CN111312413A - Device for pressure relief and verification of nuclear power unit containment tightness test - Google Patents
Device for pressure relief and verification of nuclear power unit containment tightness test Download PDFInfo
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- CN111312413A CN111312413A CN202010251776.6A CN202010251776A CN111312413A CN 111312413 A CN111312413 A CN 111312413A CN 202010251776 A CN202010251776 A CN 202010251776A CN 111312413 A CN111312413 A CN 111312413A
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- verification
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/002—Detection of leaks
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
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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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- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
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Abstract
The invention belongs to the technical field of containment tightness detection of nuclear power stations, and particularly relates to a device for pressure relief and verification of containment tightness tests of nuclear power units. The device provided by the invention can effectively conduct diversion and buffering on the pressure relief airflow in the containment tightness test of the nuclear power unit, so as to achieve the purpose of protecting surrounding equipment instruments; the working condition of the small-flow pressure relief can be adjusted as required, and the method is used for carrying out a verification test of a containment tightness test of a nuclear power unit.
Description
Technical Field
The invention belongs to the technical field of containment tightness detection of nuclear power stations, and particularly relates to a device for pressure relief and verification of a containment tightness test of a nuclear power unit.
Background
The containment tightness test is realized by supplying compressed air into the containment by a compressor, and aims to determine whether the containment and parts thereof can meet the requirements of design performance after processing, test operation, maintenance and periodic inspection in the life period of a nuclear power plant. After the test is completed, the air is released to the interlayer space and then discharged to the atmosphere through the system filter. However, the Russian design has the advantage that the upper pressure relief opening is only an upward flange blind plate, and the functions of slow flow pressure relief and verification test are not considered.
According to the requirements of ANSI-56.8-2002 standard, the containment vessel sealing performance test result should be confirmed by the performance of a verification test. The key to the proof test is to determine a stable stack leak rate, thus requiring a pressure relief port that produces a stable small flow as the proof test interface. There are more equipment instruments above the pressure release mouth, and the compressed air that the pressure release process contains more steam and aerosol strikes and can lead to the fact the damage to equipment instrument above, and the containment leakproofness is experimental to occupy the key route of power station overhaul, and large-traffic gas passes through when needing to guarantee the release, consequently need carry out the water conservancy diversion buffering to the air of pressure release mouth, avoids a large amount of gas direct impact equipment instrument.
Therefore, a device for pressure relief and verification of nuclear power unit containment tightness tests needs to be designed, the device can give consideration to both the pressure relief buffering and the verification tests, conduct large-flow diversion buffering on gas in a containment, and conduct small-flow verification tests for containment leakage rate tests, so that the defects of the prior art are overcome.
Disclosure of Invention
The invention aims to provide a device for pressure relief and verification of a containment tightness test of a nuclear power unit aiming at the defects of the prior art so as to achieve the purposes of pressure relief, buffering and verification test functions in the containment tightness test.
The technical scheme of the invention is as follows:
a device for pressure relief and verification of nuclear power unit containment tightness test comprises a buffer elbow, a first flange type three-eccentric-center multi-level metal sealing butterfly valve, a loose joint screw, a second flange type three-eccentric-center multi-level metal sealing butterfly valve, a manual main verification test ball valve, a four-way valve, a manual sealing test branch ball valve, a manual verification test main acquisition branch ball valve, a first mass flow controller, a manual verification test auxiliary acquisition branch ball valve, a second mass flow controller, a connecting hose and a connecting straight pipe, wherein the buffer elbow, the first flange type three-eccentric-center multi-level metal sealing butterfly valve, the connecting straight pipe and the second flange type three-eccentric-center multi-level metal sealing butterfly valve are sequentially connected through flanges to form a flow guide channel, one end of the manual verification test main manual ball valve is connected with the loose joint screw formed by an opening in the straight pipe, and the other end of the manual sealing test branch ball valve is connected, The manual ball valve of the main collection branch of the verification test and the manual ball valve of the auxiliary collection branch of the verification test.
The buffer elbow, the flange type three-eccentric multi-level metal sealing butterfly valve I, the loose joint screw, the flange type three-eccentric multi-level metal sealing butterfly valve II and the connecting straight pipe form a low-precision large-flow pressure relief buffer system.
The buffer elbow, the flange type three-eccentric multi-level metal sealing butterfly valve I, the loose joint screw, the flange type three-eccentric multi-level metal sealing butterfly valve II and the connecting straight pipe are made of 20 steel.
The buffer elbow is designed into a 45-degree bending structure.
The high-precision small-flow verification test system comprises a verification test main path manual ball valve, a four-way valve, a sealing test branch path manual ball valve, a verification test main acquisition branch path manual ball valve, a mass flow controller I, a mass flow controller II and a verification test auxiliary acquisition branch path manual ball valve.
The other end of the manual ball valve of the sealing test branch is connected with a connecting hose.
And the other end of the manual ball valve of the main acquisition branch of the verification test is connected with a first mass flow controller.
And the other end of the manual ball valve of the acquisition branch in the verification test is connected with a second mass flow controller.
The invention has the following beneficial effects:
the device provided by the invention can effectively conduct diversion and buffering on the pressure relief airflow in the containment tightness test of the nuclear power unit, so as to achieve the purpose of protecting surrounding equipment instruments;
the device provided by the invention can adjust the low-flow pressure relief working condition as required and is used for carrying out a verification test of a containment tightness test of a nuclear power unit;
the device provided by the invention is of variable design and wide in application range, can be applied to the field of containment vessel sealing tests of nuclear power units by modifying the interfaces of the device and the system, and has great popularization value.
Drawings
FIG. 1 is a schematic structural diagram of a device for pressure relief and verification of a containment tightness test of a nuclear power unit, which is designed by the invention;
wherein: 1-containment inner wall, 2-buffer elbow, 3-flange type three-eccentric center multi-level metal sealing butterfly valve I, 4-loose joint screw, 5-flange type three-eccentric center multi-level metal sealing butterfly valve II, 6-verification test main path manual ball valve, 7-four-way valve, 8-tightness test branch path manual ball valve, 9-verification test main acquisition branch path manual ball valve, 10-mass flow controller I, 11-verification test auxiliary acquisition branch path manual ball valve, 12-mass flow controller II, 13-connecting hose, 14-original pressure relief elbow, 15-seal flange, 16-connecting straight pipe
Detailed Description
The present technology is further described below:
as shown in figure 1, the device for pressure relief and verification of nuclear power unit containment tightness test comprises a buffer elbow 2, a flange type three-eccentric multi-level metal sealing butterfly valve I3, a loose joint screw port 4, a flange type three-eccentric multi-level metal sealing butterfly valve II 5, a verification test main circuit manual ball valve 6, a four-way valve 7, a tightness test branch circuit manual ball valve 8, a verification test main collection branch circuit manual ball valve 9, a mass flow controller I10, a verification test auxiliary collection branch circuit manual ball valve 11, a mass flow controller II 12, a connecting hose 13 and a connecting straight pipe 16.
The device is divided into three parts, namely a containment body pressure relief system, a low-precision large-flow pressure relief buffering system and a high-precision small-flow verification test system. A sealing flange 15 of the containment body pressure relief system is in flange connection with a flange type three-eccentric multi-layer metal sealing butterfly valve 5 of the low-precision large-flow pressure relief buffering system, and a loose joint screw port 4 of the low-precision large-flow pressure relief buffering system is in hose quick-plug connection with a manual ball valve 6 of a main verification test path of the high-precision small-flow verification test system.
The containment inner wall 1, the original pressure relief opening elbow 14 and the sealing flange 15 form a containment body pressure relief system, the original pressure relief opening elbow 14 is a penetrating piece of the containment inner wall 1 and is used for leading out compressed air in the containment, the sealing flange 15 is connected with the original pressure relief opening elbow 14 in a welding mode, the sealing flange 15 is connected with the sealing flange 15 through a flange blind plate in a non-test state to form a closed system, the flange blind plate is opened in a test state, and the low-precision pressure relief large-flow buffer system is connected into the containment body pressure relief system.
The buffer elbow 2, the flange type three-eccentric center multi-level metal sealing butterfly valve 3, the loose joint screw port 4, the flange type three-eccentric center multi-level metal sealing butterfly valve 5 and the connecting straight pipe 16 form a low-precision large-flow pressure relief buffer system. The buffer elbow 2, the flange type three-eccentric center multi-layer metal sealing butterfly valve 3, the connecting straight pipe 16 and the flange type three-eccentric center multi-layer metal sealing butterfly valve 5 are sequentially connected through flanges to form a flow guide channel, and finally the flange type three-eccentric center multi-layer metal sealing butterfly valve 5 is connected to the sealing flange 15 and fixed through bolts. A loose joint screw port 4 is formed by drilling a hole on the connecting straight pipe 16 and is used for connecting a high-precision small-flow verification test system. One of the key characteristics is that a connecting straight pipe 16 is arranged between the flange type three-eccentric multi-level metal sealing butterfly valve 3 and the flange type three-eccentric multi-level metal sealing butterfly valve 5, so that a larger sealing space can be provided, and the stability and the accuracy of the measurement of the small-flow gas are ensured. The second key characteristic is that the pressure relief buffer system and the pressure relief system of the containment body are made of 20 steel which is made of the same material, and the elbow is designed to be 45 degrees and guides the original upward airflow to the inner wall.
The high-precision small-flow verification test system comprises a verification test main path manual ball valve 6, a four-way valve 7, a sealing test branch path manual ball valve 8, a verification test main acquisition branch path manual ball valve 9, a mass flow controller I10, a mass flow controller II 12 and a verification test auxiliary acquisition branch path manual ball valve 11. The high-precision small-flow verification test system is characterized in that a verification test main-path manual ball valve 6 is connected to a loose joint screw port 4 of a low-precision large-flow pressure relief buffer system through a hose, a four-way valve 7 is used for connecting the verification test main-path manual ball valve 6, a sealing test branch-path manual ball valve 8, a verification test main-acquisition branch-path manual ball valve 9 and a verification test auxiliary-acquisition branch-path manual ball valve 11, one end of a connecting hose 13 is connected with the sealing test branch-path manual ball valve 8, the other end of the connecting hose is connected to a leakage detection device for sealing detection, the verification test main-acquisition branch-path manual ball valve 9 serves as a verification test main acquisition and measurement channel through a hose quick-connection quality flow controller 10, and the verification test auxiliary-acquisition and measurement channel serves as a verification test auxiliary acquisition and measurement. One of the key characteristics is that the mass flow controllers are connected behind the manual ball valve 9 of the main acquisition branch and the manual ball valve 11 of the secondary acquisition branch of the verification test respectively to form two verification test channels of main acquisition and secondary acquisition, so that the fault tolerance rate and the reliability of the system are improved.
The invention adopts 90-degree pipeline drainage to change the flow direction of pressure-relief gas, so that the pressure-relief gas impacts the wall surface to be dispersed, and the risk of damaging surrounding equipment by pressure-relief gas flow is reduced.
The invention adopts the double-channel sealing valve, isolates a small flow channel with good sealing performance for verification test, designs a corresponding flow measurement function and realizes the function of executing the verification test.
The invention combines the large-flow working condition of pressure relief and the small-flow working condition of a verification test to ensure the continuity of the test execution process and the simplicity and convenience of operation.
The present invention has been described in detail with reference to the embodiments, but the present invention is not limited to the embodiments, and various changes can be made without departing from the gist of the present invention within the knowledge of those skilled in the art. The prior art can be adopted in the content which is not described in detail in the invention.
Claims (8)
1. The utility model provides a device that is used for experimental release of nuclear power unit containment leakproofness and verifies which characterized in that: the device comprises a buffer elbow (2), a flange type three-eccentric multi-layer metal sealing butterfly valve I (3), a loose joint screw port (4), a flange type three-eccentric multi-layer metal sealing butterfly valve II (5), a verification test main path manual ball valve (6), a four-way valve (7), a sealing test branch path manual ball valve (8), a verification test main acquisition branch path manual ball valve (9), a mass flow controller I (10), a verification test auxiliary acquisition branch path manual ball valve (11), a mass flow controller II (12), a connecting hose (13) and a connecting straight pipe (16), wherein the buffer elbow (2), the flange type three-eccentric multi-layer metal sealing butterfly valve I (3), the connecting straight pipe (16) and the flange type three-eccentric multi-layer metal sealing butterfly valve II (5) are sequentially connected through flanges to form a flow guide channel, one end of the verification test main path manual ball valve (6) is connected with the loose joint screw port (4) formed by an opening in the straight pipe (16), the other end is connected with a manual ball valve (8) of a sealing test branch, a manual ball valve (9) of a main collection branch of a verification test and a manual ball valve (11) of a secondary collection branch of the verification test through a four-way valve (7).
2. The device for pressure relief and verification of nuclear power unit containment tightness test according to claim 1, is characterized in that: the buffer elbow (2), the flange type three-eccentric multi-level metal sealing butterfly valve I (3), the loose joint screw (4), the flange type three-eccentric multi-level metal sealing butterfly valve II (5) and the connecting straight pipe (16) form a low-precision large-flow pressure relief buffer system.
3. The device for pressure relief and verification of nuclear power unit containment tightness test according to claim 2, is characterized in that: the buffer elbow (2), the flange type three-eccentric multi-layer metal sealing butterfly valve I (3), the loose joint screw (4), the flange type three-eccentric multi-layer metal sealing butterfly valve II (5) and the connecting straight pipe (16) are made of 20 steel.
4. The device for pressure relief and verification of nuclear power unit containment tightness test according to claim 3, characterized in that: the buffer elbow (2) is designed into a 45-degree bending structure.
5. The device for pressure relief and verification of nuclear power unit containment tightness test according to claim 4, is characterized in that: the high-precision small-flow verification test system comprises a verification test main path manual ball valve (6), a four-way valve (7), a sealing test branch manual ball valve (8), a verification test main acquisition branch manual ball valve (9), a mass flow controller I (10), a mass flow controller II (12) and a verification test auxiliary acquisition branch manual ball valve (11).
6. The device for pressure relief and verification of nuclear power unit containment tightness test according to claim 5, is characterized in that: the other end of the manual ball valve (8) of the tightness test branch is connected with a connecting hose (13).
7. The device for pressure relief and verification of nuclear power unit containment tightness test according to claim 6, characterized in that: the other end of the manual ball valve (9) of the main collection branch of the verification test is connected with a first mass flow controller (10).
8. The device for pressure relief and verification of nuclear power unit containment tightness test according to claim 7, is characterized in that: and the other end of the manual ball valve (11) of the collection branch in the verification test is connected with a second mass flow controller (12).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010251776.6A CN111312413A (en) | 2020-04-01 | 2020-04-01 | Device for pressure relief and verification of nuclear power unit containment tightness test |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010251776.6A CN111312413A (en) | 2020-04-01 | 2020-04-01 | Device for pressure relief and verification of nuclear power unit containment tightness test |
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| Publication Number | Publication Date |
|---|---|
| CN111312413A true CN111312413A (en) | 2020-06-19 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN202010251776.6A Pending CN111312413A (en) | 2020-04-01 | 2020-04-01 | Device for pressure relief and verification of nuclear power unit containment tightness test |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112037948A (en) * | 2020-09-08 | 2020-12-04 | 三门核电有限公司 | AP1000 containment overall leakage rate test pressure relief system and method |
-
2020
- 2020-04-01 CN CN202010251776.6A patent/CN111312413A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112037948A (en) * | 2020-09-08 | 2020-12-04 | 三门核电有限公司 | AP1000 containment overall leakage rate test pressure relief system and method |
| CN112037948B (en) * | 2020-09-08 | 2022-03-18 | 三门核电有限公司 | AP1000 containment overall leakage rate test pressure relief system and method |
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