CN109224688B - High-temperature radiation gas-solid separation and filtration device for nuclear power station - Google Patents
High-temperature radiation gas-solid separation and filtration device for nuclear power station Download PDFInfo
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- CN109224688B CN109224688B CN201811294841.2A CN201811294841A CN109224688B CN 109224688 B CN109224688 B CN 109224688B CN 201811294841 A CN201811294841 A CN 201811294841A CN 109224688 B CN109224688 B CN 109224688B
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- 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
- B01D46/56—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours with multiple filtering elements, characterised by their mutual disposition
- B01D46/58—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours with multiple filtering elements, characterised by their mutual disposition connected in parallel
- B01D46/60—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours with multiple filtering elements, characterised by their mutual disposition connected in parallel arranged concentrically or coaxially
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- 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
- B01D46/0039—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours with flow guiding by feed or discharge devices
- B01D46/0041—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours with flow guiding by feed or discharge devices for feeding
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- 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
- B01D46/0084—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours provided with safety means
- B01D46/0086—Filter condition indicators
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- 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
- B01D46/24—Particle separators, e.g. dust precipitators, using rigid hollow filter bodies
- B01D46/2403—Particle separators, e.g. dust precipitators, using rigid hollow filter bodies characterised by the physical shape or structure of the filtering element
- B01D46/2411—Filter cartridges
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- 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
- G21F9/02—Treating gases
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- Physics & Mathematics (AREA)
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- High Energy & Nuclear Physics (AREA)
- Geometry (AREA)
- Filtering Of Dispersed Particles In Gases (AREA)
Abstract
The invention discloses a gas-solid separation and filtration device for high-temperature radiation of a nuclear power station, which comprises a main body, a filter tip and an end cover. The inside baffle that is equipped with the main part inner wall butt of main part, with main part inner wall butt and with baffle spaced mounting panel to and both ends are connected with baffle and mounting panel respectively's filter core, the baffle has a plurality of perforation. The filter tip interval cup joints in the one end of main part and with be formed with the clearance between the main part, the one end and the main part sealing connection of filter tip, and the filter tip be provided with the filter tip inside and the inlet pipe of clearance intercommunication, the one end that the filter tip was kept away from to the main part is located to the end cover and is provided with the discharging pipe that runs through the end cover. The high-temperature radiation gas-solid separation and filtration device for the nuclear power station can meet the requirement of normal work under a high-temperature condition, and has good filtration performance due to the fact that the baffle and the filter element are arranged inside the device.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and particularly relates to a high-temperature radiation gas-solid separation and filtration device for a nuclear power station.
Background
When radioactive solid waste is treated by a nuclear power station and other nuclear technology application units, a high-temperature steam reforming process is adopted, the radioactive organic solid waste is treated at a high temperature to generate mineralized particles and gas-phase products with high temperature, gas-solid separation treatment is needed, the mineralized particles containing radioactive nuclides are separated out to be properly packaged, and a high-temperature filtering device is needed. In case of accident, a large amount of high-temperature radioactive waste gas and waste solids are generated in the device or the plant, and radioactive gas-solid phase separation is also needed.
At present, a filtering device for radioactive gas-solid separation under the high-temperature condition is not provided in a related nuclear power station, and a high-efficiency filtering filter element adopted by a common gas-solid separation filter is made of an organic material and cannot resist high temperature. In addition, the filtering devices applied to the radioactive occasions in the nuclear industry are water filters and filter elements, and the filtering devices also need to work at normal temperature and cannot normally work at high temperature. Therefore, it is necessary to develop a filtering apparatus capable of performing radioactive gas-solid phase separation at a high temperature, so as to satisfy the development and application of various new technologies in the nuclear industry.
At present, the gas-solid phase separation mostly adopts an efficient filtering filter element made of organic materials or a simple filter screen, but has the following problems: 1) the high-efficiency filter element can meet the requirement of filter precision, but the filter element can be damaged due to overhigh temperature and cannot work normally; 2) the filter screen can be made of a non-metal material or a metal material, but the non-metal material cannot resist high temperature, and the metal material cannot meet the requirement of filter precision; 3) the filtering device matched with the filter element can not realize the purpose of gas-solid phase separation at high temperature in terms of structure and material; 4) other industries have high-temperature filters which can carry out gas-solid phase separation, but the design of matched equipment and the filter can not meet the special requirement of treating radioactive substances in the nuclear industry.
In view of this, it is necessary to provide a simple, efficient and wide-range-of-application high-temperature radioactive gas-solid separation and filtration device for nuclear power plants to promote the application research of a new radioactive solid waste treatment process in the nuclear industry and improve the efficiency and safety of radioactive waste treatment.
Disclosure of Invention
The invention aims to: the defects in the prior art are overcome, and the high-temperature radiation gas-solid separation and filtration device for the nuclear power station can meet the requirement of normal work under a high-temperature condition and has good filtration performance.
In order to achieve the purpose, the invention provides a gas-solid separation and filtration device for high-temperature radiation of a nuclear power station, which comprises a main body, a filter tip and an end cover, wherein:
the filter element comprises a main body and a filter element, wherein a baffle abutted against the inner wall of the main body, a mounting plate abutted against the inner wall of the main body and spaced from the baffle, and a filter element with two ends respectively connected with the baffle and the mounting plate are arranged in the main body;
the filter tip is sleeved at one end of the main body at intervals, a gap is formed between the filter tip and the main body, one end of the filter tip is hermetically connected with the main body, and the filter tip is provided with a feeding pipe communicated with the inside of the filter tip and the gap;
the end cover is located the one end of keeping away from the filter tip of main part is provided with and runs through the discharging pipe of end cover.
As an improvement of the high-temperature radiation gas-solid separation and filtration device for the nuclear power station, the main body comprises a first section, a second section and a first connecting section connected between the first section and the second section; the baffle is accommodated in the first section of the main body and is arranged along the transverse axis direction of the first section; the mounting plate is accommodated in the first section of the main body and is arranged along the transverse axis direction of the first section; the filter core receive in the first section of main part is located between baffle and the mounting panel, and the filter core both ends respectively with baffle and mounting panel are connected.
As an improvement of the high-temperature radiation gas-solid separation and filtration device for the nuclear power station, the main body is also provided with a monitoring device, and the monitoring device comprises a differential pressure transmitter, a first testing end and a second testing end; one end of the first testing end is connected with the differential pressure transmitter, and the other end of the first testing end is inserted into the inner part of one side, away from the filter element, of the baffle plate and communicated with the inner part of the first section; one end of the second testing end is connected with the differential pressure transmitter, and the other end of the second testing end is inserted and connected with the mounting plate to be far away from one side of the filter element, wherein the inside of the one side of the filter element is communicated with the inside of the first section.
As an improvement of the high-temperature radiation gas-solid separation and filtration device for the nuclear power station, an abutting part corresponding to the end cover is further formed in a protruding mode at one end, far away from the first connecting section, of the first section, and when the end cover is arranged at one end, far away from the first connecting section, of the main body, the end cover and the abutting part are fixed together; the first section of the outer portion is further sleeved with a first gasket, and the first gasket is clamped between the end cover and the abutting portion.
As an improvement of the high-temperature radiation gas-solid separation and filtration device for the nuclear power station, the filter tip comprises a sleeving section, a discharging section and a second connecting section connected between the sleeving section and the discharging section, and the sleeving section is sleeved outside one end, far away from the first connecting section, of the second section.
As an improvement of the high-temperature radiation gas-solid separation and filtration device for the nuclear power station, a first fastening part is convexly formed on the edge of one end, far away from the second connecting section, of the sleeving section along the direction of the transverse shaft of the sleeving section, the inner diameter of the first fastening part is smaller than that of the sleeving section, the diameter of the first fastening part is larger than that of the sleeving section, and the feeding pipe is arranged at one end, close to the first fastening part, of the sleeving section.
As an improvement of the high-temperature radiation gas-solid separation and filtration device for the nuclear power station, a second fastening part corresponding to the first fastening part is formed in a protruding and extending manner in the middle section of the second section, and when the sleeving part is sleeved outside one end of the second section, which is far away from the first connecting section, the first fastening part and the second fastening part are fixed together; and a third gasket is sleeved outside the second section and clamped between the first fastening part and the second fastening part.
As an improvement of the high-temperature radiation gas-solid separation and filtration device for the nuclear power station, the high-temperature radiation gas-solid separation and filtration device for the nuclear power station further comprises a temperature monitor, and the temperature monitor is arranged on the end cover.
As an improvement of the high-temperature radiation gas-solid separation and filtration device for the nuclear power station, the end cover is also provided with a gas receiving pipe head penetrating through the end cover, and the gas receiving pipe head and the discharge pipe are positioned on the same side of the end cover.
As an improvement of the high-temperature radiation gas-solid separation and filtration device for the nuclear power station, a second gasket is arranged at the joint of the baffle and the filter element.
Compared with the prior art, the high-temperature radiation gas-solid separation and filtration device for the nuclear power station can meet the requirement of normal work under a high-temperature condition, and has good filtration performance due to the fact that the baffle and the filter element are arranged inside. In addition, the temperature monitor is arranged, so that an operator can easily perceive the temperature shock inside the high-temperature radiation gas-solid separation and filtration device of the nuclear power station, and the possibility of accidents is further reduced.
Drawings
The high-temperature radiation gas-solid separation and filtration device for the nuclear power station is described in detail below with reference to the accompanying drawings and embodiments, wherein:
FIG. 1 is a sectional view of a gas-solid separation and filtration device for high-temperature radiation of a nuclear power plant provided by the invention.
Fig. 2 is a partially enlarged view of the area a shown in fig. 1.
Fig. 3 is a partially enlarged view of the region B shown in fig. 1.
Fig. 4 is a partially enlarged view of the region C shown in fig. 1.
Detailed Description
In order to make the objects, technical solutions and advantageous effects of the present invention more clearly apparent, the present invention will be described in further detail with reference to the accompanying drawings and the detailed description. It should be understood that the detailed description and specific examples, while indicating the preferred embodiment of the invention, are intended for purposes of illustration only and are not intended to limit the scope of the invention.
Referring to fig. 1 to 4, the present invention provides a high temperature radiation gas-solid separation filter device 100 for a nuclear power plant, which includes a hollow tubular main body 10, a hollow tubular filter 20 and an end cap 30. The main body 10 is internally provided with a baffle 11 abutted against the inner wall of the main body 10, a mounting plate 12 abutted against the inner wall of the main body 10 and spaced from the baffle 11, and a filter element 13 positioned between the baffle 11 and the mounting plate 12 and having two ends respectively connected with the baffle 11 and the mounting plate 12, wherein the baffle 11 is provided with a plurality of through holes 111. Filter 20 interval cup joints in the one end of main part 10 and is formed with clearance 200 with main part 10 between, the one end of filter 20 and main part 10 sealing connection and filter 20 are provided with the inlet pipe 21 with the inside and clearance 200 intercommunication of filter 20. The end cap 30 covers an end of the body 10 remote from the filter plug 20, and is provided with a spout 31 penetrating the end cap 30.
In the embodiment, the feeding pipe 21 is used for connecting a high-temperature container filled with a gas-solid mixture containing radioactive mineralized particles and gas, the discharging pipe 31 is used for connecting an exhaust fan, the exhaust fan enables the internal air pressure of the high-temperature radiation gas-solid separation and filtration device 100 of the nuclear power plant to be in an absolute vacuum state environment, and the absolute vacuum of the high-temperature radiation gas-solid separation and filtration device 100 of the nuclear power plant is preferably-50 kPa to-100 kPa.
Specifically, the body 10, the filter tip 20 and the end cover 30 are all made of hastelloy materials, and have good corrosion resistance and certain high temperature resistance, the filter element 13 is a tubular filter element, and the filtering precision is 20-1000 microns.
When the air exhauster is in operation (at this moment, the inside atmospheric pressure of nuclear power station high temperature radiation gas-solid separation filter device 100 is the negative pressure), the gas-solid mixture that has radioactive mineralization granule and gaseous gets into filter tip 20 by the inlet pipe fast, the large granule solid in the gas-solid mixture that has radioactive mineralization granule and gaseous is discharged from the one end that main part 10 was kept away from to filter tip 20 under the effect of gravity, the gas in the gas-solid mixture that has radioactive mineralization granule and gaseous gets into inside main part 10, and inside by filter core 13 outside entering filter core 13 through a plurality of perforation 111 of baffle 11, then discharge to discharging pipe 31 by the one end of keeping away from baffle 11 of filter core 13, finally discharge the outside of nuclear power station high temperature radiation gas-solid separation filter device 100 through discharging pipe 31. So set up, baffle 11 can carry out once filtering to the solid particle in the gas-solid mixture that has radiomineralization granule and gas, reaches the effect of carrying out gas-solid phase primary separation to the gas-solid mixture that has radiomineralization granule and gas.
Further, the main body 10 includes a first section 101, a second section 102, and a first connection section 103 connected between the first section 101 and the second section 102. The baffle 11 is accommodated in the first section 101 of the main body 10 and is arranged along the transverse axis direction of the first section 101; the mounting plate 12 is housed in the first section 101 of the main body 10 and is arranged along the transverse axis direction of the first section 101; the filter element 13 is accommodated in the first section 101 of the main body 10 and located between the baffle plate 11 and the mounting plate 12, and two ends of the filter element 13 are respectively connected with the baffle plate 11 and the mounting plate 12. In this embodiment, the first segment 101 and the second segment 102 are both hollow cylindrical, and the inner diameter of the first segment 101 is larger than that of the second segment 102; the first connecting section 103 is in the shape of a hollow cone, and the filter element 13 is in the shape of a cylinder.
Furthermore, an abutting portion 1011 corresponding to the end cap 30 is further formed by protruding the end of the first section 101 away from the first connecting section 103, and when the end cap 30 is covered on the end of the first section 101 of the main body 10 away from the first connecting section 103, the end cap 30 and the abutting portion 1011 are fixed together. Specifically, the first gasket 1012 is further sleeved outside the first section 101, and the first gasket 1012 is sandwiched between the end cover 30 and the abutting portion 1011, so that the sealing performance inside the high-temperature radiation gas-solid separation and filtration device 100 for the nuclear power plant can be improved.
Furthermore, a second gasket 112 is further disposed at the connection position of the baffle 11 and the filter element 13, so as to prevent solid particles in the gas-solid mixture containing the radioactive mineralization particles and the gas from being directly discharged to the discharge pipe 31 along the central axis of the filter element 13 through the through hole 111 of the baffle 11, and enable the filter element 13 to filter the solid particles in the gas-solid mixture containing the radioactive mineralization particles and the gas.
Further, the filter 20 comprises a socket section 201, a discharge section 202, and a second connecting section 203 connected between the socket section 201 and the discharge section 202, wherein the socket section 201 is sleeved outside an end of the second section 102 far away from the first connecting section 103. In this embodiment, the sleeve section 201 and the discharge section 202 are both hollow and cylindrical, and the inner diameter of the sleeve section 201 is larger than that of the discharge section 202; the second connecting section 203 is in a hollow conical shape, and an inner angle formed by one end of the second connecting section 203 connected with the sleeving section 201 and a horizontal plane is 60-75 degrees.
Further, a first fastening portion 2011 in a circular ring shape is convexly formed at the edge of one end, away from the second connecting section 203, of the sleeving section 201 along the direction of the transverse shaft of the sleeving section 201, and the inner diameter of the first fastening portion 2011 is smaller than that of the sleeving section 201 and is larger than that of the sleeving section 201; the feed pipe 21 is installed at one end of the sleeve joint section 201 close to the first fastening part 2011, and an included angle of 110-115 degrees is formed between the central axis of the feed pipe 21 and the part of the gap 200 close to the second connecting section 203. So set up, when making the cover section 201 cover in the second section 102 keep away from the outside of the one end of first connecting segment 103, be formed with less clearance 200 between the inner wall of cover section 201 and the outer wall of second section 102, also make the granule in the gas-solid mixture that has radioactive mineralization granule and gas more easily get into in the clearance 200. So set up, also be favorable to having the sedimentation of the large granule solid in the gaseous gas-solid mixture of radiomineralization granule and gas to separate.
Furthermore, a second fastening portion 1021 corresponding to the first fastening portion 2011 is formed in the middle section of the second section 102 in a protruding and extending manner, and when the sleeving part 201 is sleeved outside one end of the second section 102 far away from the first connecting section 103, the first fastening portion 2011 and the second fastening portion 1021 are fixed together. Specifically, a third gasket 1022 is further sleeved outside the second section 102, and the third gasket 1022 is clamped between the first fastening portion 2011 and the second fastening portion 1021, so that the sealing performance inside the high-temperature radiation gas-solid separation and filtration device 100 for the nuclear power plant can be improved. In this embodiment, the first pad 1012, the second pad 112, and the third pad 1022 are made of copper or silicon carbide, and have good corrosion resistance and high temperature resistance.
Further, the main body 10 is further provided with a monitoring device 14, in the illustrated embodiment, the monitoring device 14 is a differential pressure transmitter 141 capable of displaying a gas pressure value on a monitoring system, a first testing terminal 142 for detecting the gas pressure, and a second testing terminal 143 for detecting the gas pressure; one end of the first testing end 142 is connected with the differential pressure transmitter 141, and the other end is inserted into the baffle plate 11 and communicated with the inside of the first section 101 at the side far away from the filter element 13, so as to detect the air pressure at the inlet of the filter element 13; one end of the second testing end 143 is connected to the differential pressure transmitter 141, and the other end is inserted into the mounting plate 12 and is connected to the inside of one side of the filter element 13 and the inside of the first section 101 for detecting the air pressure at the outlet of the filter element 13. When the pressure difference transmitter 141 displays that the pressure difference between the pressure value detected by the first testing end 142 and the pressure value detected by the second testing end 143 is increased, it indicates that solid particles are adsorbed outside the filter element 13 (i.e., solid particles in the gas-solid mixture with the radioactive mineralized particles and gas are secondarily filtered), and the gas in the gas-solid mixture with the radioactive mineralized particles and gas enters the inside of the filter element 13 from the outside of the filter element 13, and is then discharged to the discharge pipe 31 from one end of the filter element 13 far away from the baffle plate 11, and finally is discharged to the outside of the high-temperature radioactive gas-solid separation filter device 100 of the nuclear power plant through the discharge pipe 31.
Further, the end cover 30 is further provided with a gas receiving pipe head 32 penetrating through the end cover 30, and the gas receiving pipe head 32 and the discharge pipe 31 are located on the same side of the end cover 30. When the high-temperature radiation gas-solid separation and filtration device 100 of the nuclear power plant works, the gas receiving pipe head 32 is in a blocking state; when the differential pressure transmitter 141 displays that the differential pressure value between the air pressure value detected by the first testing terminal 142 and the air pressure value detected by the second testing terminal 143 exceeds the predetermined range of the differential pressure transmitter, it indicates that too many solid particles are adsorbed outside the filter element 13, resulting in a great reduction in the filtering performance of the filter element. At this time, the high temperature radiation gas-solid separation and filtration device 100 of the nuclear power plant can stop working, the exhaust fan stops exhausting air, the air connecting pipe head 32 is in an unblocked state, preheated gas is blown into the high temperature radiation gas-solid separation and filtration device 100 of the nuclear power plant through the air connecting pipe head 32, solid particles adsorbed on the outer part of the filter element 13 are separated, and the filter element 13 can repeatedly recover good filtration performance.
Further, the nuclear power station high temperature radiation gas-solid separation and filtration device 100 further comprises a temperature monitor 40, wherein the temperature monitor 40 is arranged on the end cover 30 and used for detecting the temperature change inside the nuclear power station high temperature radiation gas-solid separation and filtration device 100, so that an operator can easily sense the temperature shock inside the nuclear power station high temperature radiation gas-solid separation and filtration device 100, and the possibility of accidents is further reduced.
In combination with the above detailed description of the invention, it can be seen that, compared with the prior art, the high-temperature radiation gas-solid separation and filtration device for the nuclear power station provided by the invention can meet the requirement of normal operation under high temperature conditions, and the baffle and the filter element arranged inside the device have good filtration performance. In addition, a temperature monitor is arranged, so that an operator can easily sense the temperature shock inside the high-temperature radiation gas-solid separation and filtration device of the nuclear power station, and the possibility of accidents is further reduced.
Appropriate changes and modifications to the embodiments described above will become apparent to those skilled in the art from the disclosure and teachings of the foregoing description. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and variations of the present invention should fall within the scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.
Claims (8)
1. The utility model provides a nuclear power station high temperature radiation gas-solid separation filter equipment which characterized in that, includes main part, filter tip and end cover, wherein:
the filter element comprises a main body and a filter element, wherein a baffle abutted against the inner wall of the main body, a mounting plate abutted against the inner wall of the main body and spaced from the baffle, and a filter element with two ends respectively connected with the baffle and the mounting plate are arranged in the main body; the main body comprises a first section, a second section and a first connecting section connected between the first section and the second section;
the filter tip is sleeved at one end of the main body at intervals, a gap is formed between the filter tip and the main body, one end of the filter tip is hermetically connected with the main body, and the filter tip is provided with a feeding pipe communicated with the inside of the filter tip and the gap; the filter tip comprises a sleeving section, a discharging section and a second connecting section connected between the sleeving section and the discharging section, and the sleeving section is sleeved outside one end of the second section, which is far away from the first connecting section; the edge of one end, far away from the second connecting section, of the sleeving section is convexly provided with a first fastening part along the direction of the transverse shaft of the sleeving section, the inner diameter of the first fastening part is smaller than that of the sleeving section, the diameter of the first fastening part is larger than that of the sleeving section, the feeding pipe is arranged at one end, close to the first fastening part, of the sleeving section, and an included angle of 110-115 degrees is formed between the central shaft of the feeding pipe and the part, close to the second connecting section, of the gap;
the end cover is located the one end of keeping away from the filter tip of main part is provided with and runs through the discharging pipe of end cover.
2. The gas-solid separation and filtration device for nuclear power plant high temperature radiation according to claim 1, wherein the baffle is housed in the first section of the main body and arranged along the transverse axis direction of the first section; the mounting plate is accommodated in the first section of the main body and is arranged along the transverse axis direction of the first section; the filter core receive in the first section of main part is located between baffle and the mounting panel, and the filter core both ends respectively with baffle and mounting panel are connected.
3. The gas-solid separation and filtration device for nuclear power plant high temperature radiation according to claim 2, wherein the main body is further provided with a monitoring device, and the monitoring device comprises a differential pressure transmitter, a first testing end and a second testing end; one end of the first testing end is connected with the differential pressure transmitter, and the other end of the first testing end is inserted into the inner part of one side, away from the filter element, of the baffle plate and communicated with the inner part of the first section; one end of the second testing end is connected with the differential pressure transmitter, and the other end of the second testing end is inserted and connected with the mounting plate to be far away from one side of the filter element, wherein the inside of the one side of the filter element is communicated with the inside of the first section.
4. The gas-solid separation and filtration device for high-temperature radiation of nuclear power station as claimed in claim 2, wherein the end of the first section far from the first connection section is further protruded to form an abutting part corresponding to the end cap, and when the end cap is arranged at the end of the first section far from the first connection section of the main body, the end cap and the abutting part are fixed together; the first section of the outer portion is further sleeved with a first gasket, and the first gasket is clamped between the end cover and the abutting portion.
5. The gas-solid separation and filtration device for nuclear power plant high temperature radiation according to claim 1, wherein a second fastening portion corresponding to the first fastening portion is formed by extending a middle section of the second section in a protruding manner, and when the sleeve joint portion is sleeved outside one end of the second section, which is far away from the first connection section, the first fastening portion and the second fastening portion are fixed together; and a third gasket is sleeved outside the second section and clamped between the first fastening part and the second fastening part.
6. The device for separating and filtering high-temperature radioactive gas from solid in nuclear power plant as claimed in claim 1, further comprising a temperature monitor, wherein the temperature monitor is mounted on the end cap.
7. The gas-solid separation and filtration device for nuclear power plant high temperature radiation according to claim 1, wherein the end cover is further provided with a gas receiving pipe head penetrating through the end cover, and the gas receiving pipe head and the discharge pipe are located on the same side of the end cover.
8. The gas-solid separation and filtration device for high-temperature radiation of nuclear power plant as claimed in claim 1, wherein a second gasket is further disposed at the connection of the baffle and the filter element.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811294841.2A CN109224688B (en) | 2018-11-01 | 2018-11-01 | High-temperature radiation gas-solid separation and filtration device for nuclear power station |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811294841.2A CN109224688B (en) | 2018-11-01 | 2018-11-01 | High-temperature radiation gas-solid separation and filtration device for nuclear power station |
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| Publication Number | Publication Date |
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| CN109224688A CN109224688A (en) | 2019-01-18 |
| CN109224688B true CN109224688B (en) | 2021-03-12 |
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| CN112604388B (en) * | 2020-11-12 | 2022-12-09 | 株洲航发动科南方燃气轮机有限公司 | Fuel gas filtering device |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103830977A (en) * | 2014-01-24 | 2014-06-04 | 清华大学 | Dust filter unit used for high-temperature high-pressure radioactive helium environment |
| CN106823597A (en) * | 2017-04-18 | 2017-06-13 | 山东钢铁股份有限公司 | A kind of filter and air-separating plant |
-
2018
- 2018-11-01 CN CN201811294841.2A patent/CN109224688B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103830977A (en) * | 2014-01-24 | 2014-06-04 | 清华大学 | Dust filter unit used for high-temperature high-pressure radioactive helium environment |
| CN106823597A (en) * | 2017-04-18 | 2017-06-13 | 山东钢铁股份有限公司 | A kind of filter and air-separating plant |
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