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33 results about "Fission chamber" patented technology

UV-VOC waste gas treatment device

InactiveCN103505990ARealize purificationFull oxidative fission dischargeCombination devicesFiltrationControl system
The invention relates to a UV-VOC waste gas treatment device. The device comprises a box body, wherein a photolysis oxidization fission chamber is arranged in the box body, and is connected with a waste gas inlet through a pipeline; a high pressure exciting device is arranged in the photolysis oxidization fission chamber for cracking and decomposing organic waste gas; a control system is further arranged on the box body, comprises a main controller, a negative pressure sensor and a photoelectric sensor, and realizes the control of whole operation and safety of the device. The UV-VOC waste gas treatment device effectively achieves the purification treatment of the waste gas through the photolysis oxidization fission chamber, and fully oxidizes, cracks and discharges the organic waste gas, so that pollution is nonsexist; the filtration and the separation of the waste gas are achieved through pretreatment, as a result, conditions of a subsequent photolysis oxidization fission treatment system treating the waste gas are created; the application of a water circulating system exponentially prolongs the service life of the photolysis oxidization fission device treatment system.
Owner:HANGZHOU HENGYU ENVIRONMENTAL PROTECTION TECH

Nuclear instrument system for nuclear power station and positioning method thereof

The invention relates to a nuclear instrument system for a nuclear power station and a positioning method thereof. The nuclear instrument system comprises a source range channel, a middle range channel and a power range channel, wherein each channel comprises a detector arranged on the periphery of a pressure vessel; the detectors of the power range channel and the middle range channel respectively comprise a plurality of fission chambers; the plurality of fission chambers are shared by the detectors of the power range channel and the middle range channel. The fission chambers are selected as some detectors of the nuclear instrument system, so that the anti-gamma radiating capacity, anti-noise capability and anti-electromagnetic interference property are high; the fission chambers are shared, so that the quantity of the detectors is reduced and the subsequent mounting positioning workload of the detectors is reduced; furthermore, the redundancy of some channels is increased and the system reliability is promoted; 'bucket type' mounting is adopted, so that the detectors can be conveniently mounted and taken out and the staff is prevented from high irradiation; a cable connecting plate is mounted at a hoisting port of an operation platform and is away from a reactor core, so that the transmission signal is difficult to be interfered and influenced by the reactor core environment.
Owner:中广核工程有限公司 +1

Neutron flux and energy spectrum measuring system of helium cooling solid multiplication agent tritium producing cladding

The invention relates to fusion reactor tritium generating cladding neutron measuring. Helium cooling solid breeding agent tritium generating cladding neutron flux and spectrometry measuring system includes packaging foil pneumatic transmitting activation analysis subsystem which includes activation foil and pneumatic transmitting device. The activation foil is set in the measuring tube connected with operating station through cooling layer and biological shielding layer. The operating station is set helium cooling circuit and connected with helium gas dynamic force union station and HPGe measuring station connected with electronics and data gaining system. The solid breeding agent tritium generating cladding is also set micro-fission chamber combination detector and natural diamond neutron energy spectrum detector which are connected with operating station through current sensitive preamplifier and charge sensitive preamplifier, which is connected with electronics and data gaining system.
Owner:SOUTHWESTERN INST OF PHYSICS

Fission chamber output signal digital processing system and method

The invention discloses a fission chamber output signal digital processing system and a method thereof, relates to the technical field of nuclear reactor. The system contains a preamplifier circuit and a digital processing device, wherein the digital processing device contains a signal processing unit, a high-speed analog signal acquisition unit and a signal output unit. The high-speed analog signal acquisition unit is respectively connected with the preamplifier circuit and the signal processing unit and is used for acquiring an output signal of the preamplifier circuit and converting the output signal into a digital signal for outputting. The signal processing unit is connected with the high-speed analog signal acquisition unit and is used for determining the root-mean-square value of the digital signal acquiring neutron flux according to the root-mean-square value and a calibration coefficient of preset neutron flux measuring range. According to the invention, circuit is simplified, problems such as temperature drift of components and noise in the analogue processing circuit are avoided, precision of the measurement result is raised, and stability of the system is increased.
Owner:CHINERGY CO LTD

238 U fission ionization chamber for measuring 20MeV energy zone neutron fluence rate

The invention discloses a <238>U fission chamber used for measuring the neutron fluence rate of a 20MeV energy region. The invention takes the shape of a cylinder and comprises a shell (1) which is provided with an air inlet (2) and an air outlet (3), a bottom liner (5) which is electroplated with a <238>U sample (8), and a collector (6), wherein, the bottom liner (5) and the collector (6) are fixed inside the shell (1) through a strut (7); the bottom liner (5) is connected with the shell (1) and is taken as a cathode; the collector (6) is taken as an anode; signals which are collected by the collector (6) are transmitted by a signal output plug (9); the bottom liner (5) is made of stainless steels. The invention provides the <238>U fission chamber used for measuring the neutron fluence rate of the 20MeV energy region, along with a simple structure, low cost and capability of being conveniently modulated according to measuring requirements.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY

Nuclear instrumentation system and method for locating the same

A nuclear instrumentation system and method for locating the same are disclosed. The nuclear instrumentation system includes a source range channel, an intermediate range channel and a power range channel, wherein each channel includes one detector installed around the pressure vessel, the detectors of the power range channel and the intermediate range channel both include several fission chambers, the detectors of the intermediate range channel and power range channel share several fission chambers. Some detectors employ fission chambers, so the Gamma radiation resistance property, anti-noise property and anti-electromagnetic interference property are improved. Sharing fission chambers reduces the number of detectors to be installed, thus relieving the workload of the installation and positioning of the follow-up detector. Further, the present application increases the number of some channels, which increases the redundancy, improves system reliability.
Owner:CHINA NUCLEAR POWER ENG CO LTD +1

Fission chamber based on Micromegas

The invention discloses a fission chamber based on Micromegas. The fission chamber comprises a Micromega detector, wherein the Micromega detector is provided with a metal shell, and a drift electrode, a Micromega microgrid and a collecting electrode which are arranged in the metal shell; the Micromega microgrid is arranged between the drift electrode and the collecting electrode; the collecting electrode is electrically connected with a pulse signal acquisition circuit; a drift region is formed between the Micromega microgrid and the drift electrode; a collection region is formed between theMicromega microgrid and the collecting electrode; a gas chamber is defined by the metal shell, the drift electrode and the collecting electrode, and flowing ionized gas is arranged in the gas chamber;and a uranium-235 layer is arranged on the drift electrode. The fission chamber is high in sensitivity and high in counting rate range, and neutron fluence rate monitoring full coverage of a reactorfrom physical starting to full-power operation in a single pulse mode is expected to be achieved; the fission chamber has better anti-interference capability and stronger n / gamma discrimination capability, and is especially suitable for real-time monitoring of the neutron fluence rate of a reactor and other strong electromagnetic interference and strong gamma radiation field environments.
Owner:NANHUA UNIV

Count rate measurement device and associated fission chamber calibration device

A fission chamber count rate measurement device and to the associated fission chamber calibration device; the count rate measurement device comprises: (1) a measurement cell, which contains the fission chamber (CH); (2) a neutron generator, which emits neutrons in the form of periodic pulses towards the fission chamber; (3) a neutron counter (K), which detects and counts the neutrons emitted by the neutron generator; and (4) a computing circuit, which delivers, over a predetermined time interval, a fission chamber count rate normalized with reference to the number of neutrons counted by the neutron counter (K).
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES

In-reactor neutron detector assembly for passive starting of nuclear power plant

The invention discloses an in-reactor neutron detector assembly for passive starting of a nuclear power plant, relates to the field of passive starting in-reactor neutron detectors, and solves the problem of primary neutron source monitoring. The device comprises a detector assembly penetrating through a top cover of the pressure vessel, wherein the detector assembly comprises a core body (6), thecore body (6) comprises a plurality of fission chambers (4) sensitive to neutrons, and the fission chambers (4) are located at an active section of a reactor core. According to the invention, the nuclear power plant can cancel a neutron source for the first time in the reactor core loading and critical reaching process, the whole reactor core state is monitored by monitoring neutrons generated byspontaneous fission of the new fuel assembly, and the safety of the nuclear reactor is ensured.
Owner:NUCLEAR POWER INSTITUTE OF CHINA

Probe protection device and high-temperature fission chamber with same

The invention provides a probe protection device which comprises an outer sleeve and an elastic structure arranged in the outer sleeve. The outer sleeve comprises an outer sleeve, a suspension device connecting ring and a sealing bottom, and the suspension device connecting ring and the sealing bottom are packaged at the upper end and the lower end of the outer sleeve. The elastic structure comprises a first ring body, a second ring body and a spring, and a probe is arranged in the outer sleeve. The first ring body is arranged between the probe and the suspension device connecting ring, the second ring body is arranged between the probe and the sealing bottom; the spring is clamped between the second ring body and the sealing bottom, and the spring clamps the second ring body, the probe and the first ring body and has elastic restoring force. The invention further provides a high-temperature fission chamber. The high-temperature fission chamber comprises the probe protection device. According to the probe protection device, due to the elastic structure and the insulation design, elastic buffering and good insulation between the probe and the outer sleeve can be formed, and the damage resistance and the detection capacity of the probe are enhanced.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY

238 U fission ionization chamber for measuring 20MeV energy zone neutron fluence rate

The invention discloses a <238>U fission chamber used for measuring the neutron fluence rate of a 20MeV energy region. The invention takes the shape of a cylinder and comprises a shell (1) which is provided with an air inlet (2) and an air outlet (3), a bottom liner (5) which is electroplated with a <238>U sample (8), and a collector (6), wherein, the bottom liner (5) and the collector (6) are fixed inside the shell (1) through a strut (7); the bottom liner (5) is connected with the shell (1) and is taken as a cathode; the collector (6) is taken as an anode; signals which are collected by thecollector (6) are transmitted by a signal output plug (9); the bottom liner (5) is made of stainless steels. The invention provides the <238>U fission chamber used for measuring the neutron fluence rate of the 20MeV energy region, along with a simple structure, low cost and capability of being conveniently modulated according to measuring requirements.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY

Wide dynamic range neutron flux measuring system and method based on Pulse-Current mode

The invention discloses a wide dynamic range neutron flux measuring system and method based on a Pulse-Current mode. The system comprises a fission chamber, a reference chamber, a Pulse module, a Current module, a postprocessing module and a mode selection mode. The invention further discloses a wide dynamic range neutron flux measuring method based on the Pulse-Current mode. According to the system and method, the contradiction between background radial inhibition capacity and the requirement for the signal to noise ratio in a traditional wide dynamic range neutron flux measuring process is eliminated.
Owner:UNIV OF SCI & TECH OF CHINA

GEM-based fission chamber

The invention discloses a GEM-based fission chamber, comprising a GEM detector, wherein the GEM detector is provided with a metal shell, a drift electrode, a GEM film and a collecting electrode; the drift electrode, the GEM film and the collecting electrode are arranged in the metal shell; the GEM film is arranged between the drift electrode and the collecting electrode; the drift electrode, a GEMfilm upper surface layer electrode and a GEM film lower surface layer electrode are externally applied with negative voltages which are gradually reduced in absolute values; the collecting electrodeis grounded and is electrically connected with a pulse signal acquisition circuit; a drift region is formed between the GEM film and the drift electrode, and a collection region is formed between theGEM film and the collection electrode; a gas chamber is defined by the metal shell, the drift electrode and the collecting electrode, and flowing ionized gas is arranged in the gas chamber; a plurality of aluminum plates are arranged in the drift region; each aluminum plate is vertical to the drift electrode, and one side of each aluminum plate is fixedly connected with the drift electrode; and uranium-235 layers are arranged on the two side faces of each aluminum plate. The fission chamber of the invention has the advantages of high detection efficiency, high sensitivity and high counting rate range, and is expected to meet the wide-range monitoring requirement of the neutron flux density of the reactor in a single pulse mode.
Owner:NANHUA UNIV

A portable neutron detector signal dynamic simulation device

The invention provides a portable neutron detector signal dynamic simulation device. The device comprises a back plate and a man-machine interaction module, a boron proportional counter tube detector signal simulation module, a compensated ionization chamber detector signal simulation module, a long ionization chamber detector signal simulation module, a fission chamber detector signal simulation module, an analog quantity module, a digital quantity module and a control communication module which are connected and communicated through the back plate, wherein the man-machine interaction module acquires data input by a user and distributes the data to the boron proportional counter tube detector signal simulation module, the compensated ionization chamber detector signal simulation module, the long ionization chamber detector signal simulation module, the fission chamber detector signal simulation module, the analog quantity module and the digital quantity module through the control communication module and the back plate to generate corresponding simulation signals. By the device, RPN neutron detector output signals and RPN-associated external system output signals are simulated, and a technical means is provided for the equipment debugging, logic function checking and fault detection of an RPN system.
Owner:LINGDONG NUCLEAR POWER +3

A calibrating device for a thermal neutron fluence rate in silicon single crystal irradiation channel in a nuclear reactor

The invention relates to a calibrating device for a thermal neutron fluence rate in silicon single crystal irradiation channel in a nuclear reactor. The device comprises an aluminum cylinder. One end of the aluminum cylinder is provided with a pedestal and the other end is provided with a top cover. The middle of the top cover is provided with a through hole. A silicon single crystal rod is disposed in the aluminum cylinder, and is provided with a circular hole at the axis. The opening end of the circular hole faces the through hole. A sensitive segment of a miniature fission chamber is inserted into the bottom of the circular hole. The miniature fission chamber is sleeved with a fixing tube. A lifting head is connected to the top cover with a joint pin. The joint pin is provided with a through hole I at the axial direction and matching the through hole in the top cover. According to the device, the miniature fission chamber and the silicon single crystal rod are combined by an ingenious manner, so that the environment and conditions during silicon irradiation are stimulated, and state differences between a measuring method and silicone to be irradiated are eliminated. The thermal neutron fluence rate in the silicon irradiation channel can be measured timely and accurately by lifting the device to a part to be measured of the irradiation channel. The device can be directly used for irradiation production.
Owner:NUCLEAR POWER INSTITUTE OF CHINA

GEM-based fission chamber

The invention discloses a GEM-based fission chamber, comprising a GEM detector, wherein the GEM detector is provided with a metal shell, a drift electrode, a GEM film and a collecting electrode; the drift electrode, the GEM film and the collecting electrode are arranged in the metal shell; the GEM film is arranged between the drift electrode and the collecting electrode; the drift electrode, a GEMfilm upper-surface layer electrode and a GEM film lower-surface layer electrode are externally applied with negative voltages which are gradually reduced in absolute values; the collecting electrodeis grounded and is electrically connected with a pulse signal acquisition circuit; a drift region is formed between the GEM film and the drift electrode, and a collection region is formed between theGEM film and the collection electrode; a gas chamber is defined by the metal shell, the drift electrode and the collecting electrode, and flowing ionized gas is arranged in the gas chamber; and a uranium-235 layer is arranged on the drift electrode. The GEM-based fission chamber is high in sensitivity and high in counting rate range, and the requirement for wide-range monitoring of the neutron flux density of the reactor is met in a single-pulse mode.
Owner:NANHUA UNIV

Welding method for air exhaust adapter and air exhaust pipe of miniature fission chamber

The invention provides a welding method for an air exhaust adapter and an air exhaust pipe of a miniature fission chamber, aiming at solving the problems that the size of the air exhaust adapter and the air exhaust pipe of the miniature fission chamber is small, the welding end face is narrow, the test welding space is small, the wall of a to-be-welded part is thin, penetration welding and penetration welding are easy, obvious deformation is easy to occur after welding, and subsequent assembly and leak rate test cannot be ensured. The method comprises the following steps of testing the welding depth, determining welding parameters, assembling a to-be-welded part to ensure a gap of a to-be-welded end face, carrying out laser welding with the circumference not smaller than 360 degrees, and carrying out leak detection on a welding spot. By means of the welding method, it is guaranteed that over-welding, weld penetration and deformation do not occur to the air exhaust adapter and the air exhaust pipe under the miniature size, the problems that the welding assembly difficulty of the air exhaust adapter and the air exhaust pipe is large and the like are solved, it is guaranteed that the air leakage rate of welding spots meets the design requirement, the neutron fluence rate is accurately measured, and miniaturization and localization of the fission chamber are achieved.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF

Count rate measurement device and associated fission chamber calibration device

A fission chamber count rate measurement device and to the associated fission chamber calibration device; the count rate measurement device comprises: (1) a measurement cell, which contains the fission chamber (CH); (2) a neutron generator, which emits neutrons in the form of periodic pulses towards the fission chamber; (3) a neutron counter (K), which detects and counts the neutrons emitted by the neutron generator; and (4) a computing circuit, which delivers, over a predetermined time interval, a fission chamber count rate normalized with reference to the number of neutrons counted by the neutron counter (K).
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES

uv-voc exhaust gas treatment device

InactiveCN103505990BRealize purificationFull oxidative fission dischargeCombination devicesFiltrationControl system
The invention relates to a UV-VOC waste gas treatment device. The device comprises a box body, wherein a photolysis oxidization fission chamber is arranged in the box body, and is connected with a waste gas inlet through a pipeline; a high pressure exciting device is arranged in the photolysis oxidization fission chamber for cracking and decomposing organic waste gas; a control system is further arranged on the box body, comprises a main controller, a negative pressure sensor and a photoelectric sensor, and realizes the control of whole operation and safety of the device. The UV-VOC waste gas treatment device effectively achieves the purification treatment of the waste gas through the photolysis oxidization fission chamber, and fully oxidizes, cracks and discharges the organic waste gas, so that pollution is nonsexist; the filtration and the separation of the waste gas are achieved through pretreatment, as a result, conditions of a subsequent photolysis oxidization fission treatment system treating the waste gas are created; the application of a water circulating system exponentially prolongs the service life of the photolysis oxidization fission device treatment system.
Owner:HANGZHOU HENGYU ENVIRONMENTAL PROTECTION TECH

Wide dynamic range neutron flux measurement system and method based on pulse-current mode

The invention discloses a wide dynamic range neutron flux measuring system and method based on a Pulse-Current mode. The system comprises a fission chamber, a reference chamber, a Pulse module, a Current module, a postprocessing module and a mode selection mode. The invention further discloses a wide dynamic range neutron flux measuring method based on the Pulse-Current mode. According to the system and method, the contradiction between background radial inhibition capacity and the requirement for the signal to noise ratio in a traditional wide dynamic range neutron flux measuring process is eliminated.
Owner:UNIV OF SCI & TECH OF CHINA

Calibration device for thermal neutron fluence rate of nuclear reactor silicon single crystal irradiation tunnel

ActiveCN105469842BEliminate status gapsAccurately measure fluence rateNuclear energy generationNuclear monitoringNuclear reactorSingle crystal
The invention relates to a calibrating device for the thermal neutron fluence rate of a silicon single crystal irradiation channel of a nuclear reactor, which comprises an aluminum cylinder, one end of the aluminum cylinder is provided with a base, the other end is provided with a top cover, and the center of the top cover is provided with a through hole. There is a silicon single crystal rod in the aluminum cylinder, and a round hole is arranged on the axis of the silicon single crystal rod. The open end of the round hole is opposite to the through hole. The sensitive section of the micro-fission chamber is inserted into the bottom of the round hole, and the micro-fission The chamber is set in the fixed pipe, and the hoisting head is connected with the top cover through the connecting column, and the through hole I matched with the through hole is arranged on the axial direction of the connecting column. The present invention simulates the environment and conditions during silicon irradiation by adopting the clever combination of micro-fission chambers and silicon single crystal rods, and eliminates the state gap between the measurement method and the silicon to be irradiated. The thermal neutron fluence rate of the silicon irradiation hole can be measured timely and accurately at the part to be measured in the irradiation hole, which can be directly used in the irradiation production.
Owner:NUCLEAR POWER INSTITUTE OF CHINA

Fission chamber based on Micromegas

The invention discloses a fission chamber based on Micromegas. The fission chamber comprises a Micromega detector, wherein the Micromega detector is provided with a metal shell, and a drift electrode, a Micromega microgrid and a collecting electrode which are arranged in the metal shell; the Micromega microgrid is arranged between the drift electrode and the collecting electrode; the collecting electrode is electrically connected with a pulse signal acquisition circuit; a drift region is formed between the Micromega microgrid and the drift electrode, and a collection region is formed betweenthe Micromega microgrid and the collection electrode; a gas chamber is defined by the metal shell, the drift electrode and the collecting electrode, and flowing ionized gas is arranged in the gas chamber; a plurality of aluminum plates are also arranged in the drift region; each aluminum plate is vertical to the drift electrode, and one side of each aluminum plate is fixedly connected with the drift electrode; and uranium-235 layers are arranged on the two side faces of each aluminum plate. The fission chamber is high in detection efficiency, high in sensitivity and high in counting rate range; and the fission chamber has better anti-interference capability and stronger n / gamma discrimination capability, and is especially suitable for real-time monitoring of the neutron fluence rate of a reactor and other strong electromagnetic interference and strong gamma radiation field environments.
Owner:NANHUA UNIV

High-temperature fission chamber

The embodiment of the invention provides a high-temperature fission chamber which comprises a probe, a suspension device, an insulation device, a shielding piece and an armored cable, the suspension device is provided with a cable channel, the probe is arranged at one end of the suspension device, the insulation device comprises a plurality of first insulation supporting pieces, and the shielding piece is arranged at the other end of the suspension device. The first insulating support members are arranged in the cable channel and are arranged at intervals along the extension direction of the cable channel. The shielding piece is arranged in the cable channel and located at the end, away from the probe, of the cable channel. An armored cable is arranged in the cable channel, one end of the armored cable is electrically connected with the probe, and the other end of the armored cable penetrates through the first insulation supporting piece and the shielding piece and extends out of the suspension device. The high-temperature fission chamber provided by the embodiment of the invention can guarantee effective output of a detection result.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY
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