33 results about "Fission chamber" patented technology

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.

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.

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.

A monitor of fusion neutron flux is formed by three fission chamber detectors set in stainless steel shell. It is featured as coating different mass of high purified fission material on cathodes of two fission chamber detectors make their sensitivity be 1: 100, setting the third fission chamber detector to be blank detector with no fission material, setting a layer of Cd-heat neutron shielding layer with neutron moderator structure in shell, setting lead shielding layer in neutron moderator structure and placing three fission chamber detectors in lead shielding layer.

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.

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.

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).

A method to determine the effective masses of deposits of fissile matter, including a first measuring step to measure the count rate of deposits of fissile matter of known effective masses to form a matrix [C]₀, a second measuring step to measure the count rate of deposits of fissile matter to form a matrix [C], and a computing step to calculate the effective masses to be determined.

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.

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.

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.

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.

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.