CN210837200U - Containment sealing detection device for debugging of nuclear power plant - Google Patents

Containment sealing detection device for debugging of nuclear power plant Download PDF

Info

Publication number
CN210837200U
CN210837200U CN201921643848.0U CN201921643848U CN210837200U CN 210837200 U CN210837200 U CN 210837200U CN 201921643848 U CN201921643848 U CN 201921643848U CN 210837200 U CN210837200 U CN 210837200U
Authority
CN
China
Prior art keywords
water tank
fixed
containment
debugging
power plant
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.)
Expired - Fee Related
Application number
CN201921643848.0U
Other languages
Chinese (zh)
Inventor
王伟华
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Individual
Original Assignee
Individual
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Individual filed Critical Individual
Priority to CN201921643848.0U priority Critical patent/CN210837200U/en
Application granted granted Critical
Publication of CN210837200U publication Critical patent/CN210837200U/en
Expired - Fee Related legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The utility model discloses a containment seal detection device for debugging of nuclear power plant, the water tank comprises a water tank, water tank bottom inner wall is fixed with the backup pad of two symmetric distributions, and the water tank top is fixed with two fixed establishment, and fixed establishment includes the L board, be fixed with the telescopic link on the L board, and the bottom mounting of telescopic link has the extension rod, and the extension rod bottom is passed water tank top inner wall and is fixed with the limiting plate, the water tank top is equipped with gas injection mechanism, and is equipped with inlet tube and drain pipe on the water tank, and water tank one side outer wall is equipped with the chamber door, has placed the containment body in the backup pad. The utility model discloses make the limiting plate carry out centre gripping fixed action to containment top both sides, prevent that the containment body from taking place to rock at the detection achievement time, improve the stability of detection achievement, still make things convenient for the staff to carry out the bubble from the observation window and observe, increase the intuition nature of detection achievement.

Description

Containment sealing detection device for debugging of nuclear power plant
Technical Field
The utility model relates to a leakproofness detects technical field, especially relates to a containment seals detection device for debugging of nuclear power plant.
Background
In a pressurized water reactor nuclear power plant, a fuel cladding, a primary circuit pressure boundary and a containment form three barriers for shielding radioactive substances in the nuclear power plant, wherein the containment is the third barrier for preventing the radioactive substances from being released in the nuclear power plant and the last barrier. When an accident such as a primary loop pipeline breach occurs in the nuclear power plant, the mass energy discharged into the containment vessel and the corresponding radioactive substance are contained in the containment vessel, the radioactive substance is prevented from being released to the atmosphere outside the containment vessel, and workers in the plant and public people outside the plant are protected from radioactive hazards.
The nuclear power plant debugging outline and the operation outline require that the containment isolation valve needs to be subjected to online sealing performance measurement. At present, for containment vessel sealing detection tests, a test medium can be water or air, and the existing detection device has some defects in the use process, for example, the containment vessel is inconvenient to fix and limit, and the containment vessel is easy to shake in the detection process.
SUMMERY OF THE UTILITY MODEL
The utility model aims at solving the shortcoming that exists among the prior art, and the containment sealing detection device for nuclear power plant debugging that proposes.
In order to achieve the above purpose, the utility model adopts the following technical scheme:
the utility model provides a containment sealing detection device for debugging of nuclear power plant, includes the water tank, water tank bottom inner wall is fixed with the backup pad of two symmetric distributions, and the water tank top is fixed with two fixed establishment, and fixed establishment includes the L board, be fixed with the telescopic link on the L board, and the bottom mounting of telescopic link has the extension rod, and the extension rod bottom is passed water tank top inner wall and is fixed with the limiting plate, the water tank top is equipped with gas injection mechanism, and is equipped with inlet tube and drain pipe on the water tank, and water tank one side outer wall is equipped with the chamber door, has placed the containment body in the backup pad.
Furthermore, a handle is fixed on the box door, and an anti-skid sleeve is sleeved on the handle.
Further, the gas injection mechanism includes the air pump, and the gas outlet of air pump is fixed with the air duct, and the bottom of air duct is pegged graft in the water tank.
Further, the outer wall of the bottom of the water tank is fixed with a base, and the outer wall of one side of the water tank is provided with a transparent observation window.
Furthermore, an air guide hopper is fixed at an air inlet of the air pump, and a dust filtering net is fixed on the air guide hopper.
Furthermore, a material guide plate is fixed at a position, close to the box door, inside the water tank, and a plurality of rollers distributed at equal intervals are rotatably installed at the top of the material guide plate.
The utility model has the advantages that:
1. the limiting plate at the bottom end of the extension rod can be driven to move downwards through the arrangement of the telescopic rod, so that the limiting plate can clamp and fix two sides of the top of the containment vessel, the containment vessel body is prevented from shaking during detection, and the stability of the detection is improved;
2. the gas injection mechanism is provided with the gas pump, so that the gas injection work can be performed on the sealed containment body, if the containment body has gas holes, bubbles can overflow from the water tank, the bubble observation can be performed by workers through the observation window conveniently, and the intuitiveness of the detection work is improved;
3. the containment body pushed into the water tank can be supported and guided by the guide plate, friction coefficients between the containment body and the guide plate can be reduced by the rolling shaft, and convenience of loading and unloading work of the containment body is improved.
Drawings
Fig. 1 is a schematic sectional structure view of an embodiment 1 of a containment vessel sealing detection device for debugging a nuclear power plant according to the present invention;
fig. 2 is a schematic perspective view of a containment vessel sealing detection device in accordance with an embodiment 1 of the present invention for debugging a nuclear power plant;
fig. 3 is the utility model provides a containment seals detection device's for debugging of nuclear power plant embodiment 2 sectional structure schematic diagram.
In the figure: the safety shell comprises a water tank 1, a plate 2L, a telescopic rod 3, an air pump 4, an air guide pipe 5, an extension rod 6, a water inlet pipe 7, a limiting plate 8, a safety shell body 9, a supporting plate 10, a base 11, a box door 12, a handle 13, a guide plate 14 and a roller 15.
Detailed Description
The technical solutions in the embodiments of the present invention will be described clearly and completely with reference to the accompanying drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only some embodiments of the present invention, not all embodiments.
Examples of which are illustrated in the accompanying drawings, wherein like reference numerals refer to the same or similar elements or elements having the same or similar function throughout. The embodiments described below with reference to the drawings are exemplary only for the purpose of explaining the present patent and are not to be construed as limiting the present patent.
Example 1
Referring to fig. 1 and 2, a containment sealing detection device for debugging of nuclear power plant, including water tank 1, 1 bottom inner wall of water tank is fixed with two symmetric distribution's backup pad 10, and 1 top of water tank is fixed with two fixed establishment, fixed establishment includes L board 2, be fixed with telescopic link 3 on the L board 2, and the bottom mounting of telescopic link 3 has extension rod 6, extension rod 6 bottom is passed 1 top inner wall of water tank and is fixed with limiting plate 8, 1 top of water tank is equipped with the gas injection mechanism, and be equipped with inlet tube 7 and drain pipe on the water tank 1, 1 one side outer wall of water tank is equipped with chamber door 12, containment body 9 has been placed in backup pad 10.
Its characterized in that is fixed with handle 13 on the chamber door 12, and has cup jointed the antiskid cover on the handle 13, and the gas injection mechanism includes air pump 4, and the gas outlet of air pump 4 is fixed with air duct 5, and the bottom of air duct 5 is pegged graft in water tank 1, and 1 bottom outer wall of water tank is fixed with base 11, and 1 one side outer wall of water tank is equipped with transparent observation window, and the air inlet of air pump 4 is fixed with the air guide fill, and is fixed with the dust screen on the air guide fill.
The working principle of the embodiment is as follows: lower box door 12 is opened, place into the backup pad 10 top in the water tank 1 with containment body 9 again, close box door 12, from inlet tube 7 water injection until submergence containment body 9, telescopic link 3 can drive limiting plate 8 of extension rod 6 bottom and carry out the downstream, and then make limiting plate 8 carry out centre gripping fixed action to containment 9 top both sides, prevent that containment body 9 from taking place to rock when detecting the work, improve the stability of detection achievement, air pump 4 can carry out the gas injection work to the containment body 9 after the shutoff in the gas injection mechanism, if when containment body 9 has the gas pocket, can produce the bubble in the water tank 1 and spill over, make things convenient for the staff to carry out the bubble observation from the observation window, increase the intuitionistic nature of detection achievement.
Example 2
Referring to fig. 3, a containment vessel sealing detection device for debugging in a nuclear power plant is different from embodiment 1 in that a material guide plate 14 is fixed inside a water tank 1 at a position close to a tank door 12, and a plurality of rollers 15 are rotatably mounted on the top of the material guide plate 14 and are distributed at equal intervals.
The working principle of the embodiment is as follows: the guide plate 14 can support and guide the containment body 9 pushed into the water tank 1, and the rolling shaft 15 can reduce the friction coefficient between the containment body 9 and the guide plate 14, so that the convenience of loading and unloading work of the containment body 9 is improved.
In the description of this patent, it is to be understood that the terms "coaxial," "bottom," "one end," "top," "middle," "other end," "upper," "one side," "top," "inner," "front," "center," "two ends," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the patent and for simplicity in description, and are not intended to indicate or imply that the referenced device or element must have a particular orientation, be constructed and operated in a particular orientation, and are not to be considered limiting of the patent.
In this patent, unless expressly stated or limited otherwise, the terms "mounted," "disposed," "connected," "secured," "screwed" and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; they may be directly connected or indirectly connected through an intermediate, or they may be connected internally or in an interactive relationship with each other, and unless otherwise specifically limited, the specific meaning of the above terms in this patent will be understood by those skilled in the art according to the specific circumstances.
The above, only be the concrete implementation of the preferred embodiment of the present invention, but the protection scope of the present invention is not limited thereto, and any person skilled in the art is in the technical scope of the present invention, according to the technical solution of the present invention and the utility model, the concept of which is equivalent to replace or change, should be covered within the protection scope of the present invention.

Claims (6)

1. The utility model provides a containment sealing detection device for debugging of nuclear power plant, includes water tank (1), its characterized in that, water tank (1) bottom inner wall is fixed with backup pad (10) of two symmetric distributions, and water tank (1) top is fixed with two fixed establishment, and fixed establishment includes L board (2), be fixed with telescopic link (3) on L board (2), and the bottom mounting of telescopic link (3) has extension rod (6), and extension rod (6) bottom is passed water tank (1) top inner wall and is fixed with limiting plate (8), water tank (1) top is equipped with the gas injection mechanism, and is equipped with inlet tube (7) and drain pipe on water tank (1), and water tank (1) one side outer wall is equipped with chamber door (12), has placed containment body (9) on backup pad (10).
2. The containment sealing detection device for debugging of nuclear power plant as claimed in claim 1, wherein a handle (13) is fixed on the box door (12), and an anti-slip sleeve is sleeved on the handle (13).
3. The containment sealing detection device for debugging of nuclear power plant as claimed in claim 1, wherein the gas injection mechanism comprises an air pump (4), a gas outlet of the air pump (4) is fixed with a gas guide tube (5), and the bottom end of the gas guide tube (5) is inserted into the water tank (1).
4. The containment sealing detection device for debugging of nuclear power plant as claimed in claim 1, wherein the base (11) is fixed on the outer wall of the bottom of the water tank (1), and the outer wall of one side of the water tank (1) is provided with a transparent observation window.
5. The containment sealing detection device for debugging of nuclear power plant as claimed in claim 3, wherein an air guide hopper is fixed to an air inlet of the air pump (4), and a dust filter screen is fixed to the air guide hopper.
6. The containment sealing detection device for nuclear power plant debugging of claim 2, wherein a material guide plate (14) is fixed inside the water tank (1) at a position close to the tank door (12), and a plurality of rollers (15) are rotatably mounted on the top of the material guide plate (14) and are distributed at equal intervals.
CN201921643848.0U 2019-09-29 2019-09-29 Containment sealing detection device for debugging of nuclear power plant Expired - Fee Related CN210837200U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201921643848.0U CN210837200U (en) 2019-09-29 2019-09-29 Containment sealing detection device for debugging of nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201921643848.0U CN210837200U (en) 2019-09-29 2019-09-29 Containment sealing detection device for debugging of nuclear power plant

Publications (1)

Publication Number Publication Date
CN210837200U true CN210837200U (en) 2020-06-23

Family

ID=71257923

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201921643848.0U Expired - Fee Related CN210837200U (en) 2019-09-29 2019-09-29 Containment sealing detection device for debugging of nuclear power plant

Country Status (1)

Country Link
CN (1) CN210837200U (en)

Similar Documents

Publication Publication Date Title
ES2847528T3 (en) Device and procedure for checking the tightness by inspection of leaks of a nuclear fuel element
CN210837200U (en) Containment sealing detection device for debugging of nuclear power plant
CN112151199B (en) Total gas content measuring device of pressurized water reactor nuclear power loop
CN102467984A (en) High-activity spent radioactive source conditioning method and special device thereof
CN209852539U (en) Movable construction platform for river channel treatment in-water floating
CN209357471U (en) A kind of radioactive sample cask flask
US20140161218A1 (en) Radioactive capture system for severe accident containment of light water reactors (lwrs), and method thereof
CN108154939A (en) A kind of containment filtration exhaust system based on small-sized heap waterborne
CN212328377U (en) Sewage detection that leakproofness is good holds box
CN214525919U (en) Liquid level measuring device for water reducing agent storage tank
CN214657546U (en) PH detection device for pump station installation
CN209148080U (en) A kind of coal mine empty water level measurement device always
CN209280364U (en) A kind of water environment sampler convenient for operation
CN208256295U (en) A kind of nuclear power station underwater foreign matter collection transfer device
JP3854007B2 (en) Damaged fuel detection method and system
JPS5822996B2 (en) A device that detects leaks in the cladding of fuel rods located inside the pressure vessel of a nuclear reactor.
CN214650543U (en) Anti-spilling blood gene detection kit
CN215327427U (en) Hydrochloric acid phenylhydrazine waste water neutralization apparatus
CN205392359U (en) Raw materials vacuum adsorption system
CN215492268U (en) Chemical leakage detection device
CN213658731U (en) Oil gas field sewage water quality monitoring device
CN215492627U (en) Comprehensive underground water sampling detector
CN109239274B (en) Gas sample introduction device for measuring total organic carbon of fixed pollution source
CN114068047B (en) Auxiliary water inlet device for hydrostatic test
CN215492652U (en) Portable water quality sampling device

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant
CF01 Termination of patent right due to non-payment of annual fee
CF01 Termination of patent right due to non-payment of annual fee

Granted publication date: 20200623

Termination date: 20210929