CN115055392A - High-temperature gas cooled reactor graphite nodule surface decontamination screening system and method - Google Patents
High-temperature gas cooled reactor graphite nodule surface decontamination screening system and method Download PDFInfo
- Publication number
- CN115055392A CN115055392A CN202210386514.XA CN202210386514A CN115055392A CN 115055392 A CN115055392 A CN 115055392A CN 202210386514 A CN202210386514 A CN 202210386514A CN 115055392 A CN115055392 A CN 115055392A
- Authority
- CN
- China
- Prior art keywords
- graphite
- radionuclide
- decontamination
- nodule
- subsystem
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 title claims abstract description 246
- 229910002804 graphite Inorganic materials 0.000 title claims abstract description 243
- 239000010439 graphite Substances 0.000 title claims abstract description 243
- 238000005202 decontamination Methods 0.000 title claims abstract description 77
- 230000003588 decontaminative effect Effects 0.000 title claims abstract description 73
- 238000012216 screening Methods 0.000 title claims abstract description 65
- 238000000034 method Methods 0.000 title claims abstract description 32
- 238000004458 analytical method Methods 0.000 claims abstract description 123
- 238000005259 measurement Methods 0.000 claims abstract description 82
- 238000012545 processing Methods 0.000 claims abstract description 71
- 239000000428 dust Substances 0.000 claims abstract description 65
- 230000002285 radioactive effect Effects 0.000 claims abstract description 53
- 238000012544 monitoring process Methods 0.000 claims abstract description 46
- 230000005855 radiation Effects 0.000 claims abstract description 28
- 230000000704 physical effect Effects 0.000 claims description 44
- 230000000694 effects Effects 0.000 claims description 38
- 238000001914 filtration Methods 0.000 claims description 25
- 238000012806 monitoring device Methods 0.000 claims description 15
- 230000008569 process Effects 0.000 claims description 14
- 230000010354 integration Effects 0.000 claims description 11
- 239000000126 substance Substances 0.000 claims description 8
- 230000004044 response Effects 0.000 claims description 5
- 238000009792 diffusion process Methods 0.000 abstract description 8
- 238000003915 air pollution Methods 0.000 abstract description 4
- 238000003904 radioactive pollution Methods 0.000 abstract description 3
- 239000007789 gas Substances 0.000 description 64
- 230000008054 signal transmission Effects 0.000 description 24
- 238000001514 detection method Methods 0.000 description 7
- 230000006872 improvement Effects 0.000 description 4
- 230000004913 activation Effects 0.000 description 3
- 238000004140 cleaning Methods 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 239000000203 mixture Substances 0.000 description 3
- 239000000443 aerosol Substances 0.000 description 2
- 238000011109 contamination Methods 0.000 description 2
- 230000002950 deficient Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000011261 inert gas Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000000746 purification Methods 0.000 description 2
- 239000002901 radioactive waste Substances 0.000 description 2
- 238000003860 storage Methods 0.000 description 2
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 1
- 238000000498 ball milling Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 229910052793 cadmium Inorganic materials 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000004927 fusion Effects 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 229910052740 iodine Inorganic materials 0.000 description 1
- 239000011630 iodine Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 229910052709 silver Inorganic materials 0.000 description 1
- 239000002910 solid waste Substances 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Images
Classifications
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B07—SEPARATING SOLIDS FROM SOLIDS; SORTING
- B07C—POSTAL SORTING; SORTING INDIVIDUAL ARTICLES, OR BULK MATERIAL FIT TO BE SORTED PIECE-MEAL, e.g. BY PICKING
- B07C5/00—Sorting according to a characteristic or feature of the articles or material being sorted, e.g. by control effected by devices which detect or measure such characteristic or feature; Sorting by manually actuated devices, e.g. switches
- B07C5/34—Sorting according to other particular properties
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D46/00—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours
- B01D46/42—Auxiliary equipment or operation thereof
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D46/00—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours
- B01D46/42—Auxiliary equipment or operation thereof
- B01D46/44—Auxiliary equipment or operation thereof controlling filtration
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
- B01D53/02—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by adsorption, e.g. preparative gas chromatography
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B07—SEPARATING SOLIDS FROM SOLIDS; SORTING
- B07C—POSTAL SORTING; SORTING INDIVIDUAL ARTICLES, OR BULK MATERIAL FIT TO BE SORTED PIECE-MEAL, e.g. BY PICKING
- B07C5/00—Sorting according to a characteristic or feature of the articles or material being sorted, e.g. by control effected by devices which detect or measure such characteristic or feature; Sorting by manually actuated devices, e.g. switches
- B07C5/02—Measures preceding sorting, e.g. arranging articles in a stream orientating
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B07—SEPARATING SOLIDS FROM SOLIDS; SORTING
- B07C—POSTAL SORTING; SORTING INDIVIDUAL ARTICLES, OR BULK MATERIAL FIT TO BE SORTED PIECE-MEAL, e.g. BY PICKING
- B07C5/00—Sorting according to a characteristic or feature of the articles or material being sorted, e.g. by control effected by devices which detect or measure such characteristic or feature; Sorting by manually actuated devices, e.g. switches
- B07C5/34—Sorting according to other particular properties
- B07C5/346—Sorting according to other particular properties according to radioactive properties
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B07—SEPARATING SOLIDS FROM SOLIDS; SORTING
- B07C—POSTAL SORTING; SORTING INDIVIDUAL ARTICLES, OR BULK MATERIAL FIT TO BE SORTED PIECE-MEAL, e.g. BY PICKING
- B07C5/00—Sorting according to a characteristic or feature of the articles or material being sorted, e.g. by control effected by devices which detect or measure such characteristic or feature; Sorting by manually actuated devices, e.g. switches
- B07C5/36—Sorting apparatus characterised by the means used for distribution
- B07C5/361—Processing or control devices therefor, e.g. escort memory
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B07—SEPARATING SOLIDS FROM SOLIDS; SORTING
- B07C—POSTAL SORTING; SORTING INDIVIDUAL ARTICLES, OR BULK MATERIAL FIT TO BE SORTED PIECE-MEAL, e.g. BY PICKING
- B07C5/00—Sorting according to a characteristic or feature of the articles or material being sorted, e.g. by control effected by devices which detect or measure such characteristic or feature; Sorting by manually actuated devices, e.g. switches
- B07C5/36—Sorting apparatus characterised by the means used for distribution
- B07C5/361—Processing or control devices therefor, e.g. escort memory
- B07C5/362—Separating or distributor mechanisms
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B07—SEPARATING SOLIDS FROM SOLIDS; SORTING
- B07C—POSTAL SORTING; SORTING INDIVIDUAL ARTICLES, OR BULK MATERIAL FIT TO BE SORTED PIECE-MEAL, e.g. BY PICKING
- B07C5/00—Sorting according to a characteristic or feature of the articles or material being sorted, e.g. by control effected by devices which detect or measure such characteristic or feature; Sorting by manually actuated devices, e.g. switches
- B07C5/36—Sorting apparatus characterised by the means used for distribution
- B07C5/38—Collecting or arranging articles in groups
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/008—Apparatus specially adapted for mixing or disposing radioactively contamined material
Landscapes
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Analytical Chemistry (AREA)
- General Chemical & Material Sciences (AREA)
- Oil, Petroleum & Natural Gas (AREA)
- Measurement Of Radiation (AREA)
Abstract
The invention provides a high-temperature gas cooled reactor graphite nodule surface decontamination screening system and method, and belongs to the technical field of radiation protection. The system of the present invention comprises: a graphite nodule decontamination screening subsystem and a numerical control integrated subsystem connected with the graphite nodule decontamination screening subsystem; the system comprises a graphite nodule decontamination screening subsystem, a data acquisition subsystem and a data processing subsystem, wherein the graphite nodule decontamination screening subsystem is used for removing dust on the surface of a graphite nodule and measuring radioactive nuclides and physical characteristics of the graphite nodule after the dust is removed; and the numerical control integrated subsystem is used for screening the graphite nodules according to the measurement values of the radioactive nuclides and the measurement values of the physical characteristics. The invention provides a graphite nodule decontamination, radioactivity monitoring and physical characteristic automatic analysis, measurement and screening system and a method for a high-temperature gas cooled reactor, which have the functions of graphite nodule surface decontamination, radionuclide measurement and analysis, physical characteristic monitoring, numerical control integrated automatic regulation and control and the like, greatly reduce the risks of external irradiation, internal irradiation and air pollution diffusion generated in the graphite nodule decontamination process, and greatly reduce the risk of radioactive pollution diffusion.
Description
Technical Field
The invention belongs to the technical field of radiation protection, and particularly relates to a high-temperature gas cooled reactor graphite nodule surface decontamination screening system and method.
Background
Radioactive contamination of graphite nodules discharged from the HTR-PM core results on the one hand from radioactive graphite dust adhering to the surface of the graphite nodules; on the other hand, the nuclear fusion reactor is from the neutron activation effect of graphite nodules in a reactor core, and radionuclide generated by activation of impurity nuclides in the graphite nodules, such as B, Cd, Sm, Li, Ag, Fe, Co and the like. Through estimation, the radioactivity generated by the activation of the graphite spheres is very little, and the activity of the radioactive nuclide generated by a single graphite sphere is mostly close to the exemption activity after the short-term temporary storage and decay. Through experimental research, the main source of radioactive pollution generated by graphite nodules discharged from the reactor core is surface-contaminated radioactive graphite-containing dust. After about 70 ten thousand graphite balls are discharged, radioactive graphite dust on the surface is contaminated to form radioactive waste, so that great storage pressure and resource waste are caused.
Therefore, in order to remove graphite dust contaminated on the surface of graphite nodules and greatly reduce the radioactivity of the graphite nodules, it is urgently needed to design a system and a method for decontaminating and screening the surface of the graphite nodules in a high temperature gas cooled reactor from the perspective of minimizing radioactive wastes.
Disclosure of Invention
The invention aims to at least solve one of the technical problems in the prior art and provides a system and a method for decontaminating and screening the surface of graphite nodules of a high-temperature gas cooled reactor.
In one aspect of the present invention, a high temperature gas cooled reactor graphite nodule surface decontamination screening system is provided, which includes: a graphite nodule decontamination screening subsystem and a numerical control integrated subsystem connected with the graphite nodule decontamination screening subsystem; wherein the content of the first and second substances,
the graphite nodule decontaminating and screening subsystem is used for removing dust on the surface of graphite nodules and measuring radionuclide and physical properties of the graphite nodules after dust removal;
and the numerical control integrated subsystem is used for screening the graphite nodules according to the measurement values of the radioactive nuclides and the measurement values of the physical characteristics.
Optionally, the graphite nodule decontamination screening subsystem comprises: the device comprises a graphite ball feeder, a surface decontamination device, a radionuclide measurement and analysis device and a physical characteristic measurement and analysis device which are sequentially connected through a conveyor belt; wherein, the first and the second end of the pipe are connected with each other,
the conveying belt is used for conveying the graphite nodules from the graphite nodule feeder to the surface decontamination device, the radionuclide measurement and analysis device and the physical characteristic measurement and analysis device in sequence;
the surface decontamination device is used for removing surface dust of the graphite nodules;
the radionuclide measurement and analysis device is used for measuring the radionuclide of the graphite nodule with the surface dust removed;
the physical property measurement and analysis device is used for measuring the physical properties of the graphite nodules with the surface dust removed.
Optionally, the numerical control integrated subsystem includes a radionuclide analysis signal processing module connected to the radionuclide measurement and analysis device, and the graphite nodule decontamination screening subsystem further includes a radioactive nodule shielding canister connected to the radionuclide measurement and analysis device; wherein the content of the first and second substances,
the radionuclide analysis signal processing module is used for comparing and analyzing the radionuclide measured value and the radionuclide standard value and feeding back an analysis result to the radionuclide measurement and analysis device;
the radionuclide measurement and analysis device is used for responding to the situation that the measured value of the radionuclide is larger than the standard value of the radionuclide, and the graphite ball is conveyed to the radioactive shielding can through the conveyor belt; and the graphite ball is also used for responding to the measured value of the radionuclide being less than or equal to the standard value of the radionuclide, and the graphite ball is transmitted to the physical characteristic measurement and analysis device through the conveyor belt.
Optionally, the numerical control integrated subsystem includes a physical property analysis signal processing module connected to the physical property measurement and analysis device, and the graphite nodule decontamination screening subsystem further includes a first collection tank and a second collection tank connected to the physical property measurement and analysis device; wherein the content of the first and second substances,
the physical characteristic analysis signal processing module is used for comparing and analyzing the physical characteristic measured value and the physical characteristic standard value and feeding back an analysis result to the physical characteristic measurement and analysis device;
the physical property measurement and analysis device is used for responding to the matching of the physical property measured value and the physical property standard value, and the graphite balls are conveyed to the first collection tank through the conveyor belt; and further for causing the graphite spheres to be conveyed via the conveyor belt to the second collection canister in response to the measured value of the radionuclide not matching the standard value of the radionuclide.
Optionally, the graphite nodule decontamination screening subsystem further comprises a driving motor arranged on the conveyor belt, and the numerical control integrated subsystem further comprises a driving motor rotation speed automatic adjustment signal processing module connected with the driving motor, the numerical control adjuster arranged on the conveyor belt, and a speed signal processing module connected with the numerical control adjuster;
the driving motor is used for driving the conveying belt to convey graphite balls;
the numerical control regulator is used for detecting an actual speed signal of the conveyor belt;
the speed signal processing module is used for comparing and analyzing the actual speed signal and a preset speed;
the automatic rotating speed adjusting signal processing module of the driving motor is used for adjusting the rotating speed of the driving motor according to the analysis result
Optionally, the system further includes a filtration auxiliary subsystem for filtering dust and polluted air generated in the process of removing the surface dust from the graphite nodules.
Optionally, the filtration auxiliary subsystem includes a filter and a differential pressure gauge, the filter is respectively connected to the graphite nodule feeder and the surface decontamination device, the differential pressure gauge is respectively connected to two ends of the filter, and the numerical control integrated subsystem further includes a differential pressure gauge signal processing module connected to the differential pressure gauge; wherein the content of the first and second substances,
the filter is used for filtering dust and polluted air on the surface of the graphite nodules;
the differential pressure meter is used for measuring the gas differential pressure at two ends of the filter and transmitting a differential pressure signal to the differential pressure meter signal processing module;
and the differential pressure gauge signal processing module is used for comparing and analyzing the differential pressure signal and a differential pressure preset value and processing the filter according to an analysis result.
Optionally, the filtration auxiliary subsystem further includes: the system comprises a gas driving device, a gas radiation monitoring device and a valve assembly, wherein two ends of the gas driving device are respectively connected with a filter and the gas radiation monitoring device; wherein the content of the first and second substances,
the gas driving device is used for providing driving force for the filter so as to drive the filtered gas to enter the gas radiation monitoring device;
the gas radiation monitoring device is used for monitoring the activity value of the gas and feeding back the activity monitoring value to the gas radiation monitoring signal processing module;
the gas radiation monitoring signal processing module is used for comparing and analyzing the activity monitoring value and the activity standard value and transmitting an analysis result to the valve assembly;
and the valve assembly is used for opening or closing according to the analysis result so as to correspondingly process the gas.
Optionally, the valve assembly comprises a first electric valve and a second electric valve;
when the activity monitoring value is matched with the activity standard value, the first electric valve is opened, and the second electric valve is closed, so that the gas is exhausted to the atmosphere;
and when the activity monitoring value is not matched with the activity standard value, the second electric valve is opened, and the first electric valve is closed, so that the gas is transmitted to the filter.
In another aspect of the present invention, a method for cleaning and screening the surface of a graphite sphere in a high temperature gas cooled reactor is provided, which comprises the following steps:
removing dust on the surface of graphite nodules, and measuring the radioactive nuclides and physical properties of the graphite nodules after dust removal;
filtering dust and polluted air generated in the process of removing dust on the surface of the graphite nodules;
and screening the graphite nodules according to the measured values of the radionuclide and the measured values of the physical property.
The invention provides a high-temperature gas cooled reactor graphite nodule surface decontamination screening system and a method thereof, wherein the system comprises: a graphite nodule decontamination screening subsystem and a numerical control integrated subsystem connected with the graphite nodule decontamination screening subsystem; the graphite nodule decontaminating and screening subsystem is used for removing dust on the surface of graphite nodules and measuring the radionuclides and physical characteristics of the graphite nodules after dust removal; and the numerical control integrated subsystem is used for screening the graphite nodules according to the measurement values of the radioactive nuclides and the measurement values of the physical characteristics. The invention provides a graphite nodule decontamination, radioactivity monitoring and physical property automatic analysis, measurement and screening system for a high-temperature gas cooled reactor, which has the functions of graphite nodule surface decontamination, radionuclide measurement and analysis, physical property monitoring, numerical control integrated automatic regulation and control and the like, greatly reduces the risks of external irradiation, internal irradiation and air pollution diffusion generated in the graphite nodule decontamination process, and greatly reduces the risk of radioactive pollution diffusion.
Drawings
Fig. 1 is a schematic structural diagram of a high temperature gas cooled reactor graphite nodule surface decontamination screening system according to an embodiment of the present invention;
fig. 2 is a block flow diagram of a high temperature gas cooled reactor graphite sphere surface decontamination screening method according to another embodiment of the present invention.
Detailed Description
In order to make the technical solutions of the present invention better understood, the present invention will be described in further detail with reference to the accompanying drawings and specific embodiments. It is to be understood that the embodiments described are only a few embodiments of the present invention, and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the invention without any inventive step, are within the scope of protection of the invention.
Unless otherwise specifically stated, technical or scientific terms used herein shall have the ordinary meaning as understood by those of ordinary skill in the art to which this invention belongs. The use of "including" or "comprising" and the like in the present application does not limit the presence or addition of one or more other shapes, numbers, steps, actions, operations, elements, components and/or groups thereof to those mentioned or to other different shapes, numbers, steps, actions, operations, elements, components and/or groups thereof. Furthermore, the terms "first" and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number and order of the indicated features.
In one aspect of the present invention, a high temperature gas cooled reactor graphite nodule surface decontamination screening system is provided, which includes: a graphite nodule decontamination screening subsystem and a numerical control integrated subsystem connected with the graphite nodule decontamination screening subsystem; the system comprises a graphite nodule decontamination screening subsystem, a data processing subsystem and a data processing subsystem, wherein the graphite nodule decontamination screening subsystem is used for removing dust on the surface of a graphite nodule and measuring radionuclide and physical characteristics of the graphite nodule after the dust is removed; and the numerical control integrated subsystem is used for screening the graphite nodules according to the measurement values of the radioactive nuclides and the measurement values of the physical characteristics.
The embodiment provides a graphite nodule decontamination, radioactivity monitoring and physical characteristic automatic analysis, measurement and screening system for a high-temperature gas cooled reactor, which can remove graphite dust stained on the surface of graphite nodules, greatly reduce the radioactivity of the graphite nodules, and reduce the generation amount and disposal cost of radioactive solid wastes. On the other hand, the method can be used for new reactor charging of a subsequent high-temperature gas cooled reactor by detecting the radionuclide discharged from the graphite nodules and screening and measuring physical properties such as appearance size, weight, scratch and the like, so that the reuse of the graphite nodules is realized.
Specifically, as shown in fig. 1, the graphite nodule decontaminating and screening subsystem of the present embodiment includes: the device comprises a graphite nodule feeder 1, a surface decontamination device 4, a radionuclide measuring and analyzing device 12 and a physical characteristic measuring and analyzing device 17 which are sequentially connected through a conveyor belt, wherein the conveyor belt is used for sequentially conveying graphite nodules from the graphite nodule feeder 1 to the surface decontamination device 4, the radionuclide measuring and analyzing device 12 and the physical characteristic measuring and analyzing device 17. And the surface decontamination device 4 is used for removing the surface dust of the graphite nodules. And a radionuclide measurement and analysis device 12 for measuring the radionuclide of the graphite nodule from which the surface dust is removed. And a physical property measurement and analysis device 17 for measuring the physical properties of the graphite nodules from which the surface dust is removed.
It should be noted that the conveyor belt of the present embodiment is not particularly limited, and may be specifically configured according to different needs, for example, a crawler belt is used.
Illustratively, as shown in fig. 1, a conveyor belt between a graphite ball feeder 1 and a surface decontamination device 4 is provided as a crawler belt 3, the crawler belt 3 is also connected with a crawler belt driving motor 2, and the graphite ball crawler belt 3 is driven by the crawler belt driving motor 2 to transport graphite balls from the graphite ball feeder 1 to the surface decontamination device 4.
It should be noted that, the graphite nodule feeder of this embodiment adopts a funnel type design, and graphite nodules in different numbers can be fed according to actual needs, and the inner diameter of the funnel mouth at the bottom of the funnel mouth is slightly larger than the diameter of the graphite nodule by 10mm, and is spaced from the height of the diameter of the graphite nodule by about 1.5, so as to allow the graphite nodule to be individually output to the track.
It should be further noted that the numerical control integrated subsystem of this embodiment is connected to the graphite nodule decontamination subsystem through corresponding signal transmission lines by the numerical control integrated device, and the signal transmission lines all use R485 communication lines. And the numerical control integrated device comprises 11 signal processing modules, and each signal processing module corresponds to one signal output structure.
Specifically, as shown in fig. 1, the numerical control integrated device 24 includes a track driving motor rotation speed automatic adjustment signal processing module 24-1 connected to the track driving motor 2, and the module receives/feeds back a motor rotation speed signal of the track driving motor 2 through a motor rotation speed signal transmission line 25. The module can analyze in real time and automatically adjust the rotating speed of the crawler driving motor 2 according to the set graphite nodule detection speed, and the requirement of detection speed is met.
Further, with continued reference to fig. 1, the nc integrated subsystem further includes a track speed controller 5 and a track speed signal processing module 24-6 connected to the track speed controller 5, wherein the track speed controller 5 is disposed on the track between the surface decontamination apparatus 4 and the radionuclide measurement and analysis apparatus 12, and the track speed signal processing module 24-6 receives the track speed signal from the track speed controller 5 via a track speed signal transmission line 30. The module can analyze the track speed in real time according to the set graphite nodule detection speed, namely, the actually detected speed and the preset speed are contrasted and analyzed, the analysis result is fed back to the automatic rotating speed adjusting signal processing module 24-1 of the track driving motor, and then the rotating speed of the track driving motor 2 is automatically adjusted, so that the requirement of the graphite nodule detection speed is met.
In some preferred embodiments, the inside of the surface decontamination device is provided with a roller and a brush component, so that graphite balls are subjected to ball milling and ball wall friction in the roller, dust generated by the friction is simultaneously ground by the brush, and the ground and smooth graphite balls are conveyed to the radionuclide measurement and analysis device.
Further, as shown in fig. 1, the graphite nodule decontamination screening subsystem further includes a radioactive nodule shielding canister 15 connected to the radionuclide measurement and analysis device 12, the numerical control integration subsystem includes a radionuclide analysis signal processing module 24-7 connected to the radionuclide measurement and analysis device 12, the two are connected by a radionuclide monitoring and analysis data signal transmission line 31, the radionuclide analysis signal processing module 24-7 is integrated in the numerical control integration device 24, wherein the radionuclide measurement and analysis device 12 can perform measurement and analysis on the composition of the radionuclide in the graphite nodule and transmit the measured value of the radionuclide to the numerical control integration device 24 through the radionuclide monitoring and analysis data signal transmission line 31, the radionuclide analysis signal processing module 24-7 is used for comparing and analyzing the measured value of the radionuclide with the standard value of the radionuclide, and feeds back the analysis result to the radionuclide measurement analysis device 12. The radionuclide measurement and analysis device 12 is used for responding to the situation that the measured value of the radionuclide is larger than the standard value of the radionuclide, and the graphite nodules are conveyed to the radioactive shielding tank 15 through a conveyor belt; and is also used for transmitting the graphite nodules to the physical property measurement and analysis device 17 through the transmission belt in response to the measured value of the radionuclide being less than or equal to the standard value of the radionuclide.
It should be noted that the graphite nodules are treated according to whether they have radioactivity, so that the conveyor belt connecting the radioactive shielding canister and the radionuclide measurement and analysis apparatus uses the radioactive nodule conveying crawler belt to convey the radioactive graphite nodules to the radioactive shielding canister. Further, a conveyor belt connecting the physical property measurement and analysis device and the radionuclide measurement and analysis device uses a non-radioactive sphere conveying crawler belt to convey graphite spheres having no radioactivity to the physical property measurement and analysis device.
In some preferred embodiments, the physical property measurement and analysis device may use an X-ray machine, and the X-ray machine performs measurement and analysis on physical properties such as surface cracks and traces, graphite nodule diameter, and the like on the single graphite nodule.
Illustratively, as shown in fig. 1, the radionuclide analysis signal processing module 24-7 receives the measurement value of the composition of the radionuclide in the graphite nodule from the radionuclide measurement and analysis device 12 through a radionuclide monitoring analysis data signal transmission line 31. The module analyzes and compares the measured value of the radionuclide in the single graphite nodule with the activity and specific activity exemption value (radionuclide standard value) of the radionuclide in the national standard, and if the measured value of the radionuclide in the single graphite nodule meets the activity and specific activity exemption requirement of the radionuclide in the national standard, the measured value is transmitted to an X-ray machine through a non-radioactive sphere conveying crawler 16 to perform physical characteristic measurement and analysis; if the measured value of the radioactive nuclide in the single graphite nodule is larger than the exemption requirement in the national standard, the radioactive nuclide is conveyed to the radioactive nodule shielding tank 15 through the radioactive nodule conveying crawler 13.
Furthermore, as shown in fig. 1, the numerical control integrated subsystem of this embodiment further includes a physical characteristic analysis signal processing module 24-8 connected to the physical characteristic measurement and analysis device 17, and the physical characteristic analysis signal processing module 24-8 is integrated in the numerical control integrated device 24 and connected via a physical characteristic analysis signal transmission line 32. The graphite nodule decontamination screening subsystem further comprises a first collecting tank 23 and a second collecting tank 20 which are connected with the physical property measurement and analysis device 17; the physical characteristic analysis signal processing module 24-8 is configured to compare and analyze the physical characteristic measurement value with the physical characteristic standard value, and feed back an analysis result to the physical characteristic measurement and analysis device 17. Meanwhile, the physical property measurement and analysis device 17 is configured to, in response to a match between the physical property measurement value and the physical property standard value, transfer the graphite balls to the first collection tank 23 via the conveyor belt, that is, the first collection tank corresponds to a physical property-qualified ball collection tank. And the physical characteristic measurement and analysis device 17 is also used for responding to the measured value of the radionuclide and the standard value of the radionuclide when not matching, and transmitting the graphite balls to a second collection tank 20 through a conveyor belt, wherein the second collection tank is equivalent to a physical characteristic unqualified ball collection tank.
It should be noted that, according to whether the physical characteristics of the graphite nodules meet the standard or not, the graphite nodules are correspondingly processed, so that the conveyor belt connecting the first collecting tank with the physical characteristic measuring and analyzing device adopts a qualified nodule conveying crawler belt to convey the qualified graphite nodules to the first collecting tank. In addition, the conveyer belt connecting the physical property measuring and analyzing device with the second collecting tank adopts an unqualified ball conveying crawler belt so as to convey unqualified graphite balls to the second collecting tank.
It should be further noted that, when the physical characteristic measuring and analyzing device adopts an X-ray machine, the corresponding physical characteristic analyzing signal processing module is an X-ray machine analyzing signal processing module, and a signal transmission line between the module and the X-ray machine is an X-ray machine analyzing signal transmission line.
For example, as shown in fig. 1, the X-ray machine analysis signal transmission processing module receives a physical characteristic analysis data signal of a single graphite nodule from the X-ray machine through the X-ray machine analysis signal transmission line. The X-ray machine analysis signal transmission processing module analyzes and compares the surface crack and crack, the graphite nodule diameter signal and the specific requirements of the graphite nodule purchasing technical standard and feeds back the analysis result signal to the X-ray machine. If the surface cracks, scratches and diameters of the single graphite nodule meet the technical standard requirements of graphite nodule purchase, the single graphite nodule is conveyed to a qualified nodule collecting tank, namely a first collecting tank 23, through a qualified nodule conveying crawler 21; if the surface cracks, scratches and diameters in the single graphite nodules do not meet the requirements of the graphite nodule purchasing technical standard, the graphite nodules are conveyed to a ball collecting tank with unqualified physical characteristics, namely a second collecting tank 20 through a ball conveying crawler 18 with unqualified physical characteristics.
Further, as shown in fig. 1, the graphite nodule decontamination screening subsystem further comprises a first counter 14, a second counter 19, and a third counter 22, wherein the first counter 14 is disposed on the radioactive nodule transport track 13 for counting the number of graphite nodules transported into the radioactive nodule shielding can 15. A second counter 19 is provided on the physically defective ball conveying crawler 18 to count the defective graphite balls conveyed into the second collection tank 20. The third counter 22 is provided on the qualified graphite nodule conveying crawler 21 to count the qualified graphite nodules conveyed into the first collecting tank 23, so as to count the number of the graphite nodules.
Correspondingly, as shown in fig. 1, the numerical control integration device 24 is correspondingly provided with a first counter signal processing unit 24-9, a second counter signal processing unit 24-10, and a third counter signal processing unit 24-11, which respectively receive graphite nodule number signals from the first counter 14, the second counter 19, and the third counter 22 through a first counter signal transmission line 33, a second counter signal transmission line 34, and a third counter signal transmission line 35, count graphite nodule data entering the radioactive nodule shielding tank 15, the second collection tank 20, and the first collection tank 23, and respectively display a preset graphite nodule detection number, a graphite nodule total number, a qualified nodule number, a radioactive graphite nodule number, and a physical characteristic unqualified nodule number.
Furthermore, the system of this embodiment still includes and filters auxiliary subsystem for get rid of the dust and the contaminated air that produce in the surface dust process to the graphite nodule and filter, carry out the developments to the radioactive gas after the graphite nodule decontamination and purify, saved taking of SAS canopy and torn open the work, reduced the process, greatly reduced the internal exposure risk of collective, show improvement work efficiency. That is to say, the system of this embodiment comprises graphite nodule decontamination screening main system, filtration auxiliary subsystem, numerical control integration subsystem, has functions such as graphite nodule surface decontamination, radionuclide measurement analysis, physical characteristics monitoring such as surface mar and diameter, dust and air automatic filtration, numerical control integration automatically regulated and control, has greatly reduced external irradiation, interior irradiation and air pollution diffusion risk that graphite nodule decontamination in-process produced.
Specifically, as shown in fig. 1, the filtration auxiliary subsystem comprises a filter 6 and a differential pressure gauge 7, and the filter 6 is respectively connected with the graphite nodule feeder 1 and the surface decontamination device 4 through air ducts to remove dust generated in the graphite nodule dust removal process. The differential pressure meter 7 is respectively connected with two ends of the filter 6, and the numerical control integrated device 24 comprises a differential pressure meter signal processing module 24-2 connected with the differential pressure meter 7; the filter is used for filtering dust and polluted air on the surface of the graphite nodules; the differential pressure meter is used for measuring the gas differential pressure at the two ends of the filter and transmitting a differential pressure signal to the differential pressure meter signal processing module 24-2; and the differential pressure gauge signal processing module 24-2 is used for comparing and analyzing the differential pressure signal with a differential pressure preset value and processing the filter according to an analysis result.
It should be noted that the filter of this embodiment is provided with an activated carbon dust filter material and an iodine adsorbing material inside, and can filter dust and polluted air generated during the process of cleaning and rubbing the graphite surface.
Illustratively, as shown in FIG. 1, a pressure differential gauge 7 is connected across the filter 6 by a sampling gas capillary. The differential pressure meter 7 can monitor the pressure difference of the dust and the gas at the two ends of the air filter, and transmits the signal to the differential pressure meter signal processing module 24-2 in the numerical control integrated device 24 through a differential pressure signal transmission line 26. The module receives the differential pressure signal transmitted by the differential pressure gauge 7 and then carries out processing, analysis and judgment. The differential pressure signal processing module 24-2 receives/feeds back the differential pressure signal from the differential pressure gauge 7 through the differential pressure signal transmission line 26. After the module processes, analyzes and judges the differential pressure signal, if the differential pressure is larger than a differential pressure design value required by the filtering performance of the filter 6, the module reminds that the dust and air filter needs to be replaced; if the differential pressure is smaller than the designed differential pressure value required by the filtering performance of the filter 6, the filtering performance of the filter 6 for dust and air is satisfied.
Further, as shown in fig. 1, the filter auxiliary subsystem of this embodiment further includes: the device comprises a gas driving device 8, a gas radiation monitoring device 9 and a valve assembly, wherein two ends of the gas driving device 8 are respectively connected with a filter 6 and the gas radiation monitoring device 9, and a numerical control integrated device 24 comprises a gas radiation monitoring signal processing module 24-3 which is connected with the gas radiation monitoring device 9 and the valve assembly; the gas driving device 8 is used for providing driving force for the filter so as to drive the filtered gas to enter the gas radiation monitoring device; the gas radiation monitoring device 9 is used for monitoring the activity value of the gas and feeding back the activity monitoring value to the gas radiation monitoring signal processing module 24-3; the gas radiation monitoring signal processing module 24-3 is used for comparing and analyzing the activity monitoring value and the activity standard value and transmitting the analysis result to the valve assembly; the valve assembly is used for opening or closing according to the analysis result so as to perform corresponding treatment on the gas.
It should be noted that the air driving device of the present embodiment may adopt a fan, and the fan provides air driving for the dust and air filtering auxiliary subsystem. Filtered gas enters the gas radiation monitoring device under the driving of the fan to be subjected to aerosol and inert gas activity monitoring, an activity monitoring value is transmitted to the numerical control integrated device through the gas radiation monitoring signal transmission line, and the numerical control integrated device is subjected to processing and analysis after receiving an activity monitoring value signal.
For example, as shown in fig. 1, the valve assembly includes a first electric valve 10 and a second electric valve 11, the numerical control integrated device 24 includes a first electric valve signal processing module 24-4 and a second electric valve signal processing module 24-5, which can receive the analysis result signal of the gas radiation monitoring signal processing module 24-3, and control the opening or closing of the first electric valve 10 and the second electric valve 11 through a first electric valve signal transmission line 28 and a second electric valve signal transmission line 29; at the same time, the opening and closing states of the first electric valve 10 and the second electric valve 11 can be received in real time.
Specifically, as shown in fig. 1, the gas radiation monitoring signal processing module 24-3 receives/feeds back the monitoring value signals of the activity of the aerosol and the inert gas from the gas radiation monitoring device 9 through a gas radiation monitoring signal transmission line 27. The module carries out processing analysis after receiving the activity monitoring value signal, if the activity monitoring value meets the requirements of the national gaseous radioactive effluent discharge standard, the analysis result signal is fed back to the first electric valve 10 and the second electric valve 11 through the first electric valve signal processing module 24-4 and the second electric valve signal processing module 24-5 respectively, the first electric valve 10 is controlled to be opened, the second electric valve 11 is controlled to be closed, and the filtered gas is discharged to the atmosphere. If the activity monitoring value does not meet the requirements of the national emission standard of the gaseous radioactive effluents, the analysis result signals are respectively fed back to the first electric valve 10 through the first electric valve signal processing module 24-4 and the second electric valve signal processing module 24-5, the first electric valve 10 is closed, the second electric valve 11 is opened, and the radioactive gases which do not meet the emission requirements enter the dust and air filter again for filtering until the activity value meets the requirements of the emission standard and then are discharged to the atmosphere.
The invention provides a graphite nodule decontamination, radioactivity monitoring and physical property measuring system for a high-temperature gas cooled reactor, which has the functions of graphite nodule surface decontamination, radionuclide measurement and analysis, physical property monitoring such as surface scratches and diameters, automatic dust and air filtration, numerical control integrated automatic regulation and control and the like, and is used for graphite nodule decontamination screening multiplexing technology for reactor core unloading of the high-temperature gas cooled reactor.
As shown in fig. 2, in another aspect of the present invention, a method S200 for cleaning and screening the surface of graphite spheres in a high temperature gas cooled reactor is provided, which includes the following steps S210 to S230:
s210, removing dust on the surface of the graphite nodule, and measuring the radionuclide and physical properties of the graphite nodule after dust removal.
In the present embodiment, the dust on the surface of the graphite nodule is removed based on the system described above, and the radionuclide activity automatic monitoring and the physical characteristic parameter monitoring are performed on the graphite nodule after the dust is removed.
S220, filtering dust and polluted air generated in the process of removing the dust on the surface of the graphite nodules.
Specifically, in order to reduce the dust diffusion risk that produces among the graphite nodule decontamination process, still further get rid of dust and contaminated air, carry out the dynamic purification to the radioactive gas after the graphite nodule decontamination, saved taking of SAS canopy and torn open the work, reduced the process, greatly reduced the internal exposure risk of collective, show improvement work efficiency.
And S230, screening the graphite nodules according to the measured values of the radioactive nuclides and the measured values of the physical properties.
Specifically, in this embodiment, the graphite nodules are screened according to the measured values of the radionuclides obtained in step S210, and by determining the radionuclide values of the graphite nodules, the graphite nodules without radioactivity are sent to the physical property measurement and analysis device for the next analysis and detection of the physical properties, and the graphite nodules with radioactivity are sent to the radioactive nodule shielding canister. Further, the graphite nodules are screened according to the measured values of the physical characteristics, the physical characteristics of the graphite nodules are judged, the unqualified graphite nodules are conveyed to the unqualified collecting tank, and the qualified graphite nodules are conveyed to the qualified collecting tank.
The physical properties of the present embodiment include surface cracks, scratches, diameters, and the like.
The high temperature gas cooled reactor graphite nodule surface decontamination screening system and method will be further described with reference to several embodiments:
example 1
The present example uses the apparatus of the present invention to perform decontamination screening on graphite nodules discharged from an HTR-PM core, and the main purpose of the present example application is to perform decontamination screening operation on 2 ten thousand graphite nodules discharged from an HTR-PM core by using the integrated apparatus, and the specific steps include:
(1) and finishing field arrangement: a graphite ball feeder is connected to a graphite ball pipe behind a graphite ball rechecking device of the fuel loading and unloading system, the integrated system is started, and the detection speed is set to be 50 balls/hour on the numerical control integrated device 24;
(2) the discharged graphite nodules enter a graphite nodule feeder 1, sequentially fall onto a crawler 3, and enter a surface decontamination device 4 of the graphite nodules under the driving of the crawler;
(3) a roller and an electric brush are arranged in the surface decontamination device 4 to polish the graphite balls smoothly; meanwhile, the dust and the radioactive gas enter the dust and air filter 6 for purification, and the first electric valve 10 is opened to be discharged into the atmosphere after the gas meets the emission standard;
(4) the decontaminated graphite nodules are transported to a radionuclide measurement and analysis device 12. The radionuclide measurement and analysis device 12 measures and analyzes the composition of the radioactive nuclides in the graphite nodules, and transmits the measured values of the radioactive nuclides to the numerical control integration device 24 through a radioactive nuclide monitoring and analysis data signal transmission line 31;
(5) the numerical control integration device 24 feeds back the radionuclide analysis comparison result signal to the radionuclide measurement analysis device. And (6) or (7) according to the analysis result.
(6) If the radionuclide measurement value in the single graphite sphere meets the radioactive nuclide activity and specific activity exemption requirements in the national standard, the radionuclide measurement value is transmitted to an X-ray machine through a non-radioactive sphere conveying crawler 16 to be subjected to physical characteristic measurement and analysis;
(7) if the measured value of the radioactive nuclide in the single graphite nodule is greater than the exemption requirement in the national standard, the radioactive nuclide is conveyed to the radioactive nodule shielding tank 15 through the radioactive nodule conveying crawler 13, and the screening work of the single graphite nodule is finished;
(8) the graphite nodules completing the process (6) enter an X-ray machine, physical characteristics such as surface cracks and traces and graphite nodule diameter are measured and analyzed on a single graphite nodule, and the physical characteristic analysis signals are transmitted to the numerical control integration device 24 through an X-ray machine analysis signal transmission line.
(9) The numerical control integrated device 24 feeds back the analysis result signals of the surface cracks and the diameter of the graphite nodules to the X-ray machine. And respectively entering the flow (10) or the flow (11) according to the analysis result.
(10) If the surface cracks, scratches and diameters of the single graphite nodule meet the technical standard requirements of graphite nodule purchase, the single graphite nodule is conveyed to a qualified nodule collecting tank, namely a first collecting tank 23, through a qualified nodule conveying crawler 21, and the graphite nodule screening work flow is finished;
(11) if the surface cracks, scratches and diameters in the single graphite nodule do not meet the purchasing technical standard requirements of the graphite nodule, the graphite nodule is conveyed to a graphite nodule collecting tank with unqualified physical characteristics, namely a second collecting tank 20 through a graphite nodule conveying crawler 18 with unqualified physical characteristics, and the screening work flow of the single graphite nodule is finished.
(12) And (5) repeating the steps (2) to (11) until the number of the graphite nodules displayed by the numerical control integrated device 24 is 2 ten thousand, and ending the work.
The invention provides a system and a method for decontaminating and screening the surface of graphite nodules of a high-temperature gas cooled reactor, which have the following beneficial effects: the system and the method have the functions of graphite nodule surface decontamination, radionuclide measurement and analysis, physical characteristic monitoring such as surface scratch and diameter, automatic dust and air filtration, numerical control integrated automatic regulation and control and the like, and greatly reduce the risks of external irradiation, internal irradiation and air pollution diffusion generated in the graphite nodule decontamination process. The staff takes simple external irradiation and internal irradiation protective measures to carry out closed graphite nodule decontamination sorting production line automatic operation through the system integration device, and greatly reduces the risk of radioactive contamination diffusion. Meanwhile, the dust and air filtration auxiliary subsystem is designed to dynamically purify radioactive gas after graphite nodule decontamination, so that the work of assembling and disassembling an SAS shed is omitted, the working procedures are reduced, the risk of irradiation in a collective body is greatly reduced, and the working efficiency is obviously improved.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and scope of the invention, and such modifications and improvements are also considered to be within the scope of the invention.
Claims (10)
1. The utility model provides a high temperature gas cooled reactor graphite nodule surface decontamination screening system which characterized in that includes: a graphite nodule decontamination screening subsystem and a numerical control integrated subsystem connected with the graphite nodule decontamination screening subsystem; wherein, the first and the second end of the pipe are connected with each other,
the graphite nodule decontaminating and screening subsystem is used for removing dust on the surface of graphite nodules and measuring radionuclide and physical properties of the graphite nodules after dust removal;
and the numerical control integrated subsystem is used for screening the graphite nodules according to the measurement values of the radioactive nuclides and the measurement values of the physical characteristics.
2. The system of claim 1, wherein the graphite nodule decontaminating screening subsystem comprises: the device comprises a graphite ball feeder, a surface decontamination device, a radionuclide measurement and analysis device and a physical characteristic measurement and analysis device which are sequentially connected through a conveyor belt;
the conveying belt is used for conveying the graphite nodules from the graphite nodule feeder to the surface decontamination device, the radionuclide measurement and analysis device and the physical characteristic measurement and analysis device in sequence;
the surface decontamination device is used for removing surface dust of the graphite nodules;
the radionuclide measurement and analysis device is used for measuring the radionuclide of the graphite nodule with the surface dust removed;
the physical property measurement and analysis device is used for measuring the physical property of the graphite nodules with the surface dust removed.
3. The system of claim 2 wherein the digitally controlled integrated subsystem includes a radionuclide analysis signal processing module coupled to the radionuclide measurement and analysis device, the graphite nodule decontamination screening subsystem further including a radioactive nodule shielding canister coupled to the radionuclide measurement and analysis device; wherein, the first and the second end of the pipe are connected with each other,
the radionuclide analysis signal processing module is used for comparing and analyzing the measured value of the radionuclide with a standard value of the radionuclide and feeding back the analysis result to the radionuclide measurement and analysis device;
the radionuclide measurement and analysis device is used for responding to the situation that the measured value of the radionuclide is larger than the standard value of the radionuclide, and the graphite ball is conveyed to the radioactive shielding can through the conveyor belt; and the graphite ball is also used for responding to the measured value of the radionuclide being less than or equal to the standard value of the radionuclide, and the graphite ball is transmitted to the physical characteristic measurement and analysis device through the conveyor belt.
4. The system of claim 2, wherein the numerically controlled integrated subsystem comprises a physical property analysis signal processing module coupled to the physical property measurement and analysis device, and the graphite nodule decontamination screening subsystem further comprises a first collection tank and a second collection tank coupled to the physical property measurement and analysis device; wherein the content of the first and second substances,
the physical characteristic analysis signal processing module is used for comparing and analyzing the physical characteristic measured value and the physical characteristic standard value and feeding back an analysis result to the physical characteristic measurement and analysis device;
the physical property measurement and analysis device is used for responding to the matching of the physical property measured value and the physical property standard value, and the graphite balls are conveyed to the first collection tank through the conveyor belt; and further for causing the graphite spheres to be conveyed via the conveyor belt to the second collection canister in response to the measured value of the radionuclide not matching the standard value of the radionuclide.
5. The system according to claim 2, wherein the graphite nodule decontamination screening subsystem further comprises a driving motor arranged on the conveyor belt, the numerical control integration subsystem further comprises a driving motor rotation speed automatic adjusting signal processing module connected with the driving motor, the numerical control adjuster arranged on the conveyor belt, and a speed signal processing module connected with the numerical control adjuster;
the driving motor is used for driving the conveying belt to convey graphite balls;
the numerical control regulator is used for detecting an actual speed signal of the conveyor belt;
the speed signal processing module is used for comparing and analyzing the actual speed signal and a preset speed;
and the automatic rotating speed adjusting signal processing module of the driving motor is used for adjusting the rotating speed of the driving motor according to the analysis result.
6. The system of any one of claims 2 to 5, further comprising a filtration assistance subsystem for filtering dust and contaminated air generated during the graphite nodule surface dust removal process.
7. The system of claim 6, wherein the filtration auxiliary subsystem comprises a filter and a differential pressure gauge, the filter is respectively connected with the graphite nodule feeder and the surface decontamination device, the differential pressure gauge is respectively connected with two ends of the filter, and the numerical control integrated subsystem further comprises a differential pressure gauge signal processing module connected with the differential pressure gauge; wherein the content of the first and second substances,
the filter is used for filtering dust and polluted air on the surface of the graphite nodules;
the differential pressure meter is used for measuring the gas differential pressure at two ends of the filter and transmitting a differential pressure signal to the differential pressure meter signal processing module;
and the differential pressure gauge signal processing module is used for comparing and analyzing the differential pressure signal and a differential pressure preset value and processing the filter according to an analysis result.
8. The system of claim 7, wherein the filtration assistance subsystem further comprises: the system comprises a gas driving device, a gas radiation monitoring device and a valve assembly, wherein two ends of the gas driving device are respectively connected with a filter and the gas radiation monitoring device; wherein the content of the first and second substances,
the gas driving device is used for providing driving force for the filter so as to drive the filtered gas to enter the gas radiation monitoring device;
the gas radiation monitoring device is used for monitoring the activity value of the gas and feeding back the activity monitoring value to the gas radiation monitoring signal processing module;
the gas radiation monitoring signal processing module is used for comparing and analyzing the activity monitoring value and the activity standard value and transmitting an analysis result to the valve assembly;
and the valve assembly is used for opening or closing according to the analysis result so as to correspondingly process the gas.
9. The system of claim 8, wherein the valve assembly comprises a first electrically operated valve and a second electrically operated valve;
when the activity monitoring value is matched with the activity standard value, the first electric valve is opened, and the second electric valve is closed, so that the gas is exhausted to the atmosphere;
and in response to the activity monitoring value not matching the activity standard value, opening the second electrically operated valve and closing the first electrically operated valve to deliver the gas to the filter.
10. The surface decontamination screening method of the graphite ball of the high-temperature gas cooled reactor is characterized by comprising the following steps:
removing dust on the surface of graphite nodules, and measuring the radioactive nuclides and physical properties of the graphite nodules after dust removal;
filtering dust and polluted air generated in the process of removing dust on the surface of the graphite nodules;
and screening the graphite nodules according to the measured values of the radionuclide and the measured values of the physical property.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210386514.XA CN115055392A (en) | 2022-04-14 | 2022-04-14 | High-temperature gas cooled reactor graphite nodule surface decontamination screening system and method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210386514.XA CN115055392A (en) | 2022-04-14 | 2022-04-14 | High-temperature gas cooled reactor graphite nodule surface decontamination screening system and method |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN115055392A true CN115055392A (en) | 2022-09-16 |
Family
ID=83197117
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210386514.XA Pending CN115055392A (en) | 2022-04-14 | 2022-04-14 | High-temperature gas cooled reactor graphite nodule surface decontamination screening system and method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN115055392A (en) |
Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH09122589A (en) * | 1995-09-01 | 1997-05-13 | Fuji Electric Co Ltd | Sorter of fuel pellet for atomic reactor |
| DE19824039A1 (en) * | 1998-05-29 | 1999-12-09 | Nukem Hanau Gmbh | Testing for excessive radionuclide content in bulk rubble or earth, especially when decommissioning nuclear plant |
| JP2003014890A (en) * | 2001-06-28 | 2003-01-15 | Toshiba Corp | Disposal method for radioactivated graphite and its system |
| JP2004170282A (en) * | 2002-11-21 | 2004-06-17 | Fuji Electric Systems Co Ltd | Laundry monitor |
| JP2007007547A (en) * | 2005-06-30 | 2007-01-18 | Nuclear Fuel Ind Ltd | Sphericity sorting apparatus of fuel particle |
| US20110295537A1 (en) * | 2010-05-25 | 2011-12-01 | Battelle Energy Alliance, Llc | Apparatus and method for radioactive waste screening |
| CN102692192A (en) * | 2012-05-31 | 2012-09-26 | 清华大学 | System and method for detecting diameter of spherical workpiece |
| CN103817089A (en) * | 2014-02-28 | 2014-05-28 | 清华大学 | Automatic detection system and method for spherical fuel element fuel-free section |
| CN105448372A (en) * | 2014-08-12 | 2016-03-30 | 中核核电运行管理有限公司 | Method for cleaning and releasing control of discarded air cleaner metal frameworks in nuclear power plant |
| JP2016075628A (en) * | 2014-10-08 | 2016-05-12 | 鹿島建設株式会社 | Radioactivity concentration measurement device and sorting device |
| CN108565036A (en) * | 2018-02-27 | 2018-09-21 | 中国人民解放军61489部队 | Equipment and sweep-out method are quickly removed in a kind of hard dielectric surface radioactive contamination |
| CN110314456A (en) * | 2019-07-09 | 2019-10-11 | 江苏中海华核环保有限公司 | For the radioactive spent resin effective filter that treated is vented |
| CN112992393A (en) * | 2021-03-10 | 2021-06-18 | 华能山东石岛湾核电有限公司 | Radioactive graphite nodule suction device for high-temperature gas cooled reactor |
| CN114334201A (en) * | 2022-01-11 | 2022-04-12 | 西安热工研究院有限公司 | High temperature gas cooled reactor fuel ball integrity detection device based on X-ray tomography |
-
2022
- 2022-04-14 CN CN202210386514.XA patent/CN115055392A/en active Pending
Patent Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH09122589A (en) * | 1995-09-01 | 1997-05-13 | Fuji Electric Co Ltd | Sorter of fuel pellet for atomic reactor |
| DE19824039A1 (en) * | 1998-05-29 | 1999-12-09 | Nukem Hanau Gmbh | Testing for excessive radionuclide content in bulk rubble or earth, especially when decommissioning nuclear plant |
| JP2003014890A (en) * | 2001-06-28 | 2003-01-15 | Toshiba Corp | Disposal method for radioactivated graphite and its system |
| JP2004170282A (en) * | 2002-11-21 | 2004-06-17 | Fuji Electric Systems Co Ltd | Laundry monitor |
| JP2007007547A (en) * | 2005-06-30 | 2007-01-18 | Nuclear Fuel Ind Ltd | Sphericity sorting apparatus of fuel particle |
| US20110295537A1 (en) * | 2010-05-25 | 2011-12-01 | Battelle Energy Alliance, Llc | Apparatus and method for radioactive waste screening |
| CN102692192A (en) * | 2012-05-31 | 2012-09-26 | 清华大学 | System and method for detecting diameter of spherical workpiece |
| CN103817089A (en) * | 2014-02-28 | 2014-05-28 | 清华大学 | Automatic detection system and method for spherical fuel element fuel-free section |
| CN105448372A (en) * | 2014-08-12 | 2016-03-30 | 中核核电运行管理有限公司 | Method for cleaning and releasing control of discarded air cleaner metal frameworks in nuclear power plant |
| JP2016075628A (en) * | 2014-10-08 | 2016-05-12 | 鹿島建設株式会社 | Radioactivity concentration measurement device and sorting device |
| CN108565036A (en) * | 2018-02-27 | 2018-09-21 | 中国人民解放军61489部队 | Equipment and sweep-out method are quickly removed in a kind of hard dielectric surface radioactive contamination |
| CN110314456A (en) * | 2019-07-09 | 2019-10-11 | 江苏中海华核环保有限公司 | For the radioactive spent resin effective filter that treated is vented |
| CN112992393A (en) * | 2021-03-10 | 2021-06-18 | 华能山东石岛湾核电有限公司 | Radioactive graphite nodule suction device for high-temperature gas cooled reactor |
| CN114334201A (en) * | 2022-01-11 | 2022-04-12 | 西安热工研究院有限公司 | High temperature gas cooled reactor fuel ball integrity detection device based on X-ray tomography |
Non-Patent Citations (2)
| Title |
|---|
| 周春山 等: "《新编实用化工小商品配方与生产 1》", 科学技术文献出版社, pages: 188 * |
| 杨兰和主编: "《CNP600压水堆核电厂运行 中级 上》", 31 December 2009, 科学技术文献出版社, pages: 151 * |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106291655B (en) | Airborne radioactivity monitor | |
| KR940003711B1 (en) | Manufacturing automation system for nuclear fuel rod production | |
| CN110153045A (en) | Radioactive pollution material activity continuously screens the equipment and detection method of automatic sorting | |
| CN112162309A (en) | Cabinet type air-borne radioactive integrated monitoring device | |
| CN115055392A (en) | High-temperature gas cooled reactor graphite nodule surface decontamination screening system and method | |
| JPH07198856A (en) | Method and apparatus for measuring concentration of particular radioactive substance in the air | |
| CN210604996U (en) | Detector assembly for continuously discriminating activity of radioactive contamination material | |
| Bowyer et al. | Automated particulate sampler for Comprehensive Test Ban Treaty verification (the DOE radionuclide aerosol sampler/analyzer) | |
| US6447366B1 (en) | Integrated decontamination and characterization system and method | |
| RU2696001C1 (en) | Apparatus for monitoring alpha contamination of fuel elements | |
| CN210171979U (en) | Automatic sorting equipment for radioactive pollution materials with two discrimination thresholds | |
| CN210171978U (en) | Automatic sorting equipment for continuously discriminating activity of radioactive contamination material | |
| US4626692A (en) | Apparatus for detecting iodine isotopes | |
| CN107863170A (en) | MOX pellet preparation technology radiation protection methods | |
| JPH0269658A (en) | Method for measuring volatile ruthenium | |
| CN210171977U (en) | Remote control and data acquisition device and automatic radioactive contamination material sorting equipment | |
| CN215236470U (en) | Laser decontamination robot | |
| JPH02285279A (en) | Smear apparatus of radioactive waste drum, radioactive intensity measuring apparatus and inspection installation equipped with both apparatuses | |
| CN114488270A (en) | Continuous and rapid online measuring device for radioactive xenon | |
| CN113341451A (en) | Radioactive air on-line monitoring device | |
| JPS6370186A (en) | Radioactive waste selector | |
| JPH07248283A (en) | Radioactive dust sampler | |
| Pineau | Routine use of cellulose nitrate films for the dosimetry of underground miners in France | |
| GB1231396A (en) | ||
| Hulett | Air sampling program at the Portsmouth Gaseous Diffusion Plant |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |