CN201540746U - Air bag drainage arrangement in the main pipe of the reactor pressure vessel - Google Patents
Air bag drainage arrangement in the main pipe of the reactor pressure vessel Download PDFInfo
- Publication number
- CN201540746U CN201540746U CN2009202924761U CN200920292476U CN201540746U CN 201540746 U CN201540746 U CN 201540746U CN 2009202924761 U CN2009202924761 U CN 2009202924761U CN 200920292476 U CN200920292476 U CN 200920292476U CN 201540746 U CN201540746 U CN 201540746U
- Authority
- CN
- China
- Prior art keywords
- air bag
- fixed side
- pressure vessel
- reactor pressure
- drainage arrangement
- 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 - Lifetime
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model relates to the nondestructive detection field of nuclear reactor main pipe connection, particularly relates to an air bag drainage arrangement in the main pipe of the reactor pressure vessel, and core pipe is equipped between two fixed side boards, and soft rubber air bag is shaped on the fixed side board, thereby guarantying expansion of the water drainage air bag along the pipe interior diameter direction; an air bag clamp is installed on the fixed side board, furthermore the rubber air bag is fixed, thereby guarantying good gasproof effect of experiment, and pressure can be maintained at 1.5 bar for 30 minutes without change, and guarantying water drainage effect of the air bag suing ray examination.
Description
Technical field
The utility model belongs to the Non-Destructive Testing field that the nuclear reactor trunk line is taken over, and is specifically related to a kind of air bag drainage arrangement.
Background technology
High Temperature High Pressure heat eliminating medium (water) when one circuit system of nuclear power station has contained reactor operation occurs leaking as a circuit system equipment, will cause that unplanned short shutdown causes big economic loss, may cause serious nuclear leakage accident simultaneously.Therefore according to the requirement of coherence check standard, must regularly implement Non-Destructive Testing to these equipment and pipeline, the problem that exists in the discovering device weld seam, adopting the radiological survey X instrument that these weld seams are implemented radiological survey X is a kind of important means commonly used.One circuit system trunk line of nuclear power station is taken over weld seam enforcement center transillumination mode and is checked, in the process of implementing radiological survey X, detected weld zone duct inwall heat eliminating medium whether emptying directly influences the image quality of radiological survey X, designs therefore that the air bag discharge structure is to implement one of condition of checking in the set of tubes.
One circuit system trunk line of nuclear power station is taken over welding seam ray detection and is adopted center transillumination mode to implement to check that radiographic source is positioned at pipeline center's axis, and the radial location dimension precision requirement is at ± 5mm.This radiological survey X carries out during nuclear power station operation shutdown, the trunk line inwall is full of water, the water of pipe interior will make radiological survey X not finish during radiological survey X, because in the sensitivity of film imaging process, bubble occurs as tested zone, tested medium changes, and the radial imaging non-conformity of quality closes requirement, therefore in order to realize radiological survey X under the water-filled situation of pipeline, the water in tested zone need be drained only.
Some external developed country has developed nuclear power station nuclear reactor trunk line and has taken over weld seam Non-Destructive Testing checkout facility at present, developed pressure vessel checking machine as French IC company, there is trunk line to take over weld seam Non-Destructive Testing checkout facility on the inspection machine, these checkout facilities enter the inspection commissure and check under the drive of motion platform, exist equipment huge, the assembly and adjustment task is heavy, needs certain conditions to implement.US Westinghouse company has developed the supreem system but it can not realize taking over the radiological survey X of weld seam.
Summary of the invention
The purpose of this utility model is to provide a kind of can cross the quick draining of realization, be convenient to implement to check air bag drainage arrangement in the reactor pressure vessel trunk line of raising checking efficiency.
The technical solution of the utility model is as follows:
Air bag drainage arrangement in a kind of reactor pressure vessel trunk line, it comprises the fixed side of two circles that are oppositely arranged, the fixed side outer is provided with rubber pneumatic bag, be provided with the core pipe between two fixed sides, wherein: this fixed side center is a boss, have circular hole on the boss, circular hole is provided with defeated source capsule sleeve pipe, and this defeated source capsule sleeve pipe communicates with core pipe between two fixed sides.
Air bag drainage arrangement in the aforesaid reactor pressure vessel trunk line, described rubber pneumatic bag is a cylindrical structural, even thin-walled, the rubber pneumatic bag both sides are round-corner transition, and the air bag middle part is a flat segments, and this rubber pneumatic bag is installed in the fixed side edge by screw.
Air bag drainage arrangement in the aforesaid reactor pressure vessel trunk line is respectively equipped with air-pocket splint on each fixed side.
Air bag drainage arrangement in the aforesaid reactor pressure vessel trunk line, described air-pocket splint is an annular.
The beneficial effects of the utility model are: between two fixed sides the core pipe is set, soft rubber pneumatic bag typing on fixed side, has been guaranteed that the draining air bag expands on the internal diameter of the pipeline direction; Air-pocket splint is installed on fixed side, has further been fixed rubber pneumatic bag, guaranteed that the test airtight effect is good, can keep under the pressure of 1.5bar 30 minutes, the air pressure no change has also guaranteed the air bag drainage effect when radiological survey X simultaneously.
Description of drawings
Air bag drainage arrangement structural profile synoptic diagram in the reactor pressure vessel trunk line that Fig. 1 provides for the utility model;
Among the figure: 1. core pipe; 2. fixed side; 3. rubber pneumatic bag; 4. air-pocket splint; 5. defeated source capsule sleeve pipe.
Embodiment
Below in conjunction with drawings and the specific embodiments the utility model is described in further detail.
As shown in Figure 1, the air bag drainage arrangement comprises the fixed side 2 of two circles of installing relatively in the reactor pressure vessel trunk line, by screw retention rubber pneumatic bag 3 is installed on fixed side 2 outers, this rubber pneumatic bag 3 is a cylindrical structural, even thin-walled, rubber pneumatic bag 3 both sides are round-corner transition, and the air bag middle part is a flat segments.Between two fixed sides 2 core pipe 1 is installed, described core pipe 1 is vertical with two fixed sides 2, form H shape structure, these fixed side 2 centers are a boss, have circular hole on the boss, defeated source capsule sleeve pipe 5 passes this circular hole and is installed on the fixed side 2, and communicates with core pipe 1 between two fixed sides 2.In the present embodiment, fixedly mount the air-pocket splint 4 of an annular on each fixed side 2 respectively, thus further fixing and the rubber pneumatic bag 3 of having finalized the design.
The air bag drainage arrangement is a kind of current mechanism of implementing the pipe interior radiological survey X in the reactor pressure vessel trunk line, this device is fixed on the pipeline radiological survey X instrument by fixed side 2 during inspection, move on the driving lower edge conduit axis by motion platform and be examined the zone, when moving to when being examined the zone, rubber pneumatic bag 3 inflations, thereby rubber pneumatic bag 3 is expanded, arrange the medium that is examined the zone, rubber pneumatic bag 3 is close to inner-walls of duct.
Claims (4)
1. air bag drainage arrangement in the reactor pressure vessel trunk line, it comprises the fixed side (2) of two circles that are oppositely arranged, fixed side (2) outer is provided with rubber pneumatic bag (3), be provided with core pipe (1) between two fixed sides (2), it is characterized in that: this fixed side (2) center is a boss, have circular hole on the boss, circular hole is provided with defeated source capsule sleeve pipe (5), and this defeated source capsule sleeve pipe (5) communicates with core pipe (1) between two fixed sides (2).
2. air bag drainage arrangement in the reactor pressure vessel trunk line as claimed in claim 1, it is characterized in that: described rubber pneumatic bag (3) is a cylindrical structural, even thin-walled, rubber pneumatic bag (3) both sides are round-corner transition, the air bag middle part is a flat segments, and this rubber pneumatic bag (3) is installed in fixed side (2) edge by screw.
3. air bag drainage arrangement in the reactor pressure vessel trunk line as claimed in claim 1 or 2 is characterized in that: be respectively equipped with air-pocket splint (4) on each fixed side (2).
4. air bag drainage arrangement in the reactor pressure vessel trunk line as claimed in claim 3, it is characterized in that: described air-pocket splint (4) is an annular.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009202924761U CN201540746U (en) | 2009-12-11 | 2009-12-11 | Air bag drainage arrangement in the main pipe of the reactor pressure vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009202924761U CN201540746U (en) | 2009-12-11 | 2009-12-11 | Air bag drainage arrangement in the main pipe of the reactor pressure vessel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN201540746U true CN201540746U (en) | 2010-08-04 |
Family
ID=42592204
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2009202924761U Expired - Lifetime CN201540746U (en) | 2009-12-11 | 2009-12-11 | Air bag drainage arrangement in the main pipe of the reactor pressure vessel |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN201540746U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102881341A (en) * | 2012-10-08 | 2013-01-16 | 国家核电技术有限公司 | Volume expansion component and method for increasing gravity safety injection pressure head |
| CN109724239A (en) * | 2018-12-29 | 2019-05-07 | 沈炜 | The water-saving heat pipe of water heater |
| CN112923998A (en) * | 2021-01-26 | 2021-06-08 | 中国石油化工股份有限公司 | Method for setting nuclear level indicator for pressure container |
-
2009
- 2009-12-11 CN CN2009202924761U patent/CN201540746U/en not_active Expired - Lifetime
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102881341A (en) * | 2012-10-08 | 2013-01-16 | 国家核电技术有限公司 | Volume expansion component and method for increasing gravity safety injection pressure head |
| CN102881341B (en) * | 2012-10-08 | 2015-04-22 | 国家核电技术有限公司 | Volume expansion component and method for increasing gravity safety injection pressure head |
| CN109724239A (en) * | 2018-12-29 | 2019-05-07 | 沈炜 | The water-saving heat pipe of water heater |
| CN109724239B (en) * | 2018-12-29 | 2020-12-18 | 安徽国星生物化学有限公司 | Water-saving heat pipe of water heater |
| CN112923998A (en) * | 2021-01-26 | 2021-06-08 | 中国石油化工股份有限公司 | Method for setting nuclear level indicator for pressure container |
| CN112923998B (en) * | 2021-01-26 | 2023-11-03 | 中国石油化工股份有限公司 | Nuclear charge level indicator setting method for pressure container |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term |
Granted publication date: 20100804 |
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| CX01 | Expiry of patent term |