CN116646100A - Fission ionization chamber for measuring neutron flux outside reactor - Google Patents
Fission ionization chamber for measuring neutron flux outside reactor Download PDFInfo
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- CN116646100A CN116646100A CN202310553060.5A CN202310553060A CN116646100A CN 116646100 A CN116646100 A CN 116646100A CN 202310553060 A CN202310553060 A CN 202310553060A CN 116646100 A CN116646100 A CN 116646100A
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/108—Measuring reactor flux
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
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Abstract
The application relates to the technical field of neutron flux detection, in particular to a fission ionization chamber for measuring the neutron flux outside a reactor. A fission ionization chamber for off-reactor neutron flux measurement includes a probe, a coaxial connector, and a transmission cable; the probe comprises a cathode shell and an anode liner; the anode liner is accommodated in the cathode shell and is coaxial with the cathode shell, the inner wall of the cathode shell is spaced from the outer wall of the anode liner, and the high-purity mixed inert gas is filled in the spaced area; the outer wall of the cathode shell and the anode liner are electroplated 235 U is provided; the coaxial connector is connected to the front end of the probe; the transmission cable is connected with the coaxial connector and is electrically connected with the cathode shell and the anode liner. The fission ionization chamber for measuring the neutron flux outside the reactor is used for measuring the neutron flux outside the reactor, and has the advantages of reliable working performance, stable structure, long service life and high neutron sensitivity.
Description
Technical Field
The application relates to the technical field of neutron flux detection, in particular to a fission ionization chamber for measuring the neutron flux outside a reactor.
Background
The nuclear energy is used as an energy source with low carbon, safety, high efficiency and high stability, and plays an important role in ensuring energy safety, realizing a double-carbon target, reducing fossil energy dependence, pushing geopolitical and the like. The third world of the running machine set is the nuclear power large country with leading running machine sets for many years, and based on the third world, the safe, efficient and stable running of the nuclear power station is guaranteed, and the monitoring of the neutron flux outside the reactor to provide the reactor real-time power is more important. The fission ionization chamber originated in the 40 th century of the manhattan program and was an ionization detector that utilized fission of fissile nuclides with neutrons to produce fission fragments that were ionized in an inert gas to produce secondary particles to produce pulses to effect neutron flux measurements. At present, a fission ionization chamber is an indispensable important device in an off-reactor nuclear measurement system, and is installed in an in-service nuclear power plant such as Qin mountain first-stage, second-stage and Tian Gu of China and an off-country in-service nuclear power plant such as AP100 of the United states and EPR of Europe. The fission ionization chamber used in China is mainly imported, and self-research and self-production are needed.
Other common off-stackNeutron detectors, such as: the boron-coated ionization chamber has poor gamma radiation resistance, has larger measurement deviation under the condition that gamma radiation is larger than neutron radiation, and has lower detection efficiency which is only 20% at most compared with other detectors; BF (BF) 3 The detector cannot withstand radiation, has large burnup, short service life and BF 3 Is toxic gas, can be explosively decomposed when meeting water, and has serious potential safety hazard; 3 he detectors are expensive, have poor gamma radiation resistance, and have limited application range. Compared with other off-pile neutron detectors, the fission ionization chamber has the advantages of good gamma radiation resistance, high measurement lower limit and the like based on the neutron fission principle. The research on fission ionization chambers in China starts later, and the defects of more neutron scattering, unstable structure, lower sensitivity, shorter irradiation-resistant service life, slow air leakage and the like exist in the prior art.
Disclosure of Invention
The present application provides a fission ionization chamber for off-reactor neutron flux measurement to ameliorate the above problems.
The application is specifically as follows:
a fission ionization chamber for off-reactor neutron flux measurement, comprising a probe, a coaxial connector, and a transmission cable;
the probe comprises a cathode shell and an anode liner; the anode liner is accommodated in the cathode shell and is coaxial with the cathode shell, the inner wall of the cathode shell is spaced from the outer wall of the anode liner, and the high-purity mixed inert gas is filled in the spaced area; the outer wall of the cathode shell and the anode liner are electroplated 235 U；
The coaxial connector is connected to the front end of the probe; the transmission cable is connected with the coaxial connector and is electrically connected with the cathode shell and the anode liner.
In one embodiment of the application, the cathode housing is open at the front end; the probe also comprises a high-pressure end seal head which is connected to the front end of the cathode shell so as to seal the front end of the cathode shell; the coaxial connector and the anode liner are connected with the high-pressure end seal head.
In one embodiment of the application, the probe further comprises a first insulating connecting piece, and the front end of the anode liner is connected with the high-voltage end socket through the first insulating connecting piece.
In one embodiment of the application, the rear end of the cathode housing is open; the probe also comprises a second insulating connecting piece, and the rear end of the anode liner is connected with the rear end of the cathode shell through the second insulating connecting piece.
In one embodiment of the application, the probe further comprises an inflation tube connected to the rear end of the anode liner, and the inflation tube is communicated with the inner cavity of the anode liner.
In one embodiment of the application, the second insulating member is provided with a through hole for communicating the gas filled tube with the inner cavity of the anode liner.
In one embodiment of the application, the probe further comprises an inflation end enclosure and an inflation tube protection cover;
the inflation end sealing head is connected with the second insulation connecting piece, the inflation tube and the inflation tube protecting cover are connected with the inflation end sealing head, and the inflation tube protecting cover is arranged outside the inflation tube.
In one embodiment of the present application, the outer wall of the anode liner is provided with a plurality of holes.
In one embodiment of the application, the probe further comprises a high voltage joint core wire located within the anode inner container, the high voltage joint core wire electrically connecting the transmission cable with the anode inner container.
In one embodiment of the present application, 235 u is added with regenerated material 234 U is provided; the cathode shell and the anode liner are both made of Inconel600 alloy; the first insulating piece and the second insulating piece are made of high-purity alumina.
The beneficial effects of the application are as follows:
the fission ionization chamber for measuring the neutron flux outside the reactor comprises a probe, a coaxial connector and a transmission cable; the probe comprises a cathode shell and an anode liner; the anode liner is accommodated in the cathode shell and is coaxial with the cathode shell, the inner wall of the cathode shell is spaced from the outer wall of the anode liner, and the high-purity mixed inert gas is filled in the spaced area; the outer wall of the cathode shell and the anode liner are electroplated 235 U is provided; the coaxial connector is connected to the front end of the probe; transmission ofThe cable is connected with the coaxial connector and is electrically connected with the cathode shell and the anode liner.
The probe of the fission ionization chamber for measuring the neutron flux outside the reactor comprises a cathode shell and an anode liner, wherein the cathode shell and the anode liner are cylindrical components, and a BNC coaxial connector and a transmission cable are arranged at the front end of the cathode shell; the inner wall of the cathode shell and the outer wall of the anode liner are electroplated 235 U sample (adding regeneration material) 234 U), and high-purity mixed inert gas is filled between the inner wall of the cathode shell and the outer wall of the anode liner;
therefore, when the fission ionization chamber for measuring the neutron flux outside the reactor is placed in a measuring channel outside the reactor of the nuclear power station, the fission ionization chamber is installed and fixed; when the nuclear power station starts to start running, neutrons with certain energy are released to leak outside the reactor, and after entering the probe, the neutrons are electroplated on the cathode shell and the anode liner 235 The U sample generates fission reaction to generate fission fragments, and the fission fragments pass through 235 The U layer enters the probe to ionize the filled inert gas to generate electrons and positive ions; under the action of an externally-applied high-voltage electric field, electrons and positive ions respectively move to the anode and the cathode, so that pulse signals are generated, and then the pulse signals are transmitted to an electronics system through a transmission cable;
in summary, the fission ionization chamber for measuring the neutron flux outside the reactor is used for measuring the neutron flux outside the reactor, and has reliable working performance, stable structure, long service life and high neutron sensitivity.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present application, the drawings that are needed in the embodiments will be briefly described below, it being understood that the following drawings only illustrate some embodiments of the present application and therefore should not be considered as limiting the scope, and other related drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a schematic diagram of a fission ionization chamber for off-reactor neutron flux measurement according to the present application;
fig. 2 is a cross-sectional view of a fission ionization chamber for off-reactor neutron flux measurement provided by the present application.
Icon: 200-fission ionization chamber for off-reactor neutron flux measurement; 210-a probe; 220-coaxial connectors; 230-a transmission cable; 211-a cathode housing; 212-an anode liner; 213-high pressure end closure; 214-first insulating connectors; 215-a second insulated connector; 216-an inflation tube; 217-vias; 218, an inflation end enclosure; 219-inflation tube boot; 201-holes; 202-high voltage joint core wire.
Detailed Description
For the purpose of making the objects, technical solutions and advantages of the embodiments of the present application more apparent, the technical solutions of the embodiments of the present application will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present application, and it is apparent that the described embodiments are some embodiments of the present application, but not all embodiments of the present application. The components of the embodiments of the present application generally described and illustrated in the figures herein may be arranged and designed in a wide variety of different configurations.
Thus, the following detailed description of the embodiments of the application, as presented in the figures, is not intended to limit the scope of the application, as claimed, but is merely representative of selected embodiments of the application. All other embodiments, which can be made by those skilled in the art based on the embodiments of the application without making any inventive effort, are intended to be within the scope of the application.
It should be noted that, without conflict, the embodiments of the present application and features of the embodiments may be combined with each other.
It should be noted that: like reference numerals and letters denote like items in the following figures, and thus once an item is defined in one figure, no further definition or explanation thereof is necessary in the following figures.
In the description of the embodiments of the present application, it should be noted that, the indicated orientation or positional relationship is based on the orientation or positional relationship shown in the drawings, or the orientation or positional relationship conventionally put in use of the product of the application as understood by those skilled in the art, which is merely for convenience of describing the present application and simplifying the description, and is not indicative or implying that the apparatus or element to be referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the present application. Furthermore, the terms "first," "second," "third," and the like are used merely to distinguish between descriptions and should not be construed as indicating or implying relative importance.
In the description of the embodiments of the present application, it should also be noted that, unless explicitly specified and limited otherwise, the terms "disposed," "mounted," and "connected" are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally connected; may be directly connected or indirectly connected through an intermediate medium. The specific meaning of the above terms in the present application will be understood in specific cases by those of ordinary skill in the art.
Because neutrons releasing certain energy leak outside the reactor during the operation process, the quantity of neutrons is proportional to the power of the reactor, and based on the principle, referring to fig. 1 and 2, the present application provides a fission ionization chamber 200 for measuring the neutron flux outside the reactor, which can provide a neutron flux signal to a reactor protection system through a probe 210 for detecting neutrons outside the reactor; the method provides 'state information' of reactor loading, reactor shutdown, starting and full operation in real time, triggers reactor shutdown under the conditions of high neutron flux and high change rate, and continuously monitors reactor power, change of power level and power distribution.
Specifically, referring to fig. 1 and 2, a fission ionization chamber 200 for measuring an external neutron flux of a reactor according to the present embodiment includes a probe 210, a coaxial connector 220, and a transmission cable 230;
the probe 210 includes a cathode housing 211 and an anode liner 212; the anode liner 212 is accommodated in the cathode housing 211 and is coaxial with the cathode housing 211, the inner wall of the cathode housing 211 is spaced from the outer wall of the anode liner 212, and the high purity is filled in the spaced regionMixing inert gas; the outer wall of the cathode shell 211 and the anode liner 212 are electroplated 235 U is provided; wherein,, 235 u is added with regenerated material 234 U；
The coaxial connector 220 is connected to the front end of the probe 210; the transmission cable 230 is connected to the coaxial connector 220, and is electrically connected to the cathode housing 211 and the anode inner 212.
Referring to fig. 1 and 2, the fission ionization chamber 200 for measuring the neutron flux outside the reactor has the following working principles:
the probe 210 of the fission ionization chamber 200 for measuring the neutron flux outside the reactor comprises a cathode shell 211 and an anode liner 212, wherein the cathode shell 211 and the anode liner 212 are cylindrical components, and a BNC coaxial connector 220 and a transmission cable 230 are arranged at the front end of the cathode shell 211; the inner wall of the cathode housing 211 and the outer wall of the anode liner 212 are both electroplated with 235 U sample (adding regeneration material) 234 U), and a high-purity mixed inert gas is filled between the inner wall of the cathode housing 211 and the outer wall of the anode liner 212;
thus, when the fission ionization chamber 200 for measuring the neutron flux outside the reactor is placed in the measuring channel outside the reactor of the nuclear power station, the fission ionization chamber is installed and fixed; when the nuclear power station starts to start operation, neutrons with certain energy are released to the outside of the reactor, enter the probe 210 and are electroplated on the cathode shell 211 and the anode liner 212 235 The U sample generates fission reaction to generate fission fragments, and the fission fragments pass through 235 The U layer enters the probe 210 to ionize the inert gas filled in the probe to generate electrons and positive ions; under the action of the externally applied high-voltage electric field, electrons and positive ions respectively move to the anode and the cathode, so that pulse signals are generated, and then the pulse signals are transmitted to an electronic system through a transmission cable 230;
to sum up, referring to fig. 1 and 2, the fission ionization chamber 200 for measuring the neutron flux outside the reactor is used for measuring the neutron flux outside the reactor, and has reliable working performance, stable structure, long service life and high neutron sensitivity.
Further, in the present embodiment, the front end of the cathode housing 211 is open; the probe 210 further comprises a high-pressure end enclosure 213, wherein the high-pressure end enclosure 213 is connected to the front end of the cathode housing 211 to seal the front end of the cathode housing 211; the coaxial connector 220 and the anode liner 212 are both connected to the high pressure end cap 213.
The probe 210 further comprises a first insulating connector 214, and the front end of the anode liner 212 is connected with a high-voltage end seal 213 through the first insulating connector 214. The rear end of the cathode housing 211 is open; the probe 210 further includes a second insulating connector 215, and the rear end of the anode inner container 212 is connected to the rear end of the cathode housing 211 through the second insulating connector 215.
To add high purity mixed inert gas to the probe 210, the probe 210 further includes an inflation tube 216 connected to the rear end of the anode liner 212, the inflation tube 216 being in communication with the interior cavity of the anode liner 212. Since the rear end of the anode inner container 212 is connected with the rear end of the cathode housing 211 through the second insulating connector 215, the second insulating connector is provided with a through hole 217 for communicating the gas tube 216 with the inner cavity of the anode inner container 212. In order to enable the high-purity mixed inert gas in the anode liner 212 to be introduced into the region where the inner wall of the cathode housing 211 is spaced from the outer wall of the anode liner 212, the outer wall of the anode liner 212 is provided with a plurality of holes 201.
To improve the air tightness, the probe 210 further comprises an inflation end cap 218 and an inflation tube protecting cap 219; the inflation end closure 218 is connected with the second insulating connecting piece 215, the inflation tube 216 and the inflation tube protecting cover 219 are connected with the inflation end closure 218, and the inflation tube protecting cover 219 is covered outside the inflation tube 216.
To electrically connect the anode inner 212 with the transmission cable 230, the probe 210 further includes a high voltage connector core wire 202 positioned within the anode inner 212, the high voltage connector core wire 202 electrically connecting the transmission cable 230 with the anode inner 212. When the probe 210 is manufactured, the cathode shell 211 and the anode liner 212 are all made of Inconel600 alloy; the first insulating piece and the second insulating piece are made of high-purity alumina.
Based on the above structural arrangement, referring to fig. 1 and 2, the manufacturing process of the fission ionization chamber 200 for measuring the neutron flux outside the reactor provided by the application is as follows:
the anode liner 212 is made of an Inconel600 alloy tube with the inner diameter of 17mm and the outer diameter of 22mm as a processing parent metal; the specific process flow is as follows:
firstly, polishing and manufacturing a boring cutter blade for machining an inner aperture, selecting a boring cutter handle for welding the blade by turning and milling high-strength steel, manufacturing the boring cutter handle into a polyhedron, forming a reinforcing rib, reducing the influence of a long-handle chatter cutter, milling a blade groove on the handle, and then firmly welding the blade in the groove at the front end of the handle; designing a supporting tool according to the target size of the anode liner 212, and ensuring that the anode liner 212 is stable and does not deform in the turning and boring processes; according to the tool drawing, selecting materials, processing and manufacturing, assembling and forming the tool according to a design scheme, installing the tool on a lathe, selecting a section of materials to be processed, performing liner trial manufacture, and determining and adjusting the effect of the tool. Manufacturing the inner container by using a tool and a special boring cutter according to the processing size of the inner container, and finally completing the manufacturing of the anode inner container 212 according to a stable process (including turning rotating speed, feeding amount and tool mounting methods in different processing positions);
the cathode housing 211 material is also prepared from an Inconel600 alloy material; the specific manufacturing process flow is similar to that of the inner container electrode material; processing a base material by using Inconel with the inner diameter of 22mm and the outer diameter of 30mm as a cathode shell 211; according to the drawing requirements, adopting a general turning and punching process to manufacture; the fabrication of the cathode housing 211 is finally completed according to a stabilization process;
the insulating material adopts high-purity alumina; processing a sintering mold according to the sizes of the two parts, wherein the sintering mold is made of materials which can be used for sintering ceramics at high temperature, then adding ceramic powder into the mold, and sintering by adopting a hot isostatic pressing process; after sintering the manufactured ceramic parts, polishing and modifying the ceramic parts at different angles and with different inner diameters and outer diameters on water-based ceramic polishing equipment, and polishing and measuring for multiple times to ensure that the polished parts meet the size requirements; the manufacturing of the insulating piece is finally completed according to the stabilizing process;
the corresponding parts of the part of the inflation tube 216, the inflation end seal 218, the inflation end protecting cover and the high-pressure end seal 213 can be finished by machining manufacturing processes such as turning, milling, punching, polishing or tapping; the manufacturing of the inflation tube 216, the inflation end cap 218, the inflation end shield and the high pressure end cap 213 is finally completed by a stabilizing process.
Before assembly, thoroughly cleaning each assembly, so as to ensure that each assembly is kept clean and dry during assembly; after all the metal materials are cleaned by using an organic solvent, carrying out high-temperature degassing in a vacuum furnace to evaporate impurities in the Inconel600 alloy;
referring to fig. 1 and 2, after manufacturing the components according to the above production process flow according to the design drawing, the assembly process flow of the fission ionization chamber 200 for measuring the neutron flux outside the reactor is as follows:
performing a pre-assembly test to confirm whether the pre-assembly tolerance meets the assembly requirement; after the test is passed, the whole assembly is started, and the assembly steps are as follows:
firstly, positioning and assembling an inflation end seal head 218 and an inflation tube 216 according to a drawing, and then positioning by adopting a tool; sealing and welding the assembly joints of the two, wherein the welding adopts an inner welding process;
positioning and assembling the first insulating connecting piece 214 and the cathode shell 211 according to the figure, positioning and assembling the inflation end closure 218 which is already welded with the inflation tube 216 into a whole and the cathode shell 211 according to the figure, positioning by adopting a fixture, and sealing and welding the assembly joint of the two parts, wherein an external welding process is adopted;
sealing and assembling the high-voltage end seal head 213 and the BNC joint, then assembling the insulating connecting piece 1, the BNC joint and the anode liner 212 according to a graph, and welding the end of the high-voltage joint core wire 202 with the inner wall of the anode liner 212 to form an anode liner 212 assembly;
then, the anode liner 212 assembly is assembled into the cathode shell 211 according to the figure, and is positioned and assembled with the first insulating connecting piece 214, and then, a fixture is adopted for positioning, and the joint of the high-voltage end seal head 213 and the cathode shell 211 is subjected to seal welding, wherein an external welding process is adopted;
the inflation operation is carried out by the inflation tube 216, after the inflation is completed and the inflation tube 216 is sealed, the inflation end protecting cover and the inflation end sealing head 218 are assembled according to the figure, then the tooling positioning is adopted, the joint between the inflation end protecting cover and the inflation end sealing head 218 is sealed and welded, and the external welding operation is adopted at the joint;
all the sealing welding parts adopt argon arc welding for surrounding welding so as to meet the requirements of stable connection and pressure-resistant sealing.
During the inflation process, the inflation steps are as follows:
firstly, a tee joint part is externally connected to the front part of the end of the gas charging pipe 216, the tee joint part is connected with a gas charging pipeline and a mixed inert gas steel cylinder, and one of the tee joint parts is connected with a vacuum pump;
evacuating the inner cavity of the anode liner 212, observing a vacuum pressure gauge, and closing an evacuation pipeline valve after the vacuum degree reaches a stable value, namely the evacuation limit of the vacuum pump;
opening an air injection pipeline, controlling through a valve, observing a pressure gauge, and gradually injecting mixed inert gas until a required pressure value is reached;
closing the gas injection pipeline, starting the vacuum pump, finely adjusting and opening a valve of the evacuation pipeline, smoothly pumping and discharging the injected mixed inert gas, and repeating the gas injection operation after reaching the evacuation limit of the vacuum pump again; after the above operation is repeated for 3 times, the original air in the fission ionization chamber 200 for measuring the neutron flux outside the reactor is basically removed, the mixed inert gas is injected to meet the process requirement, and the gas filling end is randomly sealed, so that the gas filling operation is completed.
Based on the above, the fission ionization chamber 200 for measuring the neutron flux outside the reactor comprises a cylindrical shell member (cathode shell 211), wherein the front end of the cylindrical shell is provided with a BNC coaxial connector 220, the matched set is fixed by a high-voltage end seal head 213 and an insulating connector, and the rear end of the cylindrical shell is provided with an inflation tube protecting cover 219; the cylindrical shell is internally provided with a coaxial anode cylindrical inner container which is connected with the cathode shell 211 through an insulating connecting piece, and the inner wall of the shell and the outer wall of the inner container are electroplated 235 U sample (adding regeneration material) 234 U), high-purity mixed inert gas is filled between the inner cylinder and the outer cylinder, and the collected signals are transmitted through the high-pressure joint core wire 202 of the inner cylinder by spot welding; anode linerThe rear end of 212 is provided with a special inflation tube 216 and is fixed by an inflation end seal head 218; therefore, the fission ionization chamber 200 for measuring the neutron flux outside the reactor has the advantages of simple structure, reliable working performance, stable structure, long service life, high neutron sensitivity and the like.
Specifically, based on the structural arrangement, first, the fission ionization chamber 200 for off-reactor neutron flux measurement is 235 The U-shaped fission ionization chamber adopts a coaxial double-cylinder structure, a hollow cylinder made of Inconel600 alloy is adopted as a cathode shell 211, an anode liner 212 also adopts the hollow cylinder made of Inconel600 alloy as an anode, the front end and the rear end of the two electrodes are encapsulated by sealing heads, and an insulating connecting piece is adopted between the two electrodes of the anode and the cathode for fixing; the structure is simple, accessories are relatively fewer, the assembly is easy, and compared with a flat plate structure, the structure is more stable;
second, the fission ionization chamber 200 for measuring the neutron flux outside the reactor is provided with a special gas filling pipe 216 and a gas filling pipe protecting cover 219, and adopts a mode of vacuum-gas filling interaction for a plurality of times so as to achieve the aim of 235 The injection requirement of high-purity inert gas in the cavity of the U-shaped fission ionization chamber; after the required pressure value is reached, the mouth of the gas charging tube 216 is tightly pressed and sealed by adopting a cold pressing process, meanwhile, the cold pressing end is welded and sealed by adopting a welding process, so that the sealing effect of secondary protection is achieved, and meanwhile, in order to avoid interference such as collision and the like on the sealing end in the using and transporting process, a gas charging tube protecting cover 219 is also arranged to protect the welded and sealed gas charging end, so that the situation that tiny gas leakage does not occur when the fission ionization chamber 200 for measuring the neutron flux outside the reactor works for a long time is ensured;
in addition, the fission ionization chamber 200 for off-reactor neutron flux measurement employs a smaller electrode spacing (1.5 mm) where process production can be satisfied; in fission ionization chamber 200 for off-reactor neutron flux measurement 235 U can spontaneously decay alpha particles, the superposition of alpha pulse signals can affect the real counting, and the ionization ratio of fission fragments and alpha particles is opposite to the relation between the ionization ratio and the range, so that the ionization ratio of the fission fragments is maximum at the beginning of the range, and alphaThe particles are maximum at the range terminal, so that the energy of fission fragments and alpha particle deposition can be better distinguished by adopting smaller electrode spacing, and the influence of alpha pulse signals on real counting is reduced; in addition, the collection time of positive and negative particles in the gas can be shortened by adopting smaller electrode spacing, and the upper measurement limit of the detector is improved;
moreover, because the metal material parts of the probe 210 are all made of the Inconel600 alloy, the Inconel600 alloy is nickel-chromium-iron-based solid solution strengthening alloy, and the density is 8.43g/cm 3 Compared with metal materials such as aluminum, stainless steel, copper and the like, the alloy has good high-temperature corrosion resistance, high-pressure resistance, irradiation resistance, oxidation resistance, and excellent cold and hot processing and welding performances; the Inconel600 alloy can improve the structure of the fission ionization chamber 200 for measuring the neutron flux outside the reactor and the stability during operation, and can keep normal operation in relatively complex environments facing high temperature, high humidity, high pressure or high radiation, etc.; in addition, the quality of the electrodeposited uranium is greatly influenced by the metal material of the detector matrix, the electrodeposited uranium is not firmly combined with the plating layer on the surfaces of metals such as stainless steel, carbon steel and zirconium alloy, the plating layer is not uniform, and the adhesion force on the surface of nickel is good, as the Inconel600 alloy contains a large amount of nickel elements, the nickel element content is more than 72 percent, when the electrodeposited uranium is plated on the walls of the cathode shell 211 and the anode liner 212 by using an electrodeposition method, compared with other alloy metals, 235 the U sample is on the Inconel600 alloy, the uranium coating is finer, the uranium grains are uniformly dispersed, and the U sample is firmly combined with the base material; the probe 210 adopts the processed Inconel600 alloy with the thickness as thin as possible (less than or equal to 1 mm), so as to reduce the influence of neutron scattering as much as possible and improve the neutron detection efficiency of the fission ionization chamber; the insulating connector parts of the probe 210, namely the first insulating connector 214 and the second insulating connector 215, are made of high-purity alumina (more than or equal to 99.99 percent) with the density of 8.43g/cm 3 The method comprises the steps of carrying out a first treatment on the surface of the The high-purity alumina has excellent insulating performance under normal temperature and normal pressure, and the insulating resistance can reach 10 14 Omega; at a high temperature of 300 ℃, good insulating performance can be maintained, and the insulating resistance is 10 13 Omega; the high-purity alumina is used as an insulating connecting piece, so that various accessories of the fission ionization chamber can be effectively fixed, an anode and a cathode are isolated, and leakage is reduced when the fission ionization chamber worksLoss of current; selecting BNC coaxial connector 220, wherein the insulator material part is polytetrafluoroethylene, and the insulation resistance is more than or equal to 500MΩ;
the fission ionization chamber 200 for measuring the neutron flux outside the reactor is filled with high-purity mixed inert gas, on the basis of high-purity argon, the drift velocity of electrons is increased by adding a certain proportion of polyatomic molecular gas, the probability of capturing the electrons is reduced, the cavity of the fission ionization chamber is vacuumized through a vacuum inflation system, then the mixed inert gas is filled and purified circularly, the concentration of the mixed inert gas in the cavity is more than or equal to 99%, so that the situation that the electronegative gas is too much, ions and electrons in the gas are compounded, no contribution is made to output signals any more, and the count of the fission ionization chamber is inaccurate is prevented;
it will be appreciated that the fission ionization chamber 200 for off-reactor neutron flux measurement employs high concentration 235 U sample, at the same time 235 Adding a certain proportion of regenerated material into the U sample 234 U, due to convention 235 The U fission ionization chamber can generate obvious burnup under the working condition of relatively high thermal neutron flux, so that the output signal strength is obviously reduced in the preset required working life; thus in 235 The U sample is added with a certain proportion of regenerated materials in advance 234 U, transform atoms 234 U can be converted into atoms after absorbing thermal neutrons 235 U, make the conversion rate approach 235 Normal consumption rate of U, replenishment 235 The consumption of U in the detection work is improved, so that the service life of the detector is prolonged, the sub-sensitivity is relatively unchanged in the prolonged irradiation period, and the constancy of the output signal of the detector is effectively improved;
in addition to the uranium plating on the outer surface of the anode liner 212, the inner surface of the cathode housing 211 is also uranium plated, so that the uranium plating area can reach about 175cm, since the diameter of the probe 210 is 28mm and the length of the sensitive region is 127mm 2 The method comprises the steps of carrying out a first treatment on the surface of the Electroplating to a certain thickness by using electrodeposition 235 U sample (adding regeneration material) 234 U), effectively increase 235 Detection efficiency and neutron of U fission ionization chamberSensitivity;
the above is only a preferred embodiment of the present application, and is not intended to limit the present application, but various modifications and variations can be made to the present application by those skilled in the art. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present application should be included in the protection scope of the present application.
Claims (10)
1. A fission ionization chamber for off-reactor neutron flux measurement, characterized by:
the fission ionization chamber for measuring the neutron flux outside the reactor comprises a probe, a coaxial connector and a transmission cable;
the probe comprises a cathode shell and an anode liner; the anode liner is accommodated in the cathode shell and is coaxial with the cathode shell, the inner wall of the cathode shell is spaced from the outer wall of the anode liner, and a high-purity mixed inert gas is filled in a spaced area; the outer wall of the cathode shell and the outer wall of the anode liner are electroplated 235 U；
The coaxial connector is connected to the front end of the probe; the transmission cable is connected with the coaxial connector and is electrically connected with the cathode shell and the anode liner.
2. The fission ionization chamber for off-reactor neutron flux measurement according to claim 1, wherein:
the front end of the cathode shell is open; the probe also comprises a high-pressure end closure head which is connected to the front end of the cathode shell so as to block the front end of the cathode shell; the coaxial connector and the anode liner are connected with the high-pressure end seal head.
3. The fission ionization chamber for off-reactor neutron flux measurement according to claim 2, wherein:
the probe also comprises a first insulating connecting piece, and the front end of the anode liner is connected with the high-voltage end seal head through the first insulating connecting piece.
4. A fission ionization chamber for off-reactor neutron flux measurement according to claim 3, wherein:
the rear end of the cathode casing is open; the probe also comprises a second insulating connecting piece, and the rear end of the anode liner is connected with the rear end of the cathode shell through the second insulating connecting piece.
5. The fission ionization chamber for off-reactor neutron flux measurement according to claim 4, wherein:
the probe also comprises an inflation tube connected to the rear end of the anode liner, and the inflation tube is communicated with the inner cavity of the anode liner.
6. The fission ionization chamber for off-reactor neutron flux measurement according to claim 5, wherein:
the second insulating piece is provided with a through hole which communicates the gas charging pipe with the inner cavity of the anode liner.
7. The fission ionization chamber for off-reactor neutron flux measurement according to claim 6, wherein:
the probe also comprises an inflation end socket and an inflation tube protecting cover;
the inflation end seal head is connected with the second insulation connecting piece, the inflation tube and the inflation tube protecting cover are connected with the inflation end seal head, and the inflation tube protecting cover is covered outside the inflation tube.
8. The fission ionization chamber for off-reactor neutron flux measurement according to claim 5, wherein:
the outer wall of the anode liner is provided with a plurality of holes.
9. The fission ionization chamber for off-reactor neutron flux measurement according to any one of claims 1-8, wherein:
the probe also comprises a high-voltage joint core wire positioned in the anode liner, and the high-voltage joint core wire electrically connects the transmission cable with the anode liner.
10. The fission ionization chamber for off-reactor neutron flux measurement according to any one of claims 1-8, wherein:
the said 235 U is added with regenerated material 234 U is provided; the cathode shell and the anode liner are both made of Inconel600 alloy; the first insulating piece and the second insulating piece are made of high-purity alumina.
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Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB956555A (en) * | 1959-06-19 | 1964-04-29 | Plessey Co Ltd | Improvements in or relating to neutron flux plotting systems |
| GB1283337A (en) * | 1969-01-30 | 1972-07-26 | Licentia Gmbh | Neutron-sensitive ionisation chamber |
| GB1308379A (en) * | 1969-07-24 | 1973-02-21 | Licentia Gmbh | Neutron-sensitive ionisation chambers |
| JPS52104693A (en) * | 1976-02-27 | 1977-09-02 | Power Reactor & Nuclear Fuel Dev Corp | Neutron detector for monitoring in reactor |
| US4410483A (en) * | 1980-06-26 | 1983-10-18 | Mitsubishi Denki Kabushiki Kaisha | Neutron detector for use within nuclear reactor |
-
2023
- 2023-05-17 CN CN202310553060.5A patent/CN116646100A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB956555A (en) * | 1959-06-19 | 1964-04-29 | Plessey Co Ltd | Improvements in or relating to neutron flux plotting systems |
| GB1283337A (en) * | 1969-01-30 | 1972-07-26 | Licentia Gmbh | Neutron-sensitive ionisation chamber |
| GB1308379A (en) * | 1969-07-24 | 1973-02-21 | Licentia Gmbh | Neutron-sensitive ionisation chambers |
| JPS52104693A (en) * | 1976-02-27 | 1977-09-02 | Power Reactor & Nuclear Fuel Dev Corp | Neutron detector for monitoring in reactor |
| US4410483A (en) * | 1980-06-26 | 1983-10-18 | Mitsubishi Denki Kabushiki Kaisha | Neutron detector for use within nuclear reactor |
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