1229 results about "Nuclear radiation" patented technology

A nuclear radiation detector included inside mobile personal communication devices (e.g. cellular or satellite phone, pager, PDA) allows for a network of portable radiation detectors that can not only detect radiation, but also track possible radiation sources by virtue of the ubiquitous nature of such personal communication devices. When radiation levels above a certain level are detected, the detector electronics embedded within any proximate mobile personal communication device communicates with the device to cause transmission of relevant data to the authorities (e.g., central reporting server monitored by FBI). The detection event is assessed by factors including, for example, quantity of alarms in a given area and radiation level detected. The small size of this embedded detector allow for its discreet configuration and monitoring at all times. The device is non-invasive and requires no user knowledge or action, thus eliminating indiscriminate and uncontrolled action by the user.

The invention relates to an automatic separator of coal gangue, which comprises a raw material feeding copper, a coal receiving copper, a gangue receiving copper, a conveying-belt conveyor, an identification and separation controlling mechanism and an executing mechanism, wherein the conveying-belt conveyer is arranged among the raw material feeding copper, the coal receiving copper and the gangue receiving copper; the identification and separation controlling mechanism comprises a single-energy gamma ray source, an X-ray sensor, a measure and control instrument and an ultrasonic transmitter-receiver; the single-energy gamma ray source is arranged below a conveying belt, the X-ray sensor is arranged above the conveying belt and corresponds to the single-energy gamma ray source, the measure and control instrument is electrically connected with the X-ray sensor, and the ultrasonic transmitter-receiver is arranged above the conveying belt and electrically connected with the measure and control instrument; the executing mechanism is a high-frequency air valve arranged above the coal receiving copper and the gangue receiving copper; and the valve port of the high-frequency air valve isarranged towards a throwing track of coal and gangue. As the single-energy gamma ray source is adopted, only one nuclear radiation material exists, and only one spectral line is radiated, the mutualinterference among a plurality of spectral lines can not be generated; and the invention has accurate measurement and good separation effect.

The invention belongs to the field of special equipment for nuclear industries, and in particular relates to an emergency treatment and rescue robot which can be used for a nuclear radiation environment. The robot consists of a walking base plate, a mechanical arm, a robot body motion control system, a robot redundancy navigation control system, a gamma camera, a holder, a gamma ray imaging system, a battery and a controller, wherein the walking base plate has a crawler-type structure; a motor is arranged in the middle of the base plate and is used for driving a crawler belt to operate through a chain; the mechanical arm is arranged at the front end of the base plate and has four degree of freedom; the gamma camera and the imaging system are positioned on the rear part of the robot and are arranged above the battery; and the gamma camera can be used for detecting the intensity and the direction of radiation and the robot can perform emergency treatment through the mechanical arm of the robot.

The invention relates to a composite shielding material and a preparation method thereof, in particular to the composite shielding material applied to nuclear radiation places such as nuclear reactor, spent fuel assembly storage and radioactive substance storage and transportation and the like. The composite shielding material is characterized by comprising the following components in percentage by weight: 0 to 30 percent of w and compound thereof, 0 to 70 percent of B4C, 0 to 90 percent of aluminum or aluminum alloy, 0 to 8 percent of other elements and the like. The composite shielding material comprising tungsten B4C/aluminum alloy is uniform in distribution of W2B5 and B4C, high in densification degree, high in strength and toughness, and particularly applicable to the field of neutron/gamma ray shielding.

The invention relates in a one aspect to a method or apparatus for measuring flow properties of a multiphase fluid stream flowing in a pipeline comprising means for sampling, with a sampling probe, a portion of the fluid stream; for measuring a differential pressure between a first pressure of the fluid stream in the pipeline and a second pressure of the portion of the fluid stream in the sampling probe; for controlling flow rate of the sampled portion, wherein the flow rate of the sampled portion is controlled to provide for nullification of the differential pressure in order to obtain substantially isokinetic sampling of the fluid stream; for measuring properties of the portion of the fluid stream; and for processing the measured properties to determine the flow properties of the multiphase fluid stream flowing in the pipeline, wherein the above elements do not require- or are performed without the determination of the density of fluid in the fluid stream through nuclear radiation methods.

An inflatable sheet includes an optical fiber extending across at least a portion of its surface to detect a breach or nuclear radiation. The sheet can line at least a portion of a container or several such sheets can line several walls of the container. A breach of the sheet or radiation within or near the sheet reduces optical transmissibility of the fiber. The fiber integrates the radiation over time and/or over the length and volumetric mass of the fiber, making the fiber sensitive to even low-level radiation. The optical fiber is monitored for a change in its transmissibility. A reduction in the transmissibility, such as to below a threshold, can trigger an alarm, such as an annunciator, a self-destruct circuit or send a message that includes information about the time or the container's contents or location when the breach or radiation is detected to a central location, such as a ship's control room or port notification system.

The invention provides a local dry-method underwater welding robot based on an ROV. The local dry-method underwater welding robot comprises the ROV and a welding mechanical arm installed on the ROV. The ROV comprises a frame, a vertical auxiliary thruster, a vertical main thruster and a horizontal thruster, wherein the vertical auxiliary thruster, the vertical main thruster and the horizontal thruster are installed on the frame, the upper portion of the frame is provided with buoyancy materials, the middle portion of the frame is provided with an electronic device sealed cabin and a welding device sealed cabin, the front of the frame is provided with an imaging sonar and an underwater lighting device, the two sides of the frame are provided with camera systems, and the bottom of the frame is provided with a pipeline fixing claw, a hydraulic pile leg and an underground hydraulic pump. The ROV is connected with a water surface control system on a mother ship through a funicle cable. The front portion of the welding mechanical arm is provided with a local dry-method arc welding gun and a weld tracker. The local dry-method underwater welding robot is high in working efficiency, large in working depth, good in underground welding flexibility and especially suitable for being used in the nuclear radiation or poisonous and harmful underwater, the atmospheric environment or in the site where workers cannot arrive at.

The present invention discloses the preparation process of irradiation resistant low smoke no-halogen fire retarding ethylene-propylene rubber as cable material. The preparation process includes heating and mixing ethylene-propylene rubber, aluminum hydroxide, silicone as fire retarding synergist, lead compound, antiager, copper resisting agent, gamma ray absorbent, liquid peroxide vulcalizer and phenolic heat stabilizer in a banbury mixer; and air cooled pelletizing in a double screw extruder. Thus prepared cable material has volume resistivity higher than 2x1015 Ohm.cm, heat life over 90 deg.c x 50 year, accumulated gamma ray resistance of 220 Mrad and radiation dosage rate resistance lower than 1Mrad/h, and is suitable for producing cable insulation layer for use in high nuclear radiation environment.

The invention belongs to the technical field of nuclear radiation detection and nuclear electronics, and relates to a nuclear radiation pulse accumulation signal judging and correcting method based on high-speed digital sampling. The method includes the steps of pulse accumulation judgment and pulse accumulation correction and specifically includes the steps of judging pulse accumulation, conducting differential on signals, judging the accumulation type, correcting pulse accumulation, calculating pulse waveform parameters, conducting cutting and correcting accumulated pulses. Compared with the prior art, the method has the advantages that the digitalization method of pulse accumulation judgment is set up, complex hardware equipment in a traditional spectrometer is abandoned, differential and analysis are conducted on collected output pulses through the digitalization method so that the current changes of the pulses can be formed, the method is simple and clear, the physical meaning is clear, the accumulation type can be accurately judged, the correction of pulse accumulation can be conducted, the use ratio of the signals can be effectively improved, energy resolution losses caused by pulse accumulation can be reduced, and meanwhile the pulse passing rate of a system is improved to the largest extent.

The present invention relates to a method of applying a pattern recognition method to a digital spectrometer to carry out nuclide rapid identification. The method comprises the steps of using the digital spectrometer to carry out real-time acquisition and data pre-processing on a nuclear radiation pulse signal, and selecting the characteristic energy ray and the area increase ratio of the characteristic energy peak of a correlated nuclide as the needed characteristic information, wherein the characteristic energy ray can be used as the main characteristic to identify the existence of the nuclide, and the area increase ratio of the characteristic energy peak is used as the auxiliary characteristic to be used as the criterion of the parallel analysis of a multi-ray nuclide. The advantages of the present invention are that: the area increase ratio of the characteristic energy peak of the nuclide substitutes the operation in the conventional method of selecting the full-energy peak area of the characteristic ray of the nuclide as the basis of identifying the existence of the nuclide, so that the identification of the nuclide is not interfered by the full-energy peak counting area of the characteristic ray of the nuclide accumulated in the early stage, and the identification reliability of the nuclide is improved; the characteristic extraction process maps an input pattern from the object space to the characteristic space, so that the quantity of information is compressed, the identification and judgement are easy, and the identification speed and efficiency of the nuclide are improved.

The invention discloses a radioactive source positioning method and system. The method includes the steps: setting initialization; performing nuclear radiation detection for radiation sources at a plurality of detection points by the aid of a plurality of mobile communication terminals; acquiring nuclear radiation dose information, position information and time information of the detection points; judging whether to give an alarm or not and whether the radiation sources move or not according to the nuclear radiation dose information; respectively positioning the fixed radiation sources and the movable radiation sources. Portable functions such as radioactivity detection and analysis are integrated into the mobile communication terminals which are separated from traditional professional devices based on electronic tags, robots and the like, the radiation sources are positioned in a cost-effective manner through a man-machine fusion method in a group environment, and the radioactive source positioning method is low in cost, wide in detection range and convenient to popularize.

The invention relates to a dual-detector segmenting gamma-scanning measuring device based on equivalent radius correction, belonging to the technical field of nuclear radiation measurement. The dual-detector segmenting gamma-scanning measuring device comprises a rotary table, a detector platform assembly, a transmission source platform assembly, a platform lifting and driving assembly, two same high-purity germanium detectors, a transmission source, a shielding part of the transmission source and an analysis module, wherein the two same high-purity germanium detectors are provided with collimators. In the invention, the influence of the nonuniformity of materials inside a wastebin is reduced through the constant rotation of the wastebin, layered measurement is carried out on the wastebin undergoing the constant rotation by placing the two same high-purity germanium detectors on different horizontal positions, the radial equivalent radius of each radionuclide layer is obtained through analysis, and the radionuclide activity of the radionuclide layer is accurately computed according to the detection efficient of the radial equivalent radius. Because an assumption of uniform radionuclide distribution is eliminated, the characteristics of an actual wastebin are better accorded with so that the measurement accuracy of the traditional segmenting gamma-scanning technology is greatly enhanced.

The invention discloses a method for displaying the evaluation data of a nuclear radiation aftermath. A radioactive release source item is analyzed and calculated according to the state of the power plant of a nuclear power station, an accident aftermath which is possibly generated after an accident occurs to the nuclear power station is forecasted and calculated according to a quick evaluation mode, a single-module mode and a fine evaluation mode, and the calculated aftermath evaluation result is written into a text file; then, these text data are respectively classified according to three modes of the quick evaluation mode, the single-module mode and the fine evaluation mode, are written on a corresponding grid chart layer of a selected mode by selecting and switching at least one mode in the three modes and are represented in the form of arrowheads with different colors and/or changes. The invention combines the parameter information of the geography, the population, the weather and the like around the nuclear power station and intuitively reflects the aftermath which is possibly caused after the accident occurs to the nuclear power station.

The invention provides an autonomous planning method for a nuclear radiation detection path of a mobile robot in an unfamiliar indoor scene, which is applied to the mobile robot. A speedometer, an acceleration sensor, a laser ranging radar, a camera, a radiation detector and a computer are carried on the mobile robot; and the speedometer, the acceleration sensor, the laser ranging radar, the camera and the radiation detector are electrically connected or in communication connection with the computer respectively. The autonomous planning method for the nuclear radiation detection path comprises: S01, obtaining an environmental map; S02, generating a global path planning; and S03, correcting the global path planning through local path planning.

The invention discloses a radiation detection aircraft, which belongs to the technical field of radiation detection, and aims at solving the problem that an existing robot for nuclear radiation detection is poor in capacity for emergency management. A camera is arranged on a flying front-end shell of a four-rotor aircraft carrier; a nuclear detector is mounted at the lower end of the shell of the four-rotor aircraft carrier; a global position system (GPS) locator is used for locating the flying position of the four-rotor aircraft carrier; a detected signal output end of the nuclear detector is connected with a detected signal input end of a signal conditioning circuit; an imaging signal output end of the camera is connected with an imaging signal input end of the signal conditioning circuit; a locating signal output end of the GPS locator is connected with a locating signal input end of the signal conditioning circuit; a conditioning signal output by the signal conditioning circuit is transmitted through a wireless general packet radio service (GPRS) data transmission unit. The radiation detection aircraft is applied to nuclear radiation detection.

This invention relates to the field of radiation imaging. In particular, the invention relates to an apparatus and a method for imaging tissue or an inanimate object using a novel probe that has an integrated solid-state semiconductor detector and complete readout electronics circuitry.

The invention belongs to robot equipment used for a nuclear power plant, and particularly relates to a multifunctional actuator for nuclear power plant operation and a control method thereof. An actuating mechanism consists of a base, a three-joint five-degree of freedom mechanical arm, a square claw plate and four switchable mechanical hands arranged on the claw plate; and a plurality of cameras and sensors are arranged on the actuating mechanism; and with the adoption of the sensors and a control system, switching, locking and positioning operations of the four mechanical hands and obstacle avoidance and action planning of the mechanical arm can be realized. The actuator can realize integral operation of various high-risk tasks such as search, pollution discharge, recycling, and equipment maintenance of objects under nuclear radiation environment, thereby realizing intelligent autonomous operation under the nuclear environment.

The invention relates to the technical field of preparation of nuclear radiation shielding materials, especially to a flexible shielding material which is used for shield radioactive parts of a nuclear power station. The shielding material is of a laminate structure and comprises a shielding function layer and protective layers arranged at two sides of the shielding function layer, wherein the shielding function layer is a compounded layer which utilizes irradiation-resistant rubber as a matrix material, absorption neutrons and gamma-ray metal powder are added in the matrix material, and the protective layers are rubber layers. The flexible shielding material is of a sandwich structure, can be applied on the occasion that a traditional radiation protection material cannot be used or is difficult to install, is convenient in on-site installation and later cleaning in a nuclear power station, does not suffer from creep deformation and flowing as a foreplate, can be repeatedly used for a long time and is environment-friendlier and more economic. Moreover, the invention also relates to a preparation method for the flexible shielding material.

The invention discloses a real-time 3D nuclear radiation environment reconstruction monitoring system which is used for establishing 3D nuclear radiation dose distribution of a monitored nuclear radiation environment in real time. The system is characterized by establishing a realistic 3D environment model possessing of the monitored nuclear radiation environment under a reference coordinate system; through a nuclear radiation sensor loaded by a mobile robot, collecting nuclear radiation dose data of different space position of the monitored nuclear radiation environment under the reference coordinate system and using the nuclear radiation dose data to establish a nuclear radiation dose model of the monitored nuclear radiation environment under the reference coordinate system; carrying out point-to-point data fusion on the nuclear radiation dose model of the monitored nuclear radiation environment and the 3D environment model so as to establish 3D nuclear radiation dose distribution of the monitored nuclear radiation environment. By using the monitoring system, 3D space distribution of real-time reconstruction radiation dose is realized; visualization is possessed so that work personnel can know a nuclear radiation condition of each position in the monitored nuclear radiation environment.

The invention discloses a nuclear radiation environment automatic sampling mechanical vehicle, comprising a chassis (1), a manipulator (2) and a travelling mechanism (3); the travelling mechanism (3) is connected with two side edges of the chassis (1) by means of a bearing plate (8), the upper surface of the chassis (1) is connected with the manipulator (2), an electronic part and component shielding box (5) and a rear camera (6), the electronic part and component shielding box (5) is connected with a cable (7), the upper surface of the chassis (1) is connected with a radioactive substance containing shielding box (4), and the radioactive substance containing shielding box (4) comprises a shell (41), a pressure sensor (42) and a slip cover (43); the slip cover (43) and the shell (41) are connected by adopting a linear sliding rail, and one end of the slip cover (43) is provided with the pressure sensor (42). The nuclear radiation environment automatic sampling mechanical vehicle has the advantages of higher radiation resistance, environment adaptation and obstacle crossing performance.

The invention discloses a teleoperation-device-based virtual reconstruction system and a teleoperation-device-based virtual reconstruction for a nuclear radiation environment. The virtual reconstruction system for the nuclear radiation environment comprises a front-end subsystem arranged on a mobile device, wherein the front-end subsystem is connected with a background subsystem through a communication cable. The virtual reconstruction system for the nuclear radiation environment acquires the information of the nuclear radiation environment through positioning measurement equipment, gamma image acquisition equipment and a gamma spectrometer, which are arranged on the front-end subsystem, and transmits the information of the nuclear radiation environment to the background subsystem for processing through the communication cable by front-end communication equipment to create a virtual scene of the nuclear radiation environment. A nuclear radiation environment field can be measured in real time, the virtual scene can be reconstructed on line, and nuclear radiation environment measurement and nuclear radiation environment reconstruction are integrated, so that reconstruction efficiency is improved; and a three-dimensional model of a radiation source and the attribute of the radiation source are associated, so that rich visual information can be provided for staff, the working hours of the staff in a radiation field are reduced, and the nuclear radiation level of the staff can be reduced as much as possible.