CN102279080A - Performance test device for sealing gasket of nuclear power equipment - Google Patents
Performance test device for sealing gasket of nuclear power equipment Download PDFInfo
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- CN102279080A CN102279080A CN2011100786326A CN201110078632A CN102279080A CN 102279080 A CN102279080 A CN 102279080A CN 2011100786326 A CN2011100786326 A CN 2011100786326A CN 201110078632 A CN201110078632 A CN 201110078632A CN 102279080 A CN102279080 A CN 102279080A
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- nuclear power
- cylindrical shell
- gasket seal
- autoclave
- power generating
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Abstract
The invention discloses a performance test device for a sealing gasket of nuclear power equipment, comprising an autoclave, a heating device for heating the autoclave, a cooling device arranged in the autoclave, an exhaust device and a control system. The test device can be used for simulating practical operation conditions of the nuclear power equipment through controlling alternative change of pressure and temperature in the autoclave by the control system and testing the sealing reliability of the sealing gasket, not only has important guiding meaning for manufacturing and improving the sealing gasket, but also can acquire final mounting parameters of the sealing gasket, and further provides beneficial helps for search of the reasons of the current nuclear power equipment leakage, such as leakage of manhole sealing of a nuclear power voltage stabilizer. The invention fills the blank of detecting and testing of sealing gaskets of the nuclear power equipment in China.
Description
Technical field
The present invention relates to a kind of nuclear power generating equipment service check device with gasket seal, it mainly is to test at the sealing reliability of gasket seal under the harsh conditions of big temperature difference temperature alternating and pressure alternation etc.
Background technology
Nuclear power generating equipment is mainly used in the nuclear power plant equipment with gasket seal (as the manhole gasket seal), it is the highest gasket seal of quality grade, its must safeguards system under the harsh conditions of nuclear power station operational system temperature and pressure alternation zero leakage, for the safe operation of nuclear power station escorts.Just because of this, nuclear power generating equipment is vital with performances such as the sealing of gasket seal and serviceable lifes for the safe operation of nuclear power station.At present nuclear power generating equipment all is to utilize the end face of the sealing surface of pad and web member (being generally joint flange) to compress with certain seal pressure to reach sealing effectiveness with gasket seal, the sealing reliability of pad is difficult to prediction and guarantees, domestic also do not have effective verifying attachment or method to be checked for above-mentioned nuclear power generating equipment with performances such as the sealing of gasket seal and serviceable lifes, this will restrict the autonomous manufacturing of China's nuclear power generating equipment with gasket seal, cause nuclear power generating equipment to delay to realize with the production domesticization of gasket seal.
Summary of the invention
Technical matters to be solved by this invention is to overcome the deficiencies in the prior art, the service check device of a kind of nuclear power generating equipment with gasket seal is provided, it can be tested with the sealing reliability of gasket seal under the harsh conditions of big temperature difference temperature alternating and pressure alternation to nuclear power generating equipment by the actual operating of simulation nuclear power plant equipment.
For solving above technical matters, the present invention takes following technical scheme:
A kind of nuclear power generating equipment is with the service check device of gasket seal, the heating arrangement that comprise autoclave, is used for autoclave is heated, is arranged on cooling device, exhaust apparatus and control system in the autoclave, wherein:
Described autoclave is included in top and bottom all to be had the cylindrical shell of opening, can be arranged on the upper flange plate and the lower flange of cylinder top opening and bottom opening position respectively with dismantling, and upper flange plate and lower flange one in the two is provided with a plurality of pipeline interfaces that are used to be connected exterior tubing and control element;
Temperature control modules, data acquisition module and controller that described control system comprises the pressure control module that is used to control cylinder internal pressure of linking to each other with described interface, cylindrical shell heated up and/or lower the temperature by control heating arrangement and cooling device; Data acquisition module is used to gather the pressure and temperature signal of pressure control module and temperature control modules gained and be sent to controller; Controller is according to from the signal of data acquisition module pressure control module and temperature control modules being controlled.
During check, gasket seal to be tested promptly fills up between the end face that places ring flange and cylindrical shell and is compacted, control system can be by the pressure, temperature variation in pressure control module and the temperature control modules control cylindrical shell, with the actual motion condition of simulation nuclear power generating equipment, whether operating personnel can leak the sealing reliability of judging gasket seal by detecting the gasket seal place.
According to the present invention, upper flange plate is connected with cylindrical shell by threaded fastener with lower flange, and described threaded fastener is preferably high-strength bolt.
Further, described verifying attachment also comprises the Detecting medium water that is infused in the cylindrical shell, and described heating arrangement comprises heating tube, and it is arranged in the water of cylindrical shell and water is heated.
Further, described verifying attachment also comprises the liquid level gauge that can measure the liquid level in the cylindrical shell.
Further, described verifying attachment also comprises the spray equipment that is arranged in the cylindrical shell, and this spray equipment is medium with water.
Further, cylindrical shell also is provided with the cooling jacket that is used for logical heat eliminating medium outward, and it is used as the auxiliary cooling way of described cooling device.
Because the enforcement of above technical scheme, the present invention compared with prior art has following advantage:
The nuclear power generating equipment of the present invention service check device of gasket seal, can control pressure and temperature alternation form in the autoclave by control system, the actual motion condition of simulation nuclear power generating equipment, sealing reliability to gasket seal is carried out test verification, not only can obtain the making of gasket seal is improved and install the parameter with great importance, the reason exploration that can also leak for nuclear power generating equipment at present etc. provides useful help.The present invention has filled up China and has detected blank on the inspection technology at nuclear power generating equipment with gasket seal.
Description of drawings
The present invention will be further described in detail below in conjunction with accompanying drawing and concrete embodiment:
Fig. 1 looks synoptic diagram for nuclear power generating equipment of the present invention with the master of the service check device of gasket seal;
Fig. 2 is the main TV structure synoptic diagram of the used autoclave of the present invention;
Fig. 3 is the control principle synoptic diagram of the control system of verifying attachment of the present invention;
Wherein: 1, cylindrical shell; 2, upper flange plate; 3, lower flange; 4, interface; 5, heating arrangement; 6, cooling device; 7, exhaust apparatus; 8, control system; 9, threaded fastener; 10, spray equipment; 11, cooling jacket; 12, gasket seal; 13, high-pressure hydraulic pump; 14, Heat-transfer Oil Pump; 15, liquid level gauge.
Embodiment
The present invention will be further described in detail below in conjunction with specific embodiment, but be not limited to these embodiment.
See figures.1.and.2,, comprising according to the nuclear power generating equipment of present embodiment service check device with gasket seal:
Autoclave, described autoclave is included in top and bottom all to be had the cylindrical shell 1 of opening, can be arranged on the upper flange plate 2 and the lower flange 3 of cylindrical shell 1 top end opening and bottom opening position respectively with dismantling, and lower flange 3 is provided with a plurality of interfaces 4 that are used to connect exterior tubing and control element; During check, get 12 two of gasket seals to be measured, wherein a pad places between the upper surface of upper flange plate 2 and cylindrical shell 1, and another piece pad places between the lower surface of lower flange 3 and cylindrical shell 1; Be connected by threaded fastener 9 between upper flange plate 2 or lower flange 3, gasket seal 12 and the cylindrical shell 1 and sealing pad 12 compacted according to predetermined seal pressure, threaded fastener 9 used in the present embodiment is a high-strength bolt;
Cooling device 6, described cooling device 6 comprise along the inwall of cylindrical shell 1 spiral upwards, the interior cooling coil that leads to heat eliminating medium, quick and even for what guarantee to lower the temperature simultaneously, outside cylindrical shell 1, also be provided with the cooling jacket 11 that is used for logical heat eliminating medium, cool off with auxiliary; Used heat eliminating medium is a conduction oil in the present embodiment;
In addition, according to present embodiment, this verifying attachment comprises also that an end links to each other with autoclave, the other end links to each other with control system 8 and can measure the liquid level gauge 15 of liquid level in the cylindrical shell 1, therefore control system 8 can in time obtain the liquid level information in the autoclave, and this also has certain reference value smoothly for testing program.
The verifying attachment of present embodiment has carried out the stress analysis evaluation to device materials and one-piece construction before making, and structural modeling carried out finite element analysis, simulate with geometry and load working condition true nuclear power generating equipment, guarantee the rationality of material and structure, allow to accurately verify the sealing property of gasket seal.During test, under different working conditions, whether leak validity and the reliability of judging gasket seal by observing gasket seal.
The method of inspection that present embodiment provides the verifying attachment of a kind of embodiment of utilization 1 that nuclear power generating equipment is tested with gasket seal, i.e. intensity hydraulic testing method.
The test condition of described intensity hydraulic testing method is:
Test temperature: normal temperature
Test(ing) medium: deionized water
Test range hydraulic pressure: 0.1MPa ~ 50MPa
May further comprise the steps:
(1) get gasket seal and respective flanges, according to gasket seal pretension is installed and is loaded fasteningly than pressure request, then by high-pressure hydraulic pump 13 water filling to the cylindrical shell 1 of autoclave in, while exhaust apparatus 7 is opened;
(2) after the cylindrical shell 1 interior fills with water, close exhaust apparatus 7, and continue by high-pressure hydraulic pump 13 toward cylindrical shell 1 interior water filling supercharging, hydraulic pressure in the cylindrical shell 1 can reach data acquisition module and finally be converted to readable signal by controller by pressure transducer simultaneously, when the hydraulic pressure in the cylindrical shell 1 reaches pressure set points, stop water filling, and at this pressure set points place pressurize certain hour;
(3) draining release, and control drainage speed;
(4) the sealing situation at observation gasket seal place if any leakage phenomenon, shows that then the sealing pad does not reach the nuclear power generating equipment request for utilization; As do not have leakage phenomenon, and continue gasket seal to be tested by set point number repeating step (1) to (3), can bear the sealing reliability that the number of times of checking and not revealing is judged gasket seal according to gasket seal.The test cycle index of present embodiment can be set repeatedly as required, if test can bear the amount of testing of setting and do not reveal with gasket seal, then thinks the favorable sealing property of sealing pad can reach the request for utilization of nuclear power generating equipment.
According to test situation, about 1,000,000 times of the cycle index that the verifying attachment of embodiment 1 can the bearing strength hydraulic testing.
The method of inspection that the verifying attachment that present embodiment provides another kind to utilize embodiment 1 is tested with gasket seal to nuclear power generating equipment, promptly big temperature difference heat cyclic test method.
The test condition of described big temperature difference heat cyclic test method is:
Test temperature :≤364 ℃
Test(ing) medium: deionized water
Test range hydraulic pressure :≤17.2MPa
Temperature rate: 〉=90 ℃/h
May further comprise the steps:
(1) get gasket seal and respective flanges, according to gasket seal pretension is installed and is loaded fasteningly than pressure request, then by high-pressure hydraulic pump 13 water filling to the cylindrical shell 1 of autoclave in, while exhaust apparatus 7 is opened fills with water in cylindrical shell 1;
(2) water of being controlled in 5 pairs of cylindrical shells of heating arrangement 1 by temperature control modules heats, and the temperature in the cylindrical shell 1 is risen, and simultaneously owing to the water expanded by heating, the pressure in the cylindrical shell 1 is also increasing gradually; At this moment, the pressure control module must be controlled hydraulic pressure in the cylindrical shell 1 according to certain rate of pressurization steady change by in good time draining, and the water temperature in cylindrical shell 1 rises to setting value (this desired temperature can between 100 ℃ ~ 364 ℃) as required;
(3) make the pressure in the autoclave reduce to 0.1 ~ 5MPa by 1 draining of control cylindrical shell simultaneously, this moment, cylindrical shell 1 was interior because draining formation certain space promptly forms the vapour chamber, and so far the water in the cylindrical shell 1 is that vapour-liquid is mixed phase by full liquid-phase conversion;
(4) continue the water that is in vapour-liquid mixing phase in the cylindrical shell 1 is heated, rise to setting value (this setting value can between 100 ℃ ~ 364 ℃) as required until temperature, controlling pressure in the cylindrical shell 1 simultaneously reaches pressure set points (this pressure set points is between 0.1MPa ~ 17.2 MPa, substantially to the saturated vapor pressure under should design temperature), finish temperature-rise period to this;
(5) after step (4) heats up and stops, water in 6 pairs of cylindrical shells of temperature control modules control cooling device 1 cools off, when pressure and temperature is reduced to setting value (pressure is substantially to the saturated vapor pressure under should temperature), control system 8 is opened spray equipment 10 according to program setting and is made it water spray, and the pressure surge in the cylindrical shell 1 is bigger at this moment; The effect of spray equipment 10 is to eliminate above-mentioned formed vapour chamber, water in cylindrical shell 1 is converted into full liquid phase mutually once more by the vapour-liquid mixing (must be stable by control system 8 controlled pressures in the vapour process that disappears, often situation about occurring is that pressure falls too soon, can stop spray this moment, by water is carried out heat temperature raising pressure is gone up to some extent, to guarantee the stable decline of pressure in the whole step-down process; Certainly, this process must accurately control by control system 8, makes the pressure stability variation by spray step-down and the heating two kinds of means actings in conjunction of boosting in good time);
(6) cooling device 6 continues cooling, simultaneously also can be toward logical heat eliminating medium in the cooling jacket 11 to bring into play the effect of auxiliary cooling, make device at the uniform velocity be cooled to 0.1 ℃ ~ 99.9 ℃, in addition, must guarantee also in the cooling procedure that pressure stability drops to setting range and (is generally 1 ~ 5MPa), if it is too fast that pressure descends, can adopt the mode controlled pressure of water filling supercharging slowly to descend;
(7) the sealing situation at observation gasket seal place if any leakage phenomenon, shows that then the sealing pad does not reach the nuclear power generating equipment request for utilization; As do not have leakage phenomenon, and continue repeating step (2) to (7) gasket seal is tested, can bear the sealing reliability that the number of times of checking and not revealing is judged gasket seal according to gasket seal.
Present embodiment can be set the test cycle index of step (2) to step (7) according to the requirement of gasket seal, be generally 〉=30 times, if test can be born the amount of testing of setting with gasket seal and do not revealed, then think and the favorable sealing property of sealing pad can reach the request for utilization of nuclear power generating equipment.
According to test situation, the verifying attachment of embodiment 1 can bear about 600,000 times of the cycle index of big temperature difference heat cyclic test.
Other need to prove, when carrying out big temperature difference heat cyclic test, can in cyclic process, intert as required and carry out the intensity hydraulic testing, perhaps in the cyclic process of carrying out the intensity hydraulic testing, intert and carry out big temperature difference heat cyclic test, can set up more harsh test condition like this, to consider and to check the sealing property of gasket seal from many aspects.
More than the present invention has been done detailed description; its purpose is to allow the personage that is familiar with this art can understand content of the present invention and is implemented; can not limit protection scope of the present invention with this; all equivalences of doing according to spirit of the present invention change or modify, and all should be encompassed in protection scope of the present invention
Claims (6)
1. a nuclear power generating equipment is with the service check device of gasket seal, it is characterized in that: the heating arrangement (5) that described verifying attachment comprises autoclave, be used for described autoclave is heated, be arranged on cooling device (6), exhaust apparatus (7) and control system (8) in the described autoclave, wherein:
Described autoclave is included in top and bottom all to be had the cylindrical shell (1) of opening, can be arranged on the upper flange plate (2) and the lower flange (3) of described cylindrical shell (1) top end opening and bottom opening position respectively with dismantling, and described upper flange plate (2) and lower flange (3) one in the two is provided with a plurality of interfaces (4) that are used to be connected exterior tubing and control element;
Temperature control modules, data acquisition module and controller that described control system (8) comprises the pressure control module that is used to control described cylindrical shell (1) internal pressure of linking to each other with described interface (4), described cylindrical shell (1) heated up and/or lowers the temperature by control described heating arrangement (5) and described cooling device (6); Described data acquisition module is used to gather the pressure and temperature signal of described pressure control module and described temperature control modules gained and is sent to described controller; Described controller is according to from the signal of described data acquisition module described pressure control module and described temperature control modules being controlled.
2. the nuclear power generating equipment according to claim 1 service check device of gasket seal, it is characterized in that: described upper flange plate (2) is connected with described cylindrical shell (1) by threaded fastener (9) with lower flange (3).
3. the nuclear power generating equipment according to claim 1 service check device of gasket seal, it is characterized in that: described verifying attachment also comprises the water that is infused in the described cylindrical shell (1), described heating arrangement comprises heating tube, and it is arranged in described water and water is heated.
4. the nuclear power generating equipment according to claim 3 service check device of gasket seal is characterized in that: described verifying attachment also comprises the liquid level gauge (15) that can measure the liquid level in the described cylindrical shell (1).
5. the nuclear power generating equipment according to claim 3 service check device of gasket seal is characterized in that: described verifying attachment also comprises the spray equipment (10) that is arranged in the described cylindrical shell (1), and this spray equipment (10) is medium with water.
6. the nuclear power generating equipment according to claim 1 service check device of gasket seal is characterized in that: described cylindrical shell (1) peripheral hardware is useful on the cooling jacket (11) of logical heat eliminating medium.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201110078632 CN102279080B (en) | 2011-03-30 | 2011-03-30 | Performance test device for sealing gasket of nuclear power equipment |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201110078632 CN102279080B (en) | 2011-03-30 | 2011-03-30 | Performance test device for sealing gasket of nuclear power equipment |
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| CN102279080A true CN102279080A (en) | 2011-12-14 |
| CN102279080B CN102279080B (en) | 2013-03-27 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN 201110078632 Active CN102279080B (en) | 2011-03-30 | 2011-03-30 | Performance test device for sealing gasket of nuclear power equipment |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107845435A (en) * | 2017-11-28 | 2018-03-27 | 中国原子能科学研究院 | Sealed cylinder |
| CN112557024A (en) * | 2020-12-28 | 2021-03-26 | 苏州宝骅密封科技股份有限公司 | Performance inspection device of flange sealing gasket for heat exchange equipment |
Citations (6)
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| DE2643274A1 (en) * | 1976-09-25 | 1978-03-30 | Interatom | Seal esp. for nuclear power plant access openings - has U=section flexible strip and expanding element |
| CN2206873Y (en) * | 1994-08-31 | 1995-09-06 | 昆山市釜用机械密封件厂 | Seal device for high-speed, high-temp and high-pressure cauldron |
| JPH07318683A (en) * | 1994-05-25 | 1995-12-08 | Mitsubishi Heavy Ind Ltd | Pressure vessel |
| CN1936539A (en) * | 2006-10-13 | 2007-03-28 | 中核东方工程有限责任公司 | High-pressure pot device for muclear electric material static corrosion test |
| CN101799349A (en) * | 2010-04-07 | 2010-08-11 | 苏州宝骅机械技术有限公司 | Device and method for detecting sealing property of sealing component |
| CN202024861U (en) * | 2011-03-30 | 2011-11-02 | 苏州宝骅机械技术有限公司 | Performance inspection device for sealing gasket for nuclear power equipment |
-
2011
- 2011-03-30 CN CN 201110078632 patent/CN102279080B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2643274A1 (en) * | 1976-09-25 | 1978-03-30 | Interatom | Seal esp. for nuclear power plant access openings - has U=section flexible strip and expanding element |
| JPH07318683A (en) * | 1994-05-25 | 1995-12-08 | Mitsubishi Heavy Ind Ltd | Pressure vessel |
| CN2206873Y (en) * | 1994-08-31 | 1995-09-06 | 昆山市釜用机械密封件厂 | Seal device for high-speed, high-temp and high-pressure cauldron |
| CN1936539A (en) * | 2006-10-13 | 2007-03-28 | 中核东方工程有限责任公司 | High-pressure pot device for muclear electric material static corrosion test |
| CN101799349A (en) * | 2010-04-07 | 2010-08-11 | 苏州宝骅机械技术有限公司 | Device and method for detecting sealing property of sealing component |
| CN202024861U (en) * | 2011-03-30 | 2011-11-02 | 苏州宝骅机械技术有限公司 | Performance inspection device for sealing gasket for nuclear power equipment |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107845435A (en) * | 2017-11-28 | 2018-03-27 | 中国原子能科学研究院 | Sealed cylinder |
| CN112557024A (en) * | 2020-12-28 | 2021-03-26 | 苏州宝骅密封科技股份有限公司 | Performance inspection device of flange sealing gasket for heat exchange equipment |
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| CN102279080B (en) | 2013-03-27 |
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Address after: Shuangfeng Taicang Suzhou City, Jiangsu province 215415 city's Economic Development Zone Patentee after: Suzhou Bao Hua sealing Polytron Technologies Inc Address before: Shuangfeng Taicang Suzhou City, Jiangsu province 215415 city's Economic Development Zone Patentee before: Suzhou Baohua Mechanical Technology Co., Ltd. |