CN103594125A - Sealing ring used for reactor pressure vessel - Google Patents
Sealing ring used for reactor pressure vessel Download PDFInfo
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- CN103594125A CN103594125A CN201310616690.9A CN201310616690A CN103594125A CN 103594125 A CN103594125 A CN 103594125A CN 201310616690 A CN201310616690 A CN 201310616690A CN 103594125 A CN103594125 A CN 103594125A
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- sealing ring
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- pressure vessel
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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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Abstract
The invention discloses a sealing ring used for a reactor pressure vessel, which comprises a coating layer in a hollow circular ring state, an interface layer and a built-in layer, the interface layer is accommodated in a hollow structure of the coating layer and clung to the inner wall of the coating layer, the built-in layer is accommodated in the hollow structure of the interface layer and clung to the inner wall of the interface layer, the cross section of the coating layer, the interface layer and the built-in layer are in a C-shaped structure, the built-in layer forms a spiral tightening spring in a circular ring state which is characterized by welding end to end by winding a wire material with a cylindrical shape, the spiral tightening spring clings to the part behind the inner wall of the interface layer, and has gap to the inner wall of the interface layer, wherein, the wire material is a nickel-based high temperature alloy material, the mass percentage of cobalt in the nickel-based high temperature alloy material is less than or equal to 0.1%, and mass percentage of copper is less than or equal to 0.2%. The nationalized sealing ring is capable of adapting the conditions of high temperature, high voltage, and instantaneous large temperature difference and pressure fluctuation in a nuclear power station, the sealing ring can ensure sealing performance of the reactor pressure vessel, and simultaneously, the cost is reduced.
Description
Technical field
The present invention relates to nuclear power plant reactor sealing for pressure vessels field, relate in particular to a kind of reactor pressure vessel sealing ring.
Background technology
At present, presurized water reactor is the main flow heap type of nuclear power station, the reactor in the whole world approximately 60% is all presurized water reactor, pressurized-water reactor nuclear power plant is generally divided into two loops: a circuit system and secondary coolant circuit system, one circuit system is called nuclear island part, secondary coolant circuit system is conventional island part, has steam turbine part and master section.One circuit system and the secondary coolant circuit system of pressurized-water reactor nuclear power plant separate completely, and it is an airtight circulation system.The principle process of nuclear power station is: main pump is sent pressure coolant into reactor, and the heat energy that cooling medium is emitted nuclear fuel is taken reactor out of, and enters steam generator, by heat-transfer pipe, heat is passed to the secondary circuit water outside pipe, makes water boiling produce steam; Coolant flow, after steam generator, then is sent into reactor by main pump, and circulation, constantly takes and change generation steam out of the heat in reactor so back and forth, from steam generator high temperature and high pressure steam out, promotes Turbo-generator Set generating.The waste vapour of doing merit condenses into water in condenser, then sends into well heater by the feed pump that condenses, and after reheating, sends steam generator back to, the secondary circuit circulation system that Here it is.
Wherein, nuclear power plant reactor pressure vessel is comprised of cylindrical shell and top cover two parts, between cylindrical shell and top cover, by shell flange, top cover flange and seal, is realized and being tightly connected.The existence of seal has guaranteed that the leakage rate of cooling medium in pressure vessel can maintain in allowed limits.At present, the seal that China's nuclear power plant reactor pressure vessel is used and the material using thereof are external product, because this product is that the difficulty of the staple product ,Gu nuclear power unit of operation relevant to nuclear safety application home products is larger.Yet the cost of a set of sealing for pressure vessels part needs hundreds of thousands, and often open primary first-order equation heap top cover with regard to needing more transducer set seal, caused thus the expensive of seal.Therefore, seal production domesticization is not only of great importance in economic benefit, and Chinese Nuclear Power localization process is had to important strategic importance.
In addition, when nuclear power station unit normally moves, require seal can bear high temperature, high pressure operating mode; During Unit Commitment heap, seal will bear the large action of thermal difference that lifting/lowering temperature speed reaches 28 ℃/h, and in some cases, the transient state temperature difference also likely reaches 128 ℃; In addition, under some transient condition of the normal operation of unit, seal also will bear the effect of pressure surge.Therefore the sealing property of seal has been proposed to very high requirement, these requirements are that conventional seal institute is unappeasable.In addition, the cooling medium in pressure vessel has high radioactivity, if occur to leak will serious threat society safety.
Therefore, be necessary to develop a kind of seal that can adapt to nuclear power station high temperature, high pressure and the instantaneous large temperature difference, pressure surge operating mode of production domesticization, guarantee the sealing property of reactor pressure vessel, to guarantee the safe operation of nuclear power station, reduce costs simultaneously.
Summary of the invention
The object of the present invention is to provide a kind of sealing ring that can adapt to nuclear power station high temperature, high pressure and the instantaneous large temperature difference, pressure surge operating mode of production domesticization, guarantee the sealing property of reactor pressure vessel, to guarantee the safe operation of nuclear power station, reduce costs simultaneously.
For achieving the above object, technical scheme of the present invention is: a kind of reactor pressure vessel sealing ring is provided, described sealing ring is circular, described sealing ring comprises the clad that is hollow circular ring shape, middle layer and build-up layer, described middle layer is placed in the hollow structure of described clad and is close to the inwall of described clad, described build-up layer is placed in the hollow structure in described middle layer and is close to the inwall in described middle layer, and described clad, the cross section of described middle layer and described build-up layer is c-shaped structure all, wherein, be circular spiral the tight spring of described build-up layer for forming by a cylindrical Wire-winding, the head and the tail of described spiral tight spring weld mutually, and described spiral tight spring are close to after the inwall in described middle layer, between described spiral tight spring and the inwall in described middle layer, also there is space, and described silk material is nickel base superalloy material, in described nickel base superalloy, the mass percentage content of cobalt is less than or equal to 0.1%, the mass percentage content of copper is less than or equal to 0.2%.
Preferably, the grain size number of described nickel base superalloy silk material is more than or equal to 5 grades.
Preferably, described middle layer is by the band material forming of a nichrome material, and the head and the tail of described band weld mutually, and wherein, in described nichrome, the mass percentage content of cobalt is less than or equal to 0.1%, and the mass percentage content of copper is less than or equal to 0.2%.
Preferably, the grain size number of described nichrome band is more than or equal to 5 grades.
Preferably, described clad is with moulding by silver, and the head and the tail of described silver band weld mutually, and in described silver band, the purity of silver is more than or equal to 99.99%.
Preferably, effective springback capacity of described sealing ring is more than or equal to 0.20 millimeter, and total springback capacity of described sealing ring is more than or equal to 0.25 millimeter.
Preferably, the temperature rate that described sealing ring bears is more than or equal to 28 ℃/h.
Preferably, in heating and cooling process, the slip of described sealing ring is less than or equal to 0.1L/h; When temperature, pressure stability, described sealing ring is without leakage.
Preferably, described clad circumferentially offers the first opening along it, and described middle layer circumferentially offers the second opening along it, and described the first opening is corresponding with described the second opening and be communicated with.
Compared with prior art, due to reactor pressure vessel sealing ring of the present invention, it comprises the clad that is hollow circular ring shape, middle layer and build-up layer, described middle layer is placed in the hollow structure of described clad and is close to the inwall of described clad, described build-up layer is placed in the hollow structure in described middle layer and is close to the inwall in described middle layer, and described clad, the cross section of described middle layer and described build-up layer is c-shaped structure all, wherein, be circular spiral the tight spring of described build-up layer for forming by a cylindrical Wire-winding, the head and the tail of described spiral tight spring weld mutually, and described spiral tight spring are close to after the inwall in described middle layer, between described spiral tight spring and the inwall in described middle layer, also there is space, and described silk material is nickel base superalloy material, in described nickel base superalloy, the mass percentage content of cobalt is less than or equal to 0.1%, the mass percentage content of copper is less than or equal to 0.2%.During work, sealing ring is impaction state under bolt pretightening effect, and itself and sealing surface fit tightly and play sealing function; When pressure medium or/and temperature while occur changing, the stability that is kept sealing property by the compression-rebound characteristics of spiral tight spring, thereby guarantee the sealing property of reactor pressure vessel, guarantee the safe operation of nuclear power station, and can adapt to nuclear power station high temperature, high pressure and the instantaneous large temperature difference, pressure surge operating mode, adopt the starting material of production domesticization to produce described sealing ring simultaneously, can not only significantly reduce the production cost of sealing ring, and Chinese Nuclear Power localization process is had to important strategic importance.
Accompanying drawing explanation
Fig. 1 is the structural representation of sealing ring of the present invention.
Fig. 2 is the cut-open view along A-A line in Fig. 1.
Fig. 3 is the cut-open view along B-B line in Fig. 2.
Fig. 4 is compression-rebound characteristics curve map of sealing ring of the present invention.
Fig. 5 is the cut-open view that is equiped with the reactor pressure vessel of sealing ring of the present invention.
Fig. 6 is the enlarged diagram of A part in Fig. 5.
Fig. 7 is the enlarged diagram of B part in Fig. 6.
Embodiment
With reference now to accompanying drawing, describe embodiments of the invention, in accompanying drawing, similarly element numbers represents similar element.The sealing ring 1 of production domesticization provided by the invention, can adapt to nuclear power station high temperature, high pressure and the instantaneous large temperature difference, pressure surge operating mode, guarantees the sealing property of reactor pressure vessel, to guarantee the safe operation of nuclear power station, reduces costs simultaneously.
As shown in Figure 1, sealing ring 1 for reactor pressure vessel provided by the present invention, it is circular, and sealing ring of the present invention 1 is major diameter sealing ring, preferably, sealing ring 1 of the present invention is mainly that diameter is the sealing ring of 3983.1mm, two kinds of models of 4071.1mm.
As shown in Figure 1-Figure 3, described sealing ring 1 comprises clad 11, middle layer 12 and the build-up layer 13 that is hollow circular ring shape, described middle layer 12 is placed in the hollow structure of described clad 11 and is close to the inwall of described clad 11, described build-up layer 13 is placed in the hollow structure in described middle layer 12 and is close to the inwall in described middle layer 12, and the cross section of described clad 11, described middle layer 12 and described build-up layer 13 is c-shaped structure (see figure 2) all, therefore sealing ring of the present invention 1 is called again C type sealing ring.
As shown in Figure 2 and Figure 3, described build-up layer 13 is circular spiral the tight springs that are that form by a cylindrical Wire-winding, and the head and the tail of described spiral tight spring weld mutually; Therefore, the c-shaped structure in the cross section of build-up layer 13.Spiral tight spring are placed in behind middle layer 12, and described spiral tight spring are close to the inwall in described middle layer 12; But because the also tight spring of spiral is formed by cylindrical Wire-winding, therefore, its outside surface is corrugated, and is not smooth curved surface, so also have a fixed gap 14(between described spiral the tight outside surface of spring and the inwall in described middle layer 12, sees Fig. 3).
In the present invention, described spiral tight spring adopt the Wire-winding of nickel base superalloy material to form, in described nickel base superalloy, the mass percentage content of cobalt is less than or equal to 0.1%, the mass percentage content of copper is less than or equal to 0.2%, and the grain size number of described nickel base superalloy silk material is more than or equal to 5 grades.Preferably, the material of described silk material is GH4145 alloy, GH4145 alloy is mainly to carry out mutually the nickel base superalloy of ageing strengthening with γ ', it has good corrosion-resistant and antioxygenic property below at 980 ℃, at 800 ℃, there is below higher intensity, at 540 ℃, there is below good resistance to relaxation property, also there is good forming property and welding performance simultaneously.This alloy is mainly for the manufacture of working below and higher resistance to lax plane spring and the volute springs of desired strength at 800 ℃.Therefore, adopt silk material manufacture spiral of the present invention the tight spring of this material, it has good rebound characteristics, thus lift-off seal performance.
In addition, in the present invention, nickel base superalloy silk material, before the also tight spring for coiling spiral, need to carry out EDDY CURRENT to it, to guarantee the quality of a material and spiral tight spring.
Make by the band of a nichrome material in middle layer 12 of the present invention, and the head and the tail of described band weld mutually, thereby make whole band only have a welding joint.Wherein, in nichrome, the mass percentage content of cobalt is less than or equal to 0.1%, and the mass percentage content of copper is less than or equal to 0.2%, and the grain size number of described nichrome band is more than or equal to 5 grades.Preferably, middle layer 12 adopts GH600 band to make; GH600 band form circular after, then by the two ends welding of band, therefore whole band only has a welding joint.Because GH600 alloy is nickel-chromium-iron-based solid solution strengthened alloy, therefore there is good high-temperature corrosion resistance and antioxygenic property, and there is good cold and hot working and welding performance, it has satisfied heat resistance and high-ductility below at 700 ℃, therefore, the effect of good spacer medium and environment is played in middle layer 12, plays good sealing function.
Preferably, described clad 11 is made by silver band, and the head and the tail of described silver band weld mutually, and therefore, whole silver band only has a welding joint.And in silver band, the purity of silver is more than or equal to 99.99%, and requires silver to have low-down air content.Because silver-colored hardness is less than the hardness of nichrome, therefore, clad 11 has high-ductility, thereby plays the effect of making up preferably when it is contacted with the sealing surface in middle layer 12.
The clad 11 of sealing ring 1 of the present invention is made by silver band, make by the band of nichrome material in middle layer 12, build-up layer 13 adopts GH4145 alloy to make, clad 11, middle layer 12 and build-up layer 13 all adopt home made materials to make, the sealing ring of preparing compared to available technology adopting foreign material, production cost significantly reduces.
For mechanical property and the sealing property of check sealing ring 1 of the present invention, also need sealing ring 1 of the present invention to carry out the test of Load-displacement Characteristics of Ram curve determination and large temperature gradient thermal cycling test, describe respectively below.
Consult shown in Fig. 4, in order to check compressibility and the rebound resilience of sealing ring 1 of the present invention, need to carry out the test of Load-displacement Characteristics of Ram curve determination to described sealing ring 1; By C type sealing ring 1, carry out the test of Load-displacement Characteristics of Ram curve, can record decrement and the springback capacity of sealing ring 1.
In compression-rebound characteristics curve of sealing ring 1 as shown in Figure 4, when reaching initial sealing state, the decrement of sealing ring 1 is e
0mm, now the fastening load in the necessary unit length of sealing ring 1 is Y
0n/mm; When sealing ring 1 keeps sealing state, and while being compressive state, the optimal compression amount of sealing ring 1 (that is, working point decrement) is e
2mm, accordingly, now the fastening load in sealing ring 1 unit length is Y
2n/mm; And sealing ring 1 guarantees that the limit decrement of sealing state is e
cmm; At e
0-e
2in the interval forming, the random single hole leak rate of helium vacuum is less than 1.33 * l0
-9pa.m
3/ s.
In addition, from above-mentioned compression-rebound characteristics curve, also can see, from compressive state e
2when place is offloaded to seal failure, the decrement of sealing ring 1 correspondence is e
1mm, correspondingly, now the fastening load in sealing ring 1 unit length is Y
1n/mm; And when sealing ring 1 is offloaded to zero, the set deformation volume of sealing ring 1 correspondence is e1`mm; Compression-the rebound characteristics of sealing ring 1 of the present invention is: effective springback capacity L
1(be e
2-e
1) be more than or equal to 0.20 millimeter, and total springback capacity L of described sealing ring 1
2(be e
2-e
1`) be more than or equal to 0.25 millimeter.
In addition, in order to verify the performance of C type sealing ring 1 under actual applying working condition, also need sealing ring 1 to carry out large temperature gradient thermal cycling test.According to the mounting structure of sealing ring 1 in the heating power operating mode in actual nuclear power station one loop and reactor pressure vessel, when sealing ring 1 is carried out to large temperature gradient thermal cycling test, top pressure is 15.5MPa, and maximum temperature is 343 ± 5 ℃, cycle index >=30 time, temperature rate >=28 ℃/h.During test, in heating and cooling process, slip is necessary≤0.1L/h; When temperature, pressure are all stablized, there is not any leakage and abnormal occurrence in sealing ring 1, so the laminating acceptance criteria of sealing ring 1.Therefore temperature rate >=28 ℃ that, sealing ring 1 of the present invention can bear.
Consult below shown in Fig. 5-Fig. 7, the concrete application of sealing ring 1 of the present invention is described.
As shown in Figure 5, nuclear power plant reactor pressure vessel 2 comprises cylindrical shell 21 and top cover 22, wherein, cylindrical shell 21 is provided with cooling medium and imports and exports ozzle 212, and the upper end of cylindrical shell 21 is provided with shell flange 211, on top cover 22, be provided with the top cover flange 221 corresponding with shell flange 211, cylindrical shell 21 is tightly connected by shell flange 211, top cover flange 221 mutually with top cover 22, and is provided with at least one sealing ring 1 between shell flange 211, top cover flange 221.
Consult shown in Fig. 5-Fig. 7, in the present embodiment, between shell flange 211, top cover flange 221, be provided with two seals ring 1.Particularly, offer the storage tank corresponding with sealing ring 1 222 on top cover flange 221, sealing ring 1 correspondence is placed in described storage tank 222, and is also provided with fixture 3 with fixing seal ring 1 in a side of storage tank 222.Wherein, fixture 3 comprises trip bolt 31 and geometrical clamp 32, geometrical clamp 32 has a fixed part 321, from one end bending of fixed part 321, extend to form a clamping part 322, fixed part 321 is fixed on top cover flange 221 by trip bolt 31, clamping part 322 is to the interior extension of storage tank 222 and press on the outer wall of sealing ring 1, and the first opening 111 on sealing ring 1, the second opening 121 are positioned at the side away from clamping part 322, it is also the opposite face that the first opening 111, the second opening 121 are positioned at pressure-bearing side.During work, sealing ring 1 presents impaction state under bolt pretightening effect, fits tightly and plays sealing function with sealing surface; When pressure medium or/and temperature while occur changing, is kept the stability of sealing property by compression-rebound characteristics of built-in spiral tight spring.
Due to sealing ring 1 for reactor pressure vessel of the present invention, it comprises the clad 11 that is hollow circular ring shape, middle layer 12 and build-up layer 13, described middle layer 12 is placed in the hollow structure of described clad 11 and is close to the inwall of described clad 11, described build-up layer 13 is placed in the hollow structure in described middle layer 12 and is close to the inwall in described middle layer 12, and described clad 11, the cross section of described middle layer 12 and described build-up layer 13 is c-shaped structure all, wherein, be circular spiral the tight spring of described build-up layer 13 for forming by a cylindrical Wire-winding, the head and the tail of described spiral tight spring weld mutually, and described spiral tight spring are close to after the inwall in described middle layer 12, between described spiral tight spring and the inwall in described middle layer 12, also there is space, and described silk material is nickel base superalloy material, in described nickel base superalloy, the mass percentage content of cobalt is less than or equal to 0.1%, the mass percentage content of copper is less than or equal to 0.2%.During work, sealing ring 1 is impaction state under the effect of bolt pretightening, and itself and sealing surface fit tightly and play sealing function; When pressure medium or/and temperature while occur changing, the stability that is kept sealing property by the compression-rebound characteristics of spiral tight spring, thereby guarantee the sealing property of reactor pressure vessel 2, guarantee the safe operation of nuclear power station, and can adapt to nuclear power station high temperature, high pressure and the instantaneous large temperature difference, pressure surge operating mode, adopt the starting material of production domesticization to produce described sealing ring 1 simultaneously, can not only significantly reduce the production cost of sealing ring 1, and Chinese Nuclear Power localization process is had to important strategic importance.
Other structures of reactor pressure vessel 2 of the present invention are well known to those of ordinary skill in the art, at this, are no longer described in detail.
Above disclosed is only the preferred embodiments of the present invention, certainly can not limit with this interest field of the present invention, and the equivalent variations of therefore doing according to the present patent application the scope of the claims, still belongs to the scope that the present invention is contained.
Claims (9)
1. a reactor pressure vessel sealing ring, described sealing ring is circular, it is characterized in that: described sealing ring comprises the clad that is hollow circular ring shape, middle layer and build-up layer, described middle layer is placed in the hollow structure of described clad and is close to the inwall of described clad, described build-up layer is placed in the hollow structure in described middle layer and is close to the inwall in described middle layer, and described clad, the cross section of described middle layer and described build-up layer is c-shaped structure all, wherein, be circular spiral the tight spring of described build-up layer for forming by a cylindrical Wire-winding, the head and the tail of described spiral tight spring weld mutually, and described spiral tight spring are close to after the inwall in described middle layer, between described spiral tight spring and the inwall in described middle layer, also there is space, and described silk material is nickel base superalloy material, in described nickel base superalloy, the mass percentage content of cobalt is less than or equal to 0.1%, the mass percentage content of copper is less than or equal to 0.2%.
2. reactor pressure vessel sealing ring as claimed in claim 1, is characterized in that: the grain size number of described nickel base superalloy silk material is more than or equal to 5 grades.
3. reactor pressure vessel sealing ring as claimed in claim 1, it is characterized in that: described middle layer is by the band material forming of a nichrome material, the head and the tail of described band weld mutually, wherein, in described nichrome, the mass percentage content of cobalt is less than or equal to 0.1%, and the mass percentage content of copper is less than or equal to 0.2%.
4. reactor pressure vessel sealing ring as claimed in claim 3, is characterized in that: the grain size number of described nichrome band is more than or equal to 5 grades.
5. reactor pressure vessel sealing ring as claimed in claim 1, is characterized in that: described clad is with moulding by silver, and the head and the tail of described silver band weld mutually, and in described silver band, the purity of silver is more than or equal to 99.99%.
6. reactor pressure vessel sealing ring as claimed in claim 1, it is characterized in that: effective springback capacity of described sealing ring is more than or equal to 0.20 millimeter, and total springback capacity of described sealing ring is more than or equal to 0.25 millimeter.
7. reactor pressure vessel sealing ring as claimed in claim 1, is characterized in that: the temperature rate that described sealing ring bears is more than or equal to 28 ℃/h.
8. reactor pressure vessel sealing ring as claimed in claim 1, is characterized in that: in heating and cooling process, the slip of described sealing ring is less than or equal to 0.1L/h; When temperature, pressure stability, described sealing ring is without leakage.
9. reactor pressure vessel sealing ring as claimed in claim 1, it is characterized in that: described clad circumferentially offers the first opening along it, described middle layer circumferentially offers the second opening along it, and described the first opening is corresponding with described the second opening and be communicated with.
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CN201310616690.9A CN103594125A (en) | 2013-11-27 | 2013-11-27 | Sealing ring used for reactor pressure vessel |
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CN201310616690.9A CN103594125A (en) | 2013-11-27 | 2013-11-27 | Sealing ring used for reactor pressure vessel |
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Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104409116A (en) * | 2014-10-27 | 2015-03-11 | 宁波天生密封件有限公司 | CAP1400 metal O-type sealing ring detection method and experiment platform |
CN106935283A (en) * | 2015-11-16 | 2017-07-07 | 通用电气-日立核能美国有限责任公司 | Nuclear reactor stream sealing system and seal |
CN117145962A (en) * | 2023-10-30 | 2023-12-01 | 沈阳精航科技有限公司 | Method for improving deformation elasticity of fluid seal C-shaped sealing ring |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5577472A (en) * | 1995-06-07 | 1996-11-26 | Cummins Engine Company, Inc. | Spring-energized cylinder head combustion seal assembly |
CN101865288A (en) * | 2010-05-13 | 2010-10-20 | 励行根 | Cladding sealing ring and manufacturing method thereof |
CN102080725A (en) * | 2011-02-01 | 2011-06-01 | 宁波天生密封件有限公司 | Intelligent wrapped C-shaped sealing ring |
JP4819592B2 (en) * | 2006-06-22 | 2011-11-24 | 三菱電線工業株式会社 | Sealing structure |
CN202176712U (en) * | 2011-02-01 | 2012-03-28 | 宁波天生密封件有限公司 | C-shaped cladding sealing ring with built-in spring |
-
2013
- 2013-11-27 CN CN201310616690.9A patent/CN103594125A/en active Pending
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5577472A (en) * | 1995-06-07 | 1996-11-26 | Cummins Engine Company, Inc. | Spring-energized cylinder head combustion seal assembly |
JP4819592B2 (en) * | 2006-06-22 | 2011-11-24 | 三菱電線工業株式会社 | Sealing structure |
CN101865288A (en) * | 2010-05-13 | 2010-10-20 | 励行根 | Cladding sealing ring and manufacturing method thereof |
CN102080725A (en) * | 2011-02-01 | 2011-06-01 | 宁波天生密封件有限公司 | Intelligent wrapped C-shaped sealing ring |
CN202176712U (en) * | 2011-02-01 | 2012-03-28 | 宁波天生密封件有限公司 | C-shaped cladding sealing ring with built-in spring |
Non-Patent Citations (1)
Title |
---|
励行根等: ""反应堆压力容器"C"形密封环的研制"", 《压力容器》 * |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104409116A (en) * | 2014-10-27 | 2015-03-11 | 宁波天生密封件有限公司 | CAP1400 metal O-type sealing ring detection method and experiment platform |
CN104409116B (en) * | 2014-10-27 | 2017-06-30 | 宁波天生密封件有限公司 | The O-shaped sealing ring detection method of CAP1400 metals and experiment porch |
CN106935283A (en) * | 2015-11-16 | 2017-07-07 | 通用电气-日立核能美国有限责任公司 | Nuclear reactor stream sealing system and seal |
CN117145962A (en) * | 2023-10-30 | 2023-12-01 | 沈阳精航科技有限公司 | Method for improving deformation elasticity of fluid seal C-shaped sealing ring |
CN117145962B (en) * | 2023-10-30 | 2024-01-09 | 沈阳精航科技有限公司 | Method for improving deformation elasticity of fluid seal C-shaped sealing ring |
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Application publication date: 20140219 |