5-1.5 parts of organotin catalyst. An internal sealing structure of a nuclear power plant includes a CV steel plate and a concrete wall, and silicone sealant. A depression is provided at the joint between the concrete wall and the CV steel plate, and the silicone sealant is provided in the depression. The beneficial effect of the present invention is: after the cumulative radiation dose and LOCA test of the 60-year lifetime of the nuclear power plant, there is no pulverization and degradation, and still has good bonding performance and flexibility; the pressure of 66psig (455kPa) inside the simulated CV Under this condition, a relative displacement of lin (25.4mm) occurs between the CV and the concrete, which can ensure good watertight and airtight performance.