CN210637513U - Nuclear-grade electric sodium bellows stop valve - Google Patents
Nuclear-grade electric sodium bellows stop valve Download PDFInfo
- Publication number
- CN210637513U CN210637513U CN201921552877.6U CN201921552877U CN210637513U CN 210637513 U CN210637513 U CN 210637513U CN 201921552877 U CN201921552877 U CN 201921552877U CN 210637513 U CN210637513 U CN 210637513U
- Authority
- CN
- China
- Prior art keywords
- valve
- sodium
- valve body
- stop valve
- corrugated pipe
- 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.)
- Active
Links
Images
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model relates to a sodium stop valve, it belongs to the valve that is applied to in the fast neutron breeds reactor that has the function of cutting. The nuclear-grade electric sodium bellows stop valve is composed of core components such as a valve body, a valve clack, a valve rod, a valve clack pressing sleeve, a bellows, a valve cover, a radiating fin, a packing pressing sleeve, a packing pressing plate leakage detection device, a preheating device, an electric fitting and the like; the valve body adopts an integral forging structure, welding seams or sealing joints are reduced, the sealing is reliable, the structure is compact, the wall thickness is uniform, the fatigue resistance of the valve is good in the using process, and the deformation resistance is strong; the valve is designed into a vertical radiating fin structure, so that the radiating efficiency is improved, the overall rigidity of the valve is enhanced, and the anti-seismic performance of the whole machine is improved. The valve body is provided with the heat tracing and temperature feedback device, so that the sodium stop valve can be reliably preheated to the required temperature, and the safe operation of the sodium stop valve is ensured, thereby ensuring the safe operation of the whole nuclear power station.
Description
Technical Field
The utility model relates to a sodium stop valve, it belongs to the valve that is applied to in the fast neutron breeds reactor that has the function of cutting.
Background
The fast breeder reactor (fast reactor) is the fourth generation advanced nuclear reactor in the world, and uses liquid metal sodium as a cooling medium, so that the utilization rate of natural uranium resources can be improved to more than 60 percent from about 1 percent of a pressurized water reactor, the generation amount of nuclear waste is reduced to the maximum degree, and the minimization of radioactive waste is realized. The international society generally considers that the development and popularization of fast reactor can fundamentally solve the problems of sustainable development and green development of world energy. The nuclear sodium stop valve is mainly applied to the pipelines of a first loop and a second loop of a fast neutron breeder reactor and an auxiliary system thereof, a sodium process system, a damage detection system and a thermal control system, and has the function of cutting off or conveying media in the pipelines.
Because the liquid metal sodium is an extremely active metal element, has high reaction activity, can directly react with oxygen, hydrogen, water and the like to generate combustible gas, the external leakage amount of the sodium stop valve is required to be zero; whereas conventional shut-off valves typically consist of a valve body, a bonnet, a flap, a center flange bolt, a center flange nut, and the like. Can only be applied to pipelines of conventional media such as water, gas, oil and the like, and cannot be applied to a sodium medium loop.
Disclosure of Invention
In order to solve the problems existing in the prior art, the utility model provides a nuclear-grade electric corrugated pipe sodium stop valve which can be applied to a fast neutron breeder reactor and can meet the requirements of sodium medium working conditions.
In order to realize the purpose, the utility model discloses the technical scheme who adopts is: a nuclear-grade electric sodium bellows stop valve sequentially comprises a valve body, a valve clack, a valve rod, a valve clack pressing sleeve, a bellows, a valve cover, a packing pressing sleeve, a packing pressing plate and an electric fitting from bottom to top, wherein the valve clack is arranged in the valve body in a sealing mode, the valve clack pressing sleeve is arranged between the valve clack and the valve rod, the bellows is arranged from the position of the valve rod, which is positioned on the upper portion of the valve clack, to the position where the valve body is connected with the valve cover, the valve body is connected with the valve cover through a middle flange, packing is arranged between the top of the valve cover and the valve rod, the packing is connected with the packing pressing plate through the packing pressing sleeve, the electric fitting is arranged at the top of;
the valve body is of a lengthened neck structure, so that welding seams or sealing joints are reduced, and the valve body is ensured to be sealed reliably;
furthermore, the valve body and the valve cover are designed into a double sealing structure with a wound gasket and lip welding, so that the leakage at the middle flange is zero;
furthermore, the sealing position of the valve rod is designed into a triple sealing structure of a corrugated pipe, a reverse seal and a packing seal, so that zero leakage at the packing position is ensured;
furthermore, a sodium leakage detection device is designed at the valve cover to monitor the sealing state of the corrugated pipe, once the sealing of the corrugated pipe fails, the sodium leakage detection device gives an alarm, and a nuclear power station maintenance worker knows the position of a valve with a problem at the first time, so that the nuclear power station maintenance worker can conveniently and timely handle the valve, and the operation safety of the nuclear power station is ensured;
furthermore, because the liquid metal sodium is changed from liquid state to solid state at the temperature of 97.8 ℃, in order to ensure that the sodium medium can smoothly pass through the sodium stop valve, a heat tracing structure with a preheating device and a temperature feedback device are arranged on the valve body of the sodium stop valve;
the preheating device of the heat tracing structure comprises a heating plate which is in split butt joint with the valve body in a design along with the shape, heat tracing wires which are uniformly distributed in the heating plate and a junction box which is arranged at the top outside the heating plate, wherein the positive and negative electrodes of the heat tracing wires are led out through the junction box;
the temperature feedback device is a K-type thermocouple arranged on the side wall of the heating plate below the junction box, and the preheating condition of the valve body is monitored through the thermocouple;
the heat tracing wires in the heating plate are uniformly arranged, so that the valve is uniformly heated, and the heat transfer efficiency is high;
the purpose of adopting the free-form design between the heating plate and the valve of the utility model is to ensure that the heating plate is tightly attached to the valve body, reduce the heat loss in the temperature transfer process and improve the heat transfer efficiency;
the heat tracing structure is designed into a casting structure, the heat tracing mode is that heat tracing wires are evenly distributed in the casting, the whole cast heating plate is heated when the valve is heated, and the valve is heated in the whole cast heating plate;
the utility model discloses in because the sodium medium temperature is higher (550 ℃), in order to guarantee that the temperature of conducting drive arrangement department is no longer than valve drive arrangement's normal operating temperature (below 70 ℃), the valve designs into vertical fin structure, has improved the radiating efficiency promptly, has also strengthened the bulk rigidity of valve, has improved the anti-seismic performance of complete machine.
Adopt the produced beneficial effect of technical scheme of the utility model is:
(1) the valve body adopts an integral forging structure, welding seams or sealing joints are reduced, the sealing is reliable, the structure is compact, the wall thickness is uniform, the fatigue resistance of the valve is good in the using process, and the deformation resistance is strong; the valve body and the valve cover are designed into a double sealing structure of a winding gasket and lip welding, and the leakage at the middle flange is ensured to be zero; the sealing position of the valve rod is designed into a triple sealing structure of a corrugated pipe, a reverse seal and a packing seal, so that zero leakage at the packing position is ensured; and the valve cover is provided with a sodium leakage detection device for monitoring the sealing state of the corrugated pipe, once the sealing of the corrugated pipe fails, the sodium leakage detection device gives an alarm, and the maintenance personnel of the nuclear power station know the position of the valve with the problem in the first time, so that the treatment is convenient and timely, and the operation safety of the nuclear power station is ensured.
(2) The heat dissipation efficiency of the heat dissipation structure which is vertically welded on the valve cover and is designed after temperature field and anti-seismic analysis is improved by more than 30%, and the anti-seismic performance of the valve is improved.
Drawings
FIG. 1 is a schematic diagram of a nuclear grade sodium cut-off valve with an electric bellows.
Fig. 2 is a schematic view of a heat dissipation structure of the sodium cut-off valve.
FIG. 3 is a schematic diagram of a sodium leak detection configuration.
Fig. 4 is a schematic diagram of a heat tracing structure of the valve body.
FIG. 5 is a schematic view of the connection structure of the heat tracing structure and the temperature feedback device.
Fig. 6 is a view showing the structure of the heating plate.
FIG. 7 is a structural view showing the distribution of heat tracing wires in the heating plate.
In the figure, 1, a valve body, 2, a valve clack, 3, a valve rod, 4, a corrugated pipe, 5, a valve cover, 6, a packing press plate, 7, an electric device, 8, a radiating fin, 9, a detecting device, 10, a preheating device, 11, a heating plate, 12, a heat tracing wire, 13, a junction box, 14 and a K-type thermocouple.
Detailed Description
The present invention will be described in detail with reference to the accompanying drawings.
The nuclear sodium stop valve is mainly applied to the pipelines of a first loop and a second loop of a fast neutron breeder reactor and an auxiliary system thereof, a sodium process system, a damage detection system and a thermal control system, has the function of cutting off or conveying media in the pipelines, and directly influences the safe operation of a nuclear power station if the nuclear sodium stop valve is safe and reliable.
Example 1
As shown in figures 1-3, the nuclear grade sodium cut-off valve for the electric corrugated pipe sequentially comprises a valve body 1, a valve clack 2, a valve rod 3, a valve clack pressing sleeve, a corrugated pipe 4, a valve cover 5, a packing pressing sleeve, a packing pressing plate 6 and an electric fitting 7 from bottom to top, the valve body 1 is of a lengthened neck structure, the valve clack 2 is arranged in the valve body 1 in a sealing mode, a valve clack pressing sleeve is arranged between the valve clack 2 and the valve rod 3, a corrugated pipe 4 is arranged from the position of the valve rod on the upper portion of the valve clack 2 to the position where the valve body is connected with the valve cover, the valve body 1 is connected with the valve cover 5 through a middle flange, packing is arranged between the top of the valve cover 5 and the valve rod 3, the packing is connected with a packing pressing plate 6 through a packing pressing sleeve, an electric, the valve cover 5 is provided with a heat dissipation structure which is a heat dissipation fin 8 vertically and uniformly distributed between a middle flange of the valve cover 5 and a flange for tightly clamping the packing pressing plate 6;
further, the valve body 1 and the valve cover 5 are designed into a double sealing structure with a wound gasket and lip welding, and the leakage at the middle flange is ensured to be zero;
furthermore, the sealing position of the valve rod 3 is designed into a triple sealing structure of a corrugated pipe, a reverse seal and a packing seal, so that zero leakage at the packing position is ensured;
furthermore, a sodium leakage detection device 9 is designed at the valve cover 5 to monitor the sealing state of the corrugated pipe 4, once the sealing of the corrugated pipe 4 fails, the sodium leakage detection device 9 gives an alarm, and a nuclear power station maintenance worker knows the position of a valve with a problem at the first time, so that the nuclear power station maintenance worker can conveniently and timely handle the valve and ensure the operation safety of the nuclear power station;
in the embodiment, the valve rod is controlled by the electric control device to drive the valve clack assembly to reciprocate, so that the valve is opened and closed.
Example 2
On the basis of the embodiment 1, as shown in fig. 1-7, since the liquid metal sodium is changed from liquid state to solid state at 97.8 ℃, in order to ensure that the sodium medium can pass through the sodium stop valve smoothly, the valve body 1 of the sodium stop valve is also provided with a heat tracing structure with a preheating device 10 and a temperature feedback device;
the preheating device 10 of the heat tracing structure comprises a heating plate 11 which is in split butt joint with the valve body 1 in a design following the shape, heat tracing wires 12 which are uniformly distributed in the heating plate 11 and a junction box 13 which is arranged at the outer top of the heating plate 11, wherein the positive and negative electrodes of the heat tracing wires 12 are led out through the junction box;
when the valve is used, the heat tracing wires are uniformly and fixedly arranged on the inner surface of the heating plate, and meanwhile, the heat tracing wires can be buckled and fastened with the outer wall of the valve body through the inner wall of the heating plate due to the shape following fit between the heating plate and the valve body;
the temperature feedback device is a K-type thermocouple 14 arranged on the side wall of the heating plate 11 below the junction box 13, and the preheating condition of the valve body 1 is monitored through the thermocouple 14;
the working mode is as follows: the valve body 1 is preheated by the heater, the preheating condition of the valve body 1 is monitored by the thermocouple 14, and after the specified preheating temperature is reached, the valve rod 3 is controlled by the electric device 7 to drive the valve clack assembly to reciprocate, so that the valve is opened and closed. When accidental leakage occurs to the corrugated pipe 4, the sodium leakage detection device 9 gives an alarm to inform maintenance personnel of timely maintaining.
The heat tracing structure and the temperature feedback device are designed on the valve body of the embodiment, the sodium stop valve can be reliably preheated to the required temperature, and the safe operation of the sodium stop valve is ensured, so that the safe operation of the whole nuclear power station is ensured.
Claims (8)
1. The utility model provides a nuclear level electric bellows sodium stop valve which characterized in that: from the bottom up includes valve body, valve clack, valve rod, valve clack pressure cover, bellows, valve gap, packs and presses cover, packing clamp plate, denso, and the valve clack passes through sealed mode and sets up in the valve body, is equipped with the valve clack between valve clack and the valve rod and presses the cover, and the valve rod position that is located valve clack upper portion links up the position to be equipped with the bellows with the valve gap to the valve body, through well flange joint between valve body and the valve gap, is equipped with the filler between valve gap top and the valve rod, packs to press the cover to be connected with packing clamp plate through packing, and the valve rod top is equipped with the denso, valve gap department is equipped with heat radiation structure, heat radiation structure.
2. The nuclear grade electric corrugated pipe sodium stop valve according to claim 1, characterized in that: the valve body is of a lengthened neck structure.
3. The nuclear grade electric corrugated pipe sodium stop valve according to claim 1, characterized in that: the valve body and the valve cover are designed into a double sealing structure with a wound gasket and lip welding.
4. The nuclear grade electric corrugated pipe sodium stop valve according to claim 1, characterized in that: the sealing position of the valve rod is designed into a triple sealing structure of a corrugated pipe, a reverse seal and a packing seal.
5. The nuclear grade electric corrugated pipe sodium stop valve according to claim 1, characterized in that: the valve cover is provided with a sodium leakage detection device.
6. The sodium shut-off valve for nuclear grade electric bellows according to any one of claims 1 to 5, wherein: a valve body of the sodium stop valve is provided with a heat tracing structure with a preheating device and a temperature feedback device.
7. The nuclear grade electric corrugated pipe sodium stop valve according to claim 6, characterized in that: the preheating device of the heat tracing structure comprises a heating plate which is in split butt joint with the valve body along with the design, heat tracing wires which are uniformly distributed in the heating plate and a junction box which is arranged at the top outside the heating plate, wherein the positive electrode and the negative electrode of the heat tracing wires are led out through the junction box.
8. The nuclear grade electric corrugated pipe sodium stop valve according to claim 6, characterized in that: the temperature feedback device is a K-type thermocouple arranged on the side wall of the heating plate below the junction box, and the preheating condition of the valve body is monitored through the thermocouple.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201921552877.6U CN210637513U (en) | 2019-09-18 | 2019-09-18 | Nuclear-grade electric sodium bellows stop valve |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201921552877.6U CN210637513U (en) | 2019-09-18 | 2019-09-18 | Nuclear-grade electric sodium bellows stop valve |
Publications (1)
Publication Number | Publication Date |
---|---|
CN210637513U true CN210637513U (en) | 2020-05-29 |
Family
ID=70798484
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201921552877.6U Active CN210637513U (en) | 2019-09-18 | 2019-09-18 | Nuclear-grade electric sodium bellows stop valve |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN210637513U (en) |
-
2019
- 2019-09-18 CN CN201921552877.6U patent/CN210637513U/en active Active
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN110701310A (en) | Nuclear-grade electric sodium bellows stop valve | |
WO2016115821A1 (en) | Nickel-based alloy pressure-resistant shell and implementation method thereof | |
CN111081392B (en) | Integrated solid reactor core adopting heat pipe | |
CN210637513U (en) | Nuclear-grade electric sodium bellows stop valve | |
CN208237290U (en) | The sealing element of high temperature resistant molten salt corrosion | |
CN201497365U (en) | Fast sealing cover for reduction distillation furnace air inlet | |
CN211284488U (en) | Large cover with heat-insulating heating and connecting device for titanium sponge distillation production | |
CN210135564U (en) | Boiler overheating and cooling device for power plant | |
CN208649435U (en) | A kind of big lid of reactor in titanium sponge production | |
CN206399864U (en) | A kind of circumferential x-ray flaw detector of continuous industrial orientation of work exposure | |
CN205843896U (en) | A kind of floating head heat exchanger tube head water pressure test frock | |
CN203442371U (en) | Sealing device for tests | |
CN209495001U (en) | A kind of shut-off valve | |
CN210686959U (en) | Winding gasket for pressure relief pipeline of temperature and pressure reducing device | |
CN212006853U (en) | Nuclear energy heat exchanger with pressure feedback and nuclear leakage prevention function | |
CN210442061U (en) | High-pressure stop device for hydrostatic test of coiled tube heat exchange module | |
CN208424803U (en) | A kind of vacuum cast aluminum heaters | |
CN208315211U (en) | Passive residual heat removal system for molten salt reactor | |
CN201864735U (en) | Protecting device for water inlet-outlet pipe on cooling wall | |
CN206527485U (en) | Pipe butt welding frock | |
CN213064686U (en) | Corrugated pipe stop valve for molten salt | |
CN217440819U (en) | Gate valve for molten salt device | |
CN218295678U (en) | Natural gas hydrogen production steam generation system | |
CN111139369A (en) | Large cover with heat-insulating heating and connecting device for titanium sponge distillation production | |
CN212967137U (en) | Reactor upper portion subassembly leakage monitoring pipe pressure equipment device |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
GR01 | Patent grant | ||
GR01 | Patent grant | ||
PE01 | Entry into force of the registration of the contract for pledge of patent right |
Denomination of utility model: A Nuclear Grade Electric Bellows Sodium Stop Valve Effective date of registration: 20230927 Granted publication date: 20200529 Pledgee: Dalian Branch of Shanghai Pudong Development Bank Co.,Ltd. Pledgor: DALIAN DV VALVE Co.,Ltd. Registration number: Y2023980059639 |
|
PE01 | Entry into force of the registration of the contract for pledge of patent right |