129 results about "Lead shielding" patented technology

A portable directional gamma ray radiation detector having a plurality of gamma ray radiation detectors separated by lead shielding arranged in an enclosure. Outputs from the detectors are applied to a signal processor to determine the location of a gamma ray emitter, and the signal processor is connected to a display device on the detector that indicates the direction to the gamma ray emitter.

The invention discloses a channel type radioactive detector with a low detection limit, which is used for a channel type radioactive monitoring system. The channel type radioactive detector comprises a shell, a shielding body arranged in the shell, a plastic scintillator, a first photomultiplier, a first preamplifier, a second photomultiplier, a second preamplifier, a signal processing and controlling unit. Two ends of the plastic scintillator are coupled with two photomultipliers through light guides to output two paths of pulse signals. The signal processing and controlling unit is internally provided with an adder circuit and an accordance circuit, which are used for adding two paths of the pulse signals to detect whether the pulse signals accord with requirements. In the invention, through a signal adding and accordance method and the shielding by using a lead shielding body, the cost can be effectively reduced, the noise is reduced, the signal to noise ratio is improved, the detection efficiency and the sensitivity are improved, and the energy detection lower limit is reduced, so that low-energy nuclides can be more effectively detected and measurement requirements are better met.

Provided is a nuclear power plant radioactive exudation monitoring system which comprises an airborne radioactive exudation monitoring system. The airborne radioactive exudation monitoring system comprises a heating unit. The heating unit is used for heating gases in a part, outside a chimney, of a sampling pipeline where an aerosol and iodine monitor in the airborne radioactive exudation monitoring system is located, and a part, outside a chimney, of a sampling pipeline where an aerosol and iodine sampler is located. The nuclear power plant radioactive exudation monitoring system may prevent aerosol and iodine steam condensation caused by a decrease in ambient temperature and may increase aerosol and iodine acquisition efficiency. Further, a compressor is arranged on the upstream of an inert gas sampling bottle so as to increase gas concentration. In a high radioactivity monitoring system, a lead shielding device is arranged outside the inert gas sampling bottle and the aerosol and iodine sampler in order to improve protection of workers against radiation. A liquid radioactive exudation monitoring system is improved, simplified in structure, and decreased in fault links. A flowmeter is provided in order to compute total discharge activity.

The invention relates to the field of radiation measurement and provides an on-line type energy spectrum analysis anti-coincidence measurement detector. The detector comprises a sodium iodide scintillator for recording a gamma ray, a photomultiplier for converting an optical signal of the sodium iodide scintillator into a weak pulse signal, a plastic scintillator for deducting Compton flashing of the sodium iodide scintillator, a silicon photomultiplier for converting an optical signal of the plastic scintillator into a weak pulse signal, a lead shielding body for shielding an environment radiation band alignment hole and a lead plug, and a forward amplifying plate for amplifying the weak signals. The detector can achieve complex environment, Compton flashing and serious background interference always on-line measuring, eliminate the influence of nuclear site Compton flashing on 50keV-1.5MeV middle and low energy section radionuclide analysis measurement, and, at the same time, solve the difficulty that anti-coincidence measurement is unlikely to be achieved on a nuclear site.

The invention discloses an anti-Compton scattering detector, which comprises a main detector made of the sodium iodide material. The lower end of the main detector is connected with a photomultiplier. The main detector is nested into an auxiliary detector compounded of a plastic scintillator. The light guide material is arranged between the main detector and the auxiliary detector. The upper end of the auxiliary detector is connected with the photomultiplier. The lower end of the auxiliary detector is provided with a lead shielding ring. According to the invention, the background influence of natural gamma-ray scattered photons (Compton effect) is reduced to the maximum extent. Meanwhile, the accuracy of the in-situ environment gamma-ray detection result is improved. The structure unit of the detector is simplified and the power consumption of a complete machine is lowered.

The invention belongs to the field of radiation monitoring technology and provides a typical nuclide monitor of fuel element failure. The monitor is realized based on a typical nuclide detection method of fuel element failure and comprises a detection sampling unit and a signal processing unit. The detection sampling unit is composed of a spiral sampling line, a lead shielding body and a detector core body. The signal processing unit comprises a main amplifier, a sampling unit and a host unit. The monitor provided by the invention can carry out quantitative monitoring on typical fission nuclide in a loop coolant by a gamma spectrometry technology, so as to accurately and timely judge whether a fuel element is damaged. The typical nuclide monitor has characteristics of high precision, fast response and good real-time performance, and is simple and easy to use.

The invention discloses a multifunctional insulation instrument withstand voltage test apparatus and a test method, and relates to the technical field of a power system. The apparatus comprises a test platform, four corners of the test platform are detachably provided with height adjustable insulation supports, two pairs of opposite height adjustable insulation supports are each provided with an insulation rod grounding clamping plate, the insulation rod grounding clamping plates are movably connected with the height adjustable insulation supports, the multifunctional insulation instrument withstand voltage test apparatus and test methods are uniformly provided with a plurality of semicircular fixation clamping ports, each semicircular clamping port is provided with a semicircular movable clamping port, and the semicircular movable clamping ports can wrap and wind the semicircular fixation clamping ports and form enclosed circular rings with the semicircular fixation clamping ports; and the other two pairs of opposite height adjustable insulation supports are each provided with a lead shielding cover clamping plate, the lead shielding cover clamping plates and the insulation rod grounding clamping plates are fixedly connected through bolts, and the lead shielding cover clamping plates are uniformly provided with at least two semicircular fixation clamping ports. The apparatus provided by the invention is simple in structure and convenient to operate, can test multiple insulation rods and insulation bars at a time, and is high in test efficiency.

The invention provides a spectrometer for gamma ray imaging, which consists of a uniform redundant array encoding board, a detection module, a front-end signal processing module, an A / D module, a control module, a data interface module, a power supply module, and a lead shielding layer composition. In the lead shielding layer, the uniform redundant array coding board is placed at the front of the detection module; the detection module is connected to the front-end signal processing module through a cable; the A / D module is connected to the front-end signal processing module, and then connected to the control module through a double row of pins The control module is connected to the data interface module through the cable socket; the data interface module is output to the upper PC through Ethernet; the power module processes the input low-voltage DC power of the system and supplies it to each module respectively. The gamma-ray imaging energy spectrometer provided by the invention can be used for both gamma-ray imaging and gamma-ray energy spectrum measurement.

The invention provides an extra-high voltage transformer lead shielding device comprising a first equalizer, a pressure equalizing ball and a second equalizer, wherein one end of the pressure equalizing ball is movably connected with the first equalizer, and the other end is fixedly connected with the second equalizer; parallel leads of the transformer are perforated in the first equalizer, the pressure equalizing ball and the second equalizer; a first equipotential connection line is connected between the pressure equalizing ball and the first equalizer; one segment of the parallel leads of the transformer in the pressure equalizing ball is connected out of the external lead which is educed outside the transformer through a sleeve inserted into the pressure equalizing ball; and a second equipotential connection line is connected between the first equalizer and the parallel lead. The extra-high voltage transformer lead shielding device can improve the magnetic field, is convenient to install and does not stress during pressure installation of the transformer body, thereby improving the safety in the installation process.

The invention relates to an SGS (Segmented Gamma-ray Scanner) and TGS (Tomographic Gamma Scanning) combined measurement device and an optimization method of a collimator. The device comprises a detection system, a lead shielding body, a collimator, a sample measurement platform and a projection shielding body, wherein the detection system is fixed on a measurement rack; a detector is mounted in the lead shielding body; the collimator comprises one out of an SGS collimator module or a TGS collimator module and is mounted on the lead shielding body; the sample measurement platform is arranged between the collimator and the projection shielding body; in a measurement process, a sample is placed on the sample measurement platform; in the measurement process, a TGS collimator and an SGS collimator can be switched; the TGS collimator and the SGS collimator are optimally designed through a Monte Carlo simulation method to determine the shape. The SGS and TGS combined measurement device combines self-measurement requirements of the SGS and the TGS and combines the measurement requirements of the SGS and the TGS through the Monte Carlo simulation method, so as to obtain a combined device meeting the measurement requirements of the SGS and the TGS; the SGS and TGS combined measurement device can be switched between two measurement modes.

The invention belongs to the technical field of measurement of radioactive wastes and discloses a transmission source device. The device comprises a push rod, a lead shielding body and a lead shielding rod and is characterized in that a transmission source is located in a transmission source cavity at the lower part of the lead shielding rod; the bottom of the push rod is fixedly connected with an electromagnet; the lead shielding rod is located rightly below the electromagnet; a push rod motor controls the push rod to move downwards until the push rod is in contact with a stainless steel shell; the electromagnet is electrified to suck the lead shielding rod, and then the push rod motor moves upwards to bring the transmission source to the height of the position of a transmission hole, so that an opening function of the transmission source is realized; after transmission measurement is finished, the push rod motor moves downwards; after the transmission source reaches the position of a closed source shielding block below the transmission hole, the electromagnet is powered off and the lead shielding rod is released; and then the push rod motor is reset upward and a closing function of the transmission source is realized.

The invention discloses a delayed neutron detecting device used for detecting the fuel element rupture which comprises parts such as a detection station, a detector, an amplifier, a processor, a display and an alarming terminal. Each part is connected together by cables, wherein, the detection station is a rectangle, in middle of the rectangular shell thereof, a neutron detector and a detector conduit are positioned; around the detector conduit, a moderation layer aiming at delayed neutrons is arranged and the interior of the detector conduit is provided with a tabular lead shielding for obstructing gamma rays. Aiming at eliminating the disturbance of background neutrons, except the interior towards the core of a reactor, the upside, underside, front-side, back-side and the exterior of the rectangular shell are all provided with the moderation layer and an absorption layer both aiming at the background neutrons. The lead shielding, the moderation layer and the absorption layer are all tabular and can be overlapped to change the thickness, convenient for plugging and pulling and installation and replacement and avoid safety risk brought by the introduction of natrium.

The invention discloses an anti-compton and anti-universe ray high-purity germanium spectrometer, which comprises a lead shielded room, a main detector, an annular anticoincidence detector and a top detector, wherein the main detector, the annular anticoincidence detector and the top detector are arranged in the lead shielded room; the top detector is located at the upper part of the annular anticoincidence detector; a hollow cavity is arranged in the middle of the annular anticoincidence detector; a first hollow cavity for installing the main detector is formed in the lower part of the hollow cavity; and a second hollow cavity for containing a to-be-detected sample is formed in the upper part of the hollow cavity. According to the anti-compton and anti-universe ray high-purity germanium spectrometer, the anti-compton scattering and anti-universe ray functions are achieved at the same time, the radioactive measurement accuracy is further improved, and the lower detection limit is reduced to the maximal extent.

The invention discloses a 18F digital conforming monitoring device and monitoring method, and relates to the technical field of radioactive leakage monitoring of a nuclear power plant. The 18F monitoring device comprises a lead shielding shell, a paper feeding mechanism, a plastic scintillator detector, a NaI detector, a photomultiplier A, a photomultiplier B, a pre-amplifier A, a pre-amplifier B,a main amplifier A, a main amplifier B, a pulse screening forming circuit A, a pulse screening forming circuit B, a high-speed data acquisition card and a computer. The 18F monitoring method is applied to the 18F digital conforming monitoring device. The 18F digital conforming monitoring device can be applied to the leakage monitoring of coolant water at the pressure boundary of the reactor primary circuit of the nuclear power plant, the radioactive activity of 18F mote in a reactor primary circuit containment can be measured on line, whether the reactor has the coolant water leakage or not is judged in real time, and the leakage rate of the coolant water is obtained by calculating.

The invention relates to an automatic shielding lead plate casting device and a shielding lead plate production process, belonging to the field of lead shielding product manufacturing, including a support frame body, a mobile vertical mold and a casting lead pot, the mobile vertical mold is installed on the inside of the support frame body, and the lead casting The pot is connected to one end of the pouring lead pipe, and the other end of the lead pouring pipe stretches into the inside of the movable vertical formwork. The invention has a reasonable structural design, can realize one-time continuous casting in a sealed environment, avoids problems such as faults and slag inclusions, can ensure the quality of the shielding lead plate, can realize efficient and safe production, reduces the labor intensity of the staff, and improves the The production efficiency of the shielding lead plate has strong practicability.

The invention discloses a very low-level transuranium nuclide radioactive waste package detection system, which relates to the technical fields of nuclear facility decommissioning and radioactive waste treatment so as to realize effective detection on a radioactive waste package with the alpha specific activity level not reaching the transuranium nuclide un-confinement standard and reduce the influences of uneven nuclide distribution on a measurement result. The system comprises a lead shielding chamber, a lead shielding cover, a copper shielding layer, a system internal cylindrical support unit, a detector assembly, a digital gamma spectrum acquisition multichannel analyzer and a control system, wherein the detector assembly comprises a NaI scintillator, a NaI matched support frame and aphotomultiplier tube. Low-level and even un-confinement-level radioactive waste monitoring, evaluation, classification and the like can be realized, the system is not limited to high-sensitive detection on 239Pu-containing wastes and can be promoted and used in the technical fields of classification, detection and disposal of nuclear power wastes, the minimum detectable alpha specific activity ofa plutonium-containing waste can reach below 85Bq / kg, and key support can be provided for safe disposal and minimized management of the radioactive waste.

The invention provides a lead shielding structure of a non-detection surface of a scintillant. The scintillant comprises a detection surface, a bottom surface opposite to the detection surface, and four side surfaces. The lead shielding structure comprises a bottom lead plate part which is arranged on the bottom surface of the scintillant, and four side surface lead plate parts which are respectively arranged on four side surfaces of the scintillant; at least one of the five lead plate parts is a stepped lead plate part of which the side edge is provided with an L-shaped step surface; the matching surface between the step surface of the stepped lead plate part and the adjacent lead plate part comprises a right angle plane. The invention also relates to a housing assembly of a scintillant detector, the scintillant detector and a radiation detection device.

The invention relates to the field of radioactive gas analysis, and relates to a rapid high-sensitivity detecting device for radioactive xenon. The device is composed of a radon progeny filter, a needle valve, an air compressor, a buffer tank, a gas source processor, a compressed air flow meter, a pressure sensor, a mass flow controller, a dew-point instrument, a hollow fiber membrane, a regulating valve, a flow meter, a decontamination column, a lead shielding room, an integrated adsorption / measurement sample box and a HPGe detector by mating. The device provided by the invention realizes on-site rapid and high-sensitivity detection of radioactive xenon, and the radon progeny filter effectively removes the radon progeny and dust and realizes self-cleaning function.

The invention relates to a nuclear radiation protective supply and a preparation method of the nuclear radiation protective supply, in particular to a lead shielding block on the end face of a nuclear fuel channel in a heavy water reactor nuclear power station and a preparation method of the lead shielding block. The lead shielding block comprises multiple layers of overlying lead foil, wherein the lead foil is provided with locating holes, the fuel channel is sleeved with the lead shielding block through the locating holes, and silicone rubber layers are arranged on the outer side edges of the multiple layers of overlying lead foil and the inner wall faces of the locating holes. The preparation method of the lead shielding block comprises the steps of preparing the multiple layers of overlying lead foil, wrapping the multiple layers of overlying lead foil with silicone rubber, and conducting compression molding to obtain the lead shielding block. The lead shielding block does not damage the fuel channel and is light in self weight and easy to prepare, install and use.

The invention discloses a medical radioactive rubbish can. The medical radioactive rubbish can is used for achieving the aims of safety storage and safety management on radioactive rubbish generated by using radionuclide in the radioactive treatment process in a hospital. The medical radioactive rubbish can is formed by a plastic inner can body, a lead shielding outer can body, a data measurement module, a display module, a network transmission module and a radio frequency identification module, wherein the plastic inner can body is used for containing the radioactive rubbish, and the lead shielding can body is used for shielding the radioactivity of the rubbish. The specific activity and the surface dose rate of the radioactive rubbish are measured through the data measurement module, the measured data are displayed through the display module, and meanwhile the data are uploaded by the network transmission module into a network database. The radio frequency identification module is used for recording the information of the specific activity and the information of the surface dose rate through radio frequency tags when the radioactive rubbish is transferred to be stored or transferred to be processed. By means of a whole system, the safety storage of the radioactive rubbish and automatic measurement and intelligent monitoring of the specific activity and the surface dose rate of the radioactive rubbish are achieved.

The invention relates to the technical field of cyclotrons, and discloses a cyclotron ionizing radiation self-shielding device of an isotope target system outside a magnet yoke. The device comprises an isotope production target chamber, an accelerator coating layer and a driving device. The accelerator coating layer coats the side and the top of the cyclotron; the accelerator coating layer is divided into a left side shielding body and a right side shielding body which are spliced; the driving device drives the left side shielding body and the right side shielding body to do opposite or reverse linear movement so as to close or open the accelerator coating layer; isotope production target chambers close to the cyclotron magnet yoke are embedded in the inner side surfaces of the left side shielding body and the right side shielding body respectively; cyclotron production targets are located in the isotope production chambers; and each isotope production target chamber is surrounded by alead shield layer and a boron-containing polyethylene shielding layer. The device realizes effective shielding of an ionizing radiation field generated by the cyclotron, thereby improving safety andreliability of medical devices and ensuring safety of workers.

A light emitting diode (LED) shielding and monitoring system includes multiple light emitting diodes (LEDs) (12, 14, 82, 92), multiple optical detectors (20, 84, 94) for detecting a light output of the plurality of LEDs (12, 14, 82, 92), and a LED shield (30, 110) with multiple compartments (38, 114) for receiving the multiple optical detectors (20, 84, 94). The LED shield (30, 110) is configured such that each compartment (38, 114) receives an optical detector (20, 84, 94), and wherein each compartment (38, 114) is configured such that the optical detector (20, 84, 94) within the compartment (38, 114) detects the light output of a LED (12, 14, 82, 92) of the multiple LEDs (12, 14, 82, 92) without detecting light output other than the light output of the LED (12, 14, 82, 92). Further, wayside LED signals including a LED shielding and monitoring system are provided.

The invention discloses an X-ray counting machine. The X-ray counting machine comprises a cabinet, wherein the cabinet is internally provided with a lead shielding room and a controller, wherein the cabinet is provided with a pull device, the pull device is connected with a material box, the lead shielding room is provided with an opening, the material box stretches into the lead shielding room from the opening during work, the lead shielding room is provided with a lifting device capable of moving upwards and downwards, a top portion of the lifting device is provided with an X light ray source, and a bottom portion of the lifting device is provided with a flat imaging device in matching with the X light ray source. The X-ray counting machine is advantaged in that the pull device is employed to realize material incoming and outgoing, the space is not only saved, but also operation is simple and convenient, moreover, the X light ray source and the flat imaging device are arranged on the lifting device, detection amplification multiplying power can be adjusted, detection on materials with different dimensions can be realized, and good versatility is realized.

The invention relates to a reactor internal supporting base with gamma-ray shielding and flow distribution functions, comprising a supporting bottom plate and a supporting top plate, wherein the supporting bottom plate and the supporting top plate are connected by a supporting annular plate provided with a circulation hole; the supporting bottom plate is provided with a pressing groove for installing a lead shielding plate; the supporting top plate is provided with a flow-distribution through hole; the supporting bottom plate is for fixed connection with a pool bottom plate; and the supportingtop plate is for being connected with a reactor internal. The beneficial effects of the present invention are as follows: the base satisfies the requirement of gamma-ray shielding by the shielding plate in the pressing groove, and realizes the flow distribution function through the flow-distribution through hole, and can satisfy the demand of simultaneously considering problems of flow distribution and activation of gamma-rays to the bottom of a pool.

The invention provides a nuclear fuel failure detection device. The device comprises a lead shielding case, a sampling chamber, a gas inlet pipe, an gas outlet pipe, a main detector, a scintillation detector A, a scintillation detector B, a collimator A, a collimator B, a photomultiplier, a pre-amplifier, a linear amplifier, an anticoincidence counting circuit, a gate circuit, an impulse amplitudeanalysis meter, a comprehensive analysis instrument, a data processor and a display screen. A nuclear fuel failure detection method is used in the nuclear fuel failure detection device. By means of the nuclear fuel failure detection device, the concentration of 133 Xe gamma rays in tail gas of a reactor condensation system can be measured on line, and therefore, whether nuclear leakage occurs ornot is judged, and the leakage rate is calculated; the interference of 13N annihilation gamma rays with a measurement result is eliminated through the scintillation detectors and the anticoincidence counting circuit; the interference of Compton trails of the 133 Xe gamma rays with the measurement result is eliminated through the impulse amplitude analysis meter. The measurement result is accurate,reliable and high in precision.

The invention discloses a field X-ray protection method and a protection device thereof. In the invention, the personnel safety is protected by spacing an infrared warning light and a warning line from the public personnel at a safe distance and equipping the ray operator with a lead shielding cover protection device. The invention has the beneficial effects that: (1) in the invention, the safe distance for common public personnel is calculated under different X-ray radiation intensities, and protection measures are arranged outside the safe protection distance so that dose received by the public personnel is controlled within a safe range; and 2) a plastic shielding cover capable of containing lead plates with different thicknesses is designed. When the shielding cover is used, the ray operator hides behind the shielding cover and thus is effectively protected.

The invention provides an anti-Compton and anti-cosmic-ray high purity germanium spectrometer comprising a lead shielding room and a main detector, a ring detector and a coincidence detector which areinstalled in the lead shielding room. The coincidence detector is arranged above the main detector. The ring detector is a BGO scintillator detector. The middle part of the ring detector is providedwith a cavity. A first installing cavity used for installing the coincidence detector is formed on the upper part of the cavity. A third installing cavity used for installing the main detector is formed on the lower part of the cavity. A second installing cavity used for placing the sample to be detected is formed in the middle part of the cavity. The BGO scintillator detector is used as the ringdetector so that the size is small and the ray detection efficiency is excellent. The ring detector, the coincidence detector and the main detector are arranged on the lower part of the lead shieldingroom, the coincidence detector and the main detector are installed on the upper and lower ends of the middle cavity of the ring detector respectively, and the second installing cavity used for placing the sample to be detected is arranged between the coincidence detector and the main detector so that the arrangement space of the detectors is compact and the size can be reduced.