72 results about "Radiation risk" patented technology

A device intended to reduce the risks of overexposure to harmful solar radiation. The device includes a detection arrangement, including at least one sensor sensitive to solar radiation, in particular UV. In addition, an arrangement is linked to the detection arrangement to generate a signal representing the quantity of radiation received by the detection means. An attachment arrangement is provided to attach the device to the head of a subject, such that the sensor(s) is (are) oriented in a substantially perpendicular manner to the vertical plane of the subject when the latter is active in the sun. The device is preferably configured in the form of a cap, with the detection arrangement arranged on a first visor intended to be positioned over the back of the individual's neck. The cap also preferably includes a second visor located opposite the first.

The invention discloses a method for evaluating a single-particle effect index of a satellite device. The evaluating method comprises the following steps of: acquiring a single-particle turnover test value of a to-be-evaluated device by testing or simulating; calculating a single-particle turnover index required prediction value, required by a task, of the to-be-evaluated device; acquiring a radiation design margin according to a test expected value of the single-particle turnover index of the device and the single-particle turnover index required prediction value; and evaluating the radiation risk level of the device according to the radiation design margin. According to the technical scheme, the method for evaluating the single-particle effect index of the satellite device can effectively direct the model selection of the satellite device by calculating the single-particle turnover rate index of the device, and provide quality assurance for the satellite to victoriously finish the task.

The invention discloses a nuclear rector pressure vessel nozzle safe end welding joint automatic ray inspection device. The device comprises a support positioning mechanism for supporting the integral device on a pressure vessel, a min rotating mechanism for adjusting an inspection angle, and three telescopic inspection arm mechanisms which are peripherally and uniformly distributed to inspect the weld joint. The structure and operation inspection device provided by the invention have high automatic degree so that the staff is free from operating near source, thereby furthest eliminating the potential radiation risk; the device can simultaneously inspect safe ends of three water inlet nozzles or three water outlet nozzles in 120 degrees with each other, improve the inspection efficiency, and shorten piling time of a nuclear power station in major overhaul period; an inspection assembly has the functions of radial self-adjusting, automatic centering and through flow, is used for solving the problem that the axial direction force on the device is overlarge due to the overlarge radial force on an air bag and the pressure difference between two sides of the air bag. The technical scheme can be widely applied to the ray inspection of other underground pipelines and has great application value.

The invention relates to the technical field of CT (computed tomography) system parameter calibration, in particular to a C-arm system rotational angle calibration device and a C-arm system calibration method; the C-arm system rotational angle calibration device comprises a motion conversion component, a displacement sensor, a data transmitter and a processor, the motion conversion component is arranged to connect with a C-arm and convert rotational motion of the C-arm into linear motion, the displacement sensor is connected with the motion conversion component and is arranged to acquire a displacement signal of the motion conversion component and transmit the displacement signal to the data transmitter connected with the displacement sensor, and the processor is connected with the data transmitter and is arranged to receive and analyze the displacement signal transmitted by the data transmitter. The C-arm system rotational angle calibration device is simple to operate, good in operational stability and reliability, and free of X-ray exposure in use, so that the radiation risk can be lowered.

The invention relates to a non-radioactivity tracing flow well logging method and process based on the pulse neutron technology in the oilfield production injection profile well logging technology. The non-radioactivity tracing flow well logging method and process based on the pulse neutron technology includes the steps of using a solution of a non-radioactive substance, such as a gadolinium compound or a boron compound, with a high heat neutron capture cross section as a tracing agent, using the neutron lifetime manner to measure the macroscopic capture cross section of fluid in a well, namely using high-strength pulse neutrons emitted by a pulse neutron generator to bombard the tracing agent, capturing heat neutrons by the tracing agent, using different well logging processes to record heat neutron time spectrums or the heat neutron counting rate of a fixed spacing detector, and calculating the flow speed of the fluid in the well and the use conditions of a thin difference layer by analyzing well logging data. The non-radioactivity tracing flow well logging method and process based on the pulse neutron technology is free of radiation risks, meets the environment-friendly requirement, is low in measuring lower limit, effectively solves the problem that an current layering injection well is low in flow and large in monitoring error, and has wide site adaptability.

The invention belongs to the technical field of probabilistic safety assessment, and specifically relates to a probabilistic safety assessment method for nuclear fuel highway transportation. Accordingto the invention, potential accident determination is performed according to basic data of the evaluation, accident scenario analysis and package integrity analysis, then accident frequency calculation, source item analysis and consequence estimation are performed, finally overall radiation risk calculation is performed, and the transportation risk is assessed. The probabilistic safety assessmentmethod can make up a defect that the selection of radiation consequence accident calculation in the traditional method is purely by experience, can be applied to safety assessment for nuclear fuel highway transportation, and is quantitative and more scientific.

The invention discloses a power generation and nuclear fuel processing disposal integrated nuclear energy base based on closed cycle. The power generation and nuclear fuel processing disposal integrated nuclear energy base comprises a nuclear energy power generation area, a spent fuel and waste disposal area, and a waste final disposal area. The nuclear energy power generation area comprises a reactor workshop, a nuclear auxiliary workshop, and a fuel workshop. The spent fuel and waste disposal area comprises a spent fuel and waste disposal workshop and a waste processing workshop. The waste disposal area comprises a commissioned near surface disposal warehouse, a decommissioned near surface disposal warehouse, a middle depth disposal warehouse, and a deep geological disposal warehouse. The nuclear energy base is divided into the power generation area, the fuel and waste disposal area, and the waste final disposal area according to functions, and the planning, the siting, and the investment of the whole nuclear energy base are realized in a unified manner, and therefore planning is facilitated, and factory site resources are saved. The spent fuel and the wastes are processed and disposed in the neighborhood, and therefore radiation risks caused by long distance transport are prevented.

The invention discloses a detection device of an on-orbit radiation risk of a spacecraft. The detection device comprises a detector shell and seven built-in detection unit groups. Each detection unitgroup consists of a temperature sensor and a total dose detector; the shell part right above one detection unit group is opened to ensure detection without shielding limiting of the shell; the anotherdetection unit group uses the spacecraft shell as a shielding layer for detection and the other five detection unit groups are provided with metal shielding layers with different thicknesses to detect different space radiation effects. Each detection unit group is arranged on the intermediate circuit board for collecting the temperature and the total dose. The detection device has characteristicsof simple structure, small size, light weight, low power consumption and the like; risks of different space radiation effects such as a surface charge-discharge effect, a total dose effect, a singleparticle effect, a displacement damage effect, an internal electrification effect and the like can be determined.

The invention discloses a sealed radioactive source and a preparation device and method thereof. The sealed radioactive source comprises an airtight bag shell and a radioactive substance contained inthe airtight bag shell, and the airtight bag shell comprises two interfaces which can be open and closed. The preparation device comprises a mixed liquid circulating pipeline and a circulating power component, the mixed liquid circulating pipeline comprises two bag shell interfaces and at least one drug interface, the two bag shell interfaces are used for being detachably and hermetically connected with the two interfaces on the airtight bag shell respectively to enable the inside of the airtight bag shell to be communicated with the mixed liquid circulating pipeline, the drug interface is used for guiding radioactive drug in at least one external radioactive drug container into the mixed liquid circulating pipeline, and the circulating power component is used for providing circulating power into the mixed liquid circulating pipeline. The preparation device prepares the sealed radioactive source in a fully automatic manner and does not need participation of operating personnel, so thatradiation risk of the operating personnel is lowered, and the radioactive source prepared by the device is uniform in activity.

The invention discloses an invisible laser system and an optical path visualization method thereof and belongs to the technical field of laser. The invisible laser system comprises an invisible laser generator for generating invisible laser; a visible light generator for generating visible light; and an optical path visualization component which is arranged in light paths of the invisible laser and the visible light, and at least comprises a first incoming end, a second incoming end and a first outgoing end, wherein the invisible laser is incident at the first incoming end; the visible light is incident at the second incoming end; and all invisible laser and at least a part of visible light are output in parallel at the first outgoing end. According to the invisible laser system and the optical path visualization method thereof, all invisible laser only exists in the direction parallel to the light path of the visible light, and the invisible laser does not exist in other directions, thereby eliminating radiation risk.

The invention relates to an optimization design method of a liquid state effluent measure apparatus sampling system, which comprises the optimization of a detector system used by matching with a sampling chamber in the sampling system; optimization of the thickness of a shielding layer at the peripheral part of the sampling chamber; and optimization of volume and dimension of the sampling chamber. The method comprises the following steps: for a simulated source item containing nuclide to be measured, preferably selecting a detector with 1-5 inches and performing preliminary simulation by different sizes, analyzing detection and electronic performance of the detector, and analyzing the relation of sampling chamber volume and the detection system counting rate; by aiming at the selected area to take regard of extraneous interference factor, performing background radiation shield simulation to determine an appropriate shielding layer thickness; measuring the counting rate relation of economic cost and detection system; and determining the optimized liquid state effluent monitoring sampling system. According to the method, excellent monitoring performance of the monitoring sampling system is obtained, and the system research and open time can be simultaneously and effectively saved, design cost is saved, and the radiation risk is minimized.

The invention provides a metabolic marker for diagnosing or monitoring lung adenocarcinoma and a screening method and application of the metabolic marker. A metabolic marker system is selected from one or a combination of more of D-galactose, homocitrulline, N6-acetyl-L-lysine, 4-hydroxy-L-proline, hexadecanedioic acid, guanine, glutamic acid, creatine, alanine and kynuric acid. The metabolic marker provided by the invention can accurately diagnose a lung adenocarcinoma patient, can distinguish an early-stage lung adenocarcinoma patient from a healthy person, is high in sensitivity and strong in specificity, can well replace an existing tissue biopsy and imaging diagnosis mode, and reduces trauma and radiation risks.

The invention belongs to the technical field of mechanical design, and particularly relates to a device suitable for flushing the surface of a spent fuel dry-method storage container. The device comprises a flushing water tank, flushing supports, flushing sprayers, flushing pipes and quick connectors; and the multiple flushing pipes form a loop through the quick connectors, each flushing pipe is provided with one flushing sprayer and one flushing support used for fixing, and one flushing pipe is connected with the flushing water tank. Radiation risks and industrial risks caused by the fact that personnel stand beside a spent fuel pool to flush the surface of the storage container are avoided, the surface pollution level of the full-load spent fuel container meets the radioactive substancetransportation standard in a nuclear power plant, meanwhile, the radiation dosage borne by the personnel when the personnel flush the storage container is reduced, the operation time of the personnelduring near-edge operation is shortened, risks of the personnel during near-edge operation are reduced, the operation process is optimized, and the safety of the personnel and equipment is ensured.

The invention discloses a reading method of a non-digitalization transmission instrument in a nuclear radiation environment. The reading method comprises the following steps: S1: transmitting an image acquisition instruction of the non-digitalization transmission instrument in the field of the nuclear radiation environment according to an instruction; S2: receiving the image acquisition instruction, and performing the image acquisition on the non-digitalization transmission instrument to obtain a display image of the non-digitalization transmission instrument; and S3: comparing the display image with background information in an instrument background information database to obtain reading information of the non-digitalization transmission instrument. By adopting the reading method and the reading system of the non-digitalization transmission instrument in the nuclear radiation environment, the non-digitalization transmission instrument in the nuclear radiation field can be remotely and intelligently read, the personnel does not need to go the field, and the radiation risk can be avoided.

The invention discloses a control method, a control system and a control device of auto-exposure of C-arm X-ray machines. The device collects images according to the setting exposure parameter, analyzes images, adjusts the exposure parameter and collects images again. Through such a rapid and continuous process of collection and adjustment, the control device of auto-exposure of C-arm X-ray machine realizes auto-exposure control, eases the burden of doctors and reduces the surgical risk by automatically outputting and locking the optimal exposure parameter in a short time. the control device of auto-exposure of C-arm X-ray machine also realizes consistency of the diagnostic images of different body parts of patients in different body sizes; in addition to meeting the diagnosis quality demand of images, the device also minimizes the radiation level of rays and reduces the radiation risk of doctors and patients.

Methods and compositions are provided for alleviating and / or preventing one or more side effects associated with exposure to radiation in a subject exposed to radiation or at risk for exposure to radiation comprising oral administration to the subject of an amount of an edible source of melanin effective to alleviate a side effect associated with radiation.

The invention relates to a radiation protective control method for repairing a damaged spent fuel assembly of a mega-kilowatt nuclear power plant. The radiation control method comprises the following steps of A1, carrying out sipping test and ultrasonic or eddy current inspection on the damaged spent fuel assembly; A2, analyzing a radiative source term according to the test result and the inspection result; A3, developing a radiation protective optimized action form and a control point document according to the analysis result of the radiative source term, and finishing the work of a radiation protective control document; A4, performing the radiation protective control in the repairing process of the damaged spent fuel assembly on the basis of the radiation protective control document. According to the radiation protective control method disclosed by the invention, standardized operation can be realized by combining practical experience and adopting scientific and reasonable radiation protective means, so that accidental release of radioactive substances in the repairing process of the damaged spent fuel assembly is prevented, and radiation risk for operators is reduced.

The invention discloses a route planning method under the nuclear radiation environment. The route planning method comprises the following steps: S1, in order to prevent workers from colliding obstacles in a walking process, swelling the obstacles; S2, in a map which the obstacles have been swelled on, generating a point set V containing the appointed number of random points; on a free space whichthe random points exist in, avoiding collision with the obstacles; S3, performing partial planning, connecting elements in the random point set V two by two, constructing a set E related to side lengths after collision detection and calculating out dosage values corresponding to all the side lengths through a dosage function at the same time; S4, inputting a starting point qI and a terminal pointqG and connecting the starting point and the terminal point into the side length set E according to the S2; S5, utilizing an A*algorithm to perform discrete searching to obtain a side sequence and forming a route from the qI to the qG through the obtained side sequence. The route planning method disclosed by the invention utilizes a random route diagram method to find routes under the nuclear radiation environment, has a small calculation amount, can quickly find the route with the complete probability and reduces radiation risk.

The invention belongs to the field of mechanical separation and connection, and particularly relates to a connecting device. The connecting device comprises a connecting body, a locking arm arranged on the outer side of the connecting body, a supporting sleeve arranged in the connecting body, a bevel gear arranged in the supporting sleeve and a bearing seat capable of being inserted in and pulled out of the connecting body. A hollow shaft sleeve penetrates through the bearing seat, the sealed top end of the shaft sleeve protrudes upwards out of the bearing seat, and a spring and a transmission shaft are arranged in the shaft sleeve. A baffle ring blocking separation of the transmission shaft is arranged at the bottom end of the shaft sleeve, the spring squeezes the transmission shaft to the direction of an opening in the bottom end of the shaft sleeve, and the end, away from the spring, of the transmission shaft protrudes out of the bottom of the shaft sleeve and can be connected with or separated from the top of the bevel gear along with inserting and pulling of the bearing seat in the connecting body. An end cover blocking separation of the shaft sleeve is arranged at the bottom end of the bearing seat, and a bearing is arranged between the bearing seat and the shaft sleeve. An operator can remotely mount and separate the connecting device in a hot chamber by operating a mechanical arm, so that operation is simple and rapid, the repairing cost is reduced, and meanwhile, the radiation risk to the operator is avoided.

The invention discloses a Monte Carlo method-based cargo packet drop angle analysis method and system. The method comprises the following steps of: step 101, recording random sampling times; 102, generating a random number; 103, performing sampling to obtain each random variable; 104, based on each random variable obtained by sampling at this time, carrying out simulation analysis on a collision accident scene at this time, and determining a cargo packet drop angle simulated at this time as a sampling result at this time; step 105, performing statistical analysis on the sampling result of the current time; and 106, carrying out credibility evaluation on the statistical analysis result, if the evaluation result is credible, ending the evaluation, if the evaluation result is not credible, adding 1 to the sampling times, and returning to the step 102, and continuing to repeatedly sample. According to the method and the system provided by the invention, the cargo packet drop angle in a single collision accident scene is analyzed through a Monte Carlo method, a credible confidence interval is given according to the drop angle, and the result credibility of subsequent accident analysis and radiation risk evaluation is ensured.

The invention belongs to the field of safety evaluation for radioactive substance transportation, and specifically relates to a method for determining a quantitative safety goal of radioactive substance transportation. In the method, the concept of [alpha] in a cost-benefit analysis method in radiation protection optimization is utilized, a radiation risk target value of radioactive substance transportation is calculated, and the calculated radiation risk target value is compared with a radiation risk value of a probabilistic safety assessment result to determine whether the radioactive substance transportation process meets the quantitative safety goal or not. The method is simple in logic, convenient to operate and applicable to determining the quantitative safety goal for transportationof various types of radioactive substances.

The invention relates to an application of circulating blood miR-34a in radiation monitoring as a radiation biomarker. The circulating blood miR-34a is extracted from animal or human serum through a routine method, and is used for judging the degree of damages of irradiation and radiation to animals or people when non-uniform irradiation or accidental irradiation is carried out for above 6h. The circulating blood miR-34a can be used to monitor the irradiation condition of people and animals in accidental radiation as a beneficial supplement of a physical dosimeter measurement result in order to effectively improve the assessment accuracy of radiation risks and radiation harms.

The invention provides a metabolic marker for diagnosing benign and malignant pulmonary nodules and application of the metabolic marker. The metabolic marker is selected from one or combination of 4-hydroxy-L-proline, hyodeoxycholic acid, xanthine, 2-hydroxy-6-aminopurine, 5, 6-dihydrothymine, isobutyryl carnitine, guanine, glutamic acid, asparagine, formononetin, alanine and kynuric acid. The 12 metabolic markers provided by the invention can accurately diagnose and distinguish lung benign and malignant nodules, have high sensitivity and strong specificity, can well replace the existing tissue biopsy and imaging diagnosis mode, reduce trauma and radiation risks, and have clinical use and popularization values.

Provided herein are methods for preventing conditions related to UV-radiation exposure in subjects at risk for exposure to UV-radiation. In particular, the invention relates to compositions comprising specific formulations of dietary carotenoids (e.g., bixin) which function as activators of NRF2 pathway related activity, and related methods for the protection of mammalian skin against UV-radiation.

The invention discloses a CT imaging system and a CT imaging method. The system includes: an X-ray source, a rotary table, an energy-resolving photon counting-type X-ray detector, and a processor, wherein the rotary table is configured to carry an imaging target, and carries the imaging target to rotate with a rotary table rotating shaft as a rotation center. The X-ray source is used for emittingX-rays to the imaging target; the energy-resolving photon counting-type X-ray detector is electrically connected to the processor for collecting the imaging targets passing through the X-rays, and theprojection data is sent to the processor in the projection data of the at least two energy intervals; the processor is configured to process the received projection data of the at least two energy intervals to generate the CT image of the imaging target. The technical scheme of the system achieves improving the contrast of the CT image and reducing the radiation risk.

The invention discloses an improved 2228 lithologic density logging instrument with exemption sources. The improved 2228 lithologic density logging instrument with the exemption sources comprises a long source distance detector and a short source distance detector. A sheath assembly of the long source distance detector and a sheath assembly of the short source distance detector are each internally provided with a crystal and a photomultiplier. A spring is arranged between each crystal and the top of the corresponding sheath assembly. The exemption sources are arranged on the outer side face, adjacent to the corresponding crystal, of the sheath assembly of the long source distance detector and the outer side face, adjacent to the corresponding crystal, of the sheath assembly of the short source distance detector correspondingly. By additionally arranging the exemption monitoring cesium sources of 0.25 microcuries for the long source distance detector and the short source distance detector, the instrument is free of control from a radioactive source in the using process, the effect that the radiation risk is reduced to the minimum is ensured, and stable operation and reliable technologies of the long source distance detector and the short source distance detector can be achieved.

The invention discloses a method for analyzing the total dose effect generated by an isotope heat source, thereby solving a problem that the total dose-year spectrum generated by gamma rays of an isotope power source cannot be obtained at present. With an established model, a total dose spectrum being a total dose-year relationship generated by gamma rays in actual application can be obtained by backstepping according to specific packaging materials, isotopic nuclear fuel mass, and a distance to the central distance of the isotope nuclear fuel, so that the total dose effect risk of the spacecraft during the whole task period is estimated. The isotope power source is estimated by the model, so that the testing and monitoring of the isotope radioactive fuel are avoided. The method is simpleand is easy to implement; the test expenses and radiation risk are saved; and the method has the certain economic significance and guiding significance in engineering design. According to the invention, the method not only is involved in the isotope power source of nuclear decay but also is suitable for a nuclear reactor source of nuclear fission, thereby realizing evaluation of the total dose effect generated by the nuclear power supply in space nuclear power spacecraft. The method has the certain universality.

The invention relates to a remote intelligent examination system for the radiology department. A voice navigation module is arranged and can intelligently guide a patient to adjust the body posture and position, so that the patient can independently complete X-ray shooting, and the radiation risk of a doctor is reduced; meanwhile, images shot in real time can be displayed during display, so that the patient can visually see the difference between the two images, the shooting speed of the patient is increased, and time is saved; an image comparison module is arranged, and the real-time image and the historical image of the patient are compared, so the optimal shooting parameters are selected, unattended automatic shooting can be achieved, the definition and the contrast ratio of the image are improved, it is guaranteed that the shot image is available, and the radiation risk of an operation doctor is further reduced. A parameter input module is arranged, and it can be guaranteed that the patient entering the shooting and the actually registered patient are the same person; in addition, the parameter input module is arranged outdoors, so that face recognition can be prevented from being affected by radiation.