CN111899900A - Nuclear power voltage stabilizer seal head - Google Patents
Nuclear power voltage stabilizer seal head Download PDFInfo
- Publication number
- CN111899900A CN111899900A CN202010782876.1A CN202010782876A CN111899900A CN 111899900 A CN111899900 A CN 111899900A CN 202010782876 A CN202010782876 A CN 202010782876A CN 111899900 A CN111899900 A CN 111899900A
- Authority
- CN
- China
- Prior art keywords
- shrouding
- inlayer
- nuclear power
- voltage stabilizer
- pressure
- 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.)
- Pending
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/028—Seals, e.g. for pressure vessels or containment vessels
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/06—Sealing-plugs
- G21C13/073—Closures for reactor-vessels, e.g. rotatable
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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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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/112—Measuring temperature
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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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides a voltage stabilizer end socket for nuclear power, and mainly relates to the field of pressure equipment. Stabiliser head for nuclear power, including outer shrouding and inlayer shrouding, outer shrouding all is the spherical crown shape with the inlayer shrouding, outer shrouding and inlayer shrouding welding, be the cushion chamber between outer shrouding and the inlayer shrouding, set up outer hole and the outer hole seat of maintaining of spraying on the outer shrouding, set up on the inlayer shrouding and spray the corresponding inlayer of hole and spray the hole, with the corresponding inlayer hole seat of maintaining of outer hole seat. The invention has the beneficial effects that: the invention can perform two-way protection when the seal head of the voltage stabilizer leaks, thereby increasing the safety performance of the nuclear power voltage stabilizer.
Description
Technical Field
The invention mainly relates to the field of pressure equipment, in particular to a voltage stabilizer end socket for nuclear power.
Background
There are approximately 440 nuclear power plants operating worldwide, the vast majority of which are Light Water Reactors (LWR), which are mainly of the two types of Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR), of which approximately 75% are pressurized water reactors. A pressure stabilizer, also called a pressure balancer, in a pressurized water reactor nuclear power plant is equipment for controlling the pressure change of a reactor.
The stabiliser acts to stabilise and maintain pressure during normal operation, and in the event of an accident the stabiliser provides over-pressure protection for the entire circuit, so the stabiliser is a high pressure vessel. The end socket of the steam space of the voltage stabilizer is communicated with a sprayer connecting pipe and a maintenance hole seat for installing a maintenance hole component. In the process of high-voltage operation of the voltage stabilizer, the end socket has potential safety hazard of high-voltage leakage, wherein the sprayer connecting pipe and the maintenance hole seat are key pressure relief monitoring objects. Once the nuclear power voltage stabilizer leaks, the consequences are not considered.
Disclosure of Invention
In order to solve the defects of the prior art, the invention provides the end socket of the voltage stabilizer for nuclear power, which has a buffering function.
In order to achieve the purpose, the invention is realized by the following technical scheme:
stabiliser head for nuclear power, including outer shrouding and inlayer shrouding, outer shrouding all is the spherical crown shape with the inlayer shrouding, outer shrouding and inlayer shrouding welding, be the cushion chamber between outer shrouding and the inlayer shrouding, set up outer hole and the outer hole seat of maintaining of spraying on the outer shrouding, set up on the inlayer shrouding and spray the corresponding inlayer of hole and spray the hole, with the corresponding inlayer hole seat of maintaining of outer hole seat.
The voltage stabilizer end socket for the nuclear power further comprises a welding piece, the welding piece is in a circular ring shape, the bottom of the inner layer sealing plate is provided with a skirt edge, the skirt edge is welded with the inner ring of the welding piece, and the outer layer sealing plate is welded with the top of the welding piece.
And a pressure detection unit and a temperature detection unit are arranged in the buffer cavity.
The spherical crown radius of the outer sealing plate is 2/3-3/4 of the spherical crown radius of the inner sealing plate.
And a pressure object is introduced into the buffer cavity.
The pressure object is high-pressure air and/or high-pressure water.
The pressure in the buffer cavity is 1/4-1/2 of the conventional pressure in the voltage stabilizer.
Compared with the prior art, the invention has the beneficial effects that:
the outer sealing plate and the inner sealing plate are combined to form the double-layer voltage stabilizer end socket, so that double-layer protection is provided for the voltage stabilizer. After the inner layer shrouding appeared leaking the condition, the buffer chamber between two shroudings was connected with the stabiliser inner chamber promptly and is become a whole, and outer shrouding continues to form an inclosed space with the stabiliser to carry out pressure control to whole return circuit. The detection element is installed in the buffer cavity of the device, and when abnormal changes of pressure are detected, an operator can perform corresponding treatment to prevent safety accidents. Through the double-layer sealing plate arrangement, secondary protection can be carried out when the seal head of the voltage stabilizer leaks, buffer space and time in an emergency state are provided for the voltage stabilizer, and therefore the safety performance of the nuclear power voltage stabilizer is improved.
Drawings
FIG. 1 is a schematic cross-sectional structural view of the present invention;
FIG. 2 is a schematic structural diagram of the present invention.
Reference numerals shown in the drawings: 1. an outer layer sealing plate; 2. an inner layer sealing plate; 3. a buffer chamber; 4. outer layer spray holes; 5. an outer layer maintenance hole seat; 6. inner layer spray holes; 7. an inner layer maintenance hole seat; 8. a welding part; 21. a skirt edge; 31. a pressure detection unit; 32. a temperature detection unit.
Detailed Description
The invention is further described with reference to the accompanying drawings and specific embodiments. It should be understood that these examples are for illustrative purposes only and are not intended to limit the scope of the present invention. Further, it should be understood that various changes or modifications of the present invention may be made by those skilled in the art after reading the teaching of the present invention, and these equivalents also fall within the scope of the present application.
As shown in fig. 1-2, the end socket of the voltage stabilizer for nuclear power of the present invention comprises an outer layer sealing plate 1 and an inner layer sealing plate 2, wherein the outer layer sealing plate 1 and the inner layer sealing plate 2 are both in a spherical crown shape, the outer layer sealing plate 1 and the inner layer sealing plate 2 are welded, and a buffer cavity 3 is formed between the outer layer sealing plate 1 and the inner layer sealing plate 2 after welding. This head and stabiliser jar body welding back, inlayer shrouding are as direct pressure-bearing shrouding, and outer shrouding is the second way protection means of stabiliser, and the buffer chamber between outer shrouding and the inlayer shrouding is as the buffer space when the inlayer shrouding is damaged, can strive for sufficient time and space buffering after leaking for the inlayer shrouding is damaged, and then handles for operating personnel provides sufficient reaction time, prevents the emergence of major incident. The outer shrouding 1 is last to offer outer spraying hole 4 and outer maintenance hole seat 5, offer on the inlayer shrouding 2 with outer spraying hole 4 corresponding inlayer spray hole 6, with outer maintenance hole seat 5 corresponding inlayer maintenance hole seat 7. The spray pipe is arranged in the voltage stabilizer after passing through the outer layer spray hole 4 and the inner layer spray hole 6, and the outer layer maintenance hole seat 5 and the inner layer maintenance hole seat 7 are correspondingly formed into a channel for internal maintenance and overhaul. The inner layer spraying hole and the inner layer maintenance hole seat of the device are key monitoring positions for pressure leakage. And a pressure detection unit 31 and a temperature detection unit 32 are arranged in the buffer cavity 3, wherein the pressure detection unit adopts a pressure sensor, the temperature monitoring unit adopts a temperature sensor, and the two sensors are in signal connection with a nuclear power master controller, so that the pressure and temperature change in the buffer cavity is detected. Once the temperature and pressure in the buffer chamber are abnormally changed, the controller gives an alarm to perform emergency treatment by an operator or a system.
Further, the welding piece 8 is circular, the skirt 21 is integrally formed at the bottom of the inner layer sealing plate 2, the skirt 21 is welded with the inner ring of the welding piece 8, and the outer layer sealing plate 1 is welded with the top of the welding piece 8. As the connection media of inlayer shrouding and outer shrouding through the welding, can make inlayer shrouding and outer shrouding carry out stable sealing connection, the welding is used for welding with the stabiliser main part simultaneously, can realize the stable connection of stabiliser head and stabiliser cylinder.
Furthermore, the spherical crown radius of the outer sealing plate 1 is 2/3-3/4 of the spherical crown radius of the inner sealing plate 2, so that the space of the buffer cavity is ensured, and the buffer cavity has a sufficient buffer effect.
Further, a pressure object is introduced into the buffer cavity 3. The pressure in the buffer cavity can cause a buffer environment, so that the relative pressure difference between the two sides of the inner layer sealing plate is reduced, namely the pressure of the inner layer sealing plate is relieved by utilizing the outer layer sealing plate, the service life of the inner layer sealing plate is prolonged, and the use safety of the device is improved.
Further, the pressure object is high-pressure air and/or high-pressure water. The pressurizing mode of mixing high-pressure water and high-pressure air is preferred, so that the pressure change of the buffer cavity caused by temperature change can be reduced as far as possible on the premise of ensuring the pressure. When the machine needs to be stopped for maintenance, high-pressure gas and liquid in the buffer cavity need to be discharged firstly.
Furthermore, the pressure in the buffer cavity 3 is 1/4-1/2 of the conventional pressure in the pressure stabilizer, so that the pressure difference between two sides of the inner layer sealing plate is relatively small, and the use safety of the inner layer sealing plate is guaranteed.
Claims (7)
1. Stabiliser head for nuclear power, including outer shrouding (1) and inlayer shrouding (2), its characterized in that: outer shrouding (1) all is the spherical crown shape with inlayer shrouding (2), outer shrouding (1) and inlayer shrouding (2) welding, be cushion chamber (3) between outer shrouding (1) and inlayer shrouding (2), set up on outer shrouding (1) and outer hole (4) and outer maintenance hole seat (5) spray, set up on inlayer shrouding (2) and spray the corresponding inlayer in hole (4) and spray hole (6), with outer maintenance hole seat (5) corresponding inlayer maintenance hole seat (7).
2. The voltage stabilizer head for nuclear power according to claim 1, further comprising a weldment (8), characterized in that: the welding piece (8) is in a circular ring shape, the bottom of the inner layer sealing plate (2) is provided with a skirt edge (21), the skirt edge (21) is welded with the inner ring of the welding piece (8), and the outer layer sealing plate (1) is welded with the top of the welding piece (8).
3. The voltage stabilizer head for nuclear power according to claim 1, further comprising a weldment (8), characterized in that: a pressure detection unit (31) and a temperature detection unit (32) are arranged in the buffer cavity (3).
4. The voltage stabilizer head for nuclear power according to claim 1, further comprising a weldment (8), characterized in that: the spherical crown radius of the outer sealing plate (1) is 2/3-3/4 of the spherical crown radius of the inner sealing plate (2).
5. The voltage stabilizer head for nuclear power according to any one of claims 1-4, further comprising a weldment (8), characterized in that: and a pressure object is introduced into the buffer cavity (3).
6. The end socket of the voltage stabilizer for nuclear power of claim 5, characterized in that: the pressure object is high-pressure air and/or high-pressure water.
7. The voltage stabilizer head for nuclear power according to claim 5, further comprising a weldment (8), characterized in that: the pressure in the buffer cavity (3) is 1/4-1/2 of the conventional pressure in the voltage stabilizer.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
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CN202010782876.1A CN111899900A (en) | 2020-08-06 | 2020-08-06 | Nuclear power voltage stabilizer seal head |
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CN202010782876.1A CN111899900A (en) | 2020-08-06 | 2020-08-06 | Nuclear power voltage stabilizer seal head |
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CN111899900A true CN111899900A (en) | 2020-11-06 |
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CN202010782876.1A Pending CN111899900A (en) | 2020-08-06 | 2020-08-06 | Nuclear power voltage stabilizer seal head |
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Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN201462306U (en) * | 2009-07-28 | 2010-05-12 | 石家庄巨力科技有限公司 | High temperature resistant anti-explosion auto-alarm corrugated compensator capable of being monitored |
CN203465067U (en) * | 2013-09-11 | 2014-03-05 | 南京晨光东螺波纹管有限公司 | Device for monitoring pressure between two layers of corrugated pipes or two layers of container shells |
CN104464841A (en) * | 2014-12-16 | 2015-03-25 | 中国核动力研究设计院 | Thermal insulation plate for built-in steam pressurizer of pressurized water reactor and integrated pressurized water reactor formed by thermal insulation plate |
CN106328216A (en) * | 2016-08-30 | 2017-01-11 | 中广核工程有限公司 | Water seal device for nuclear power plant voltage stabilizer and nuclear power plant voltage stabilizer |
CN206075829U (en) * | 2016-09-27 | 2017-04-05 | 上海新闵(东台)重型锻造有限公司 | Pressurized-water reactor nuclear power plant end socket of voltage regulator |
CN106887261A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | A kind of integrated module formula presurized water reactor of 69 reactor core |
US20180178940A1 (en) * | 2015-05-28 | 2018-06-28 | Kyoraku Co., Ltd. | Double container |
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2020
- 2020-08-06 CN CN202010782876.1A patent/CN111899900A/en active Pending
Patent Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN201462306U (en) * | 2009-07-28 | 2010-05-12 | 石家庄巨力科技有限公司 | High temperature resistant anti-explosion auto-alarm corrugated compensator capable of being monitored |
CN203465067U (en) * | 2013-09-11 | 2014-03-05 | 南京晨光东螺波纹管有限公司 | Device for monitoring pressure between two layers of corrugated pipes or two layers of container shells |
CN104464841A (en) * | 2014-12-16 | 2015-03-25 | 中国核动力研究设计院 | Thermal insulation plate for built-in steam pressurizer of pressurized water reactor and integrated pressurized water reactor formed by thermal insulation plate |
US20180178940A1 (en) * | 2015-05-28 | 2018-06-28 | Kyoraku Co., Ltd. | Double container |
CN106887261A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | A kind of integrated module formula presurized water reactor of 69 reactor core |
CN106328216A (en) * | 2016-08-30 | 2017-01-11 | 中广核工程有限公司 | Water seal device for nuclear power plant voltage stabilizer and nuclear power plant voltage stabilizer |
CN206075829U (en) * | 2016-09-27 | 2017-04-05 | 上海新闵(东台)重型锻造有限公司 | Pressurized-water reactor nuclear power plant end socket of voltage regulator |
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Application publication date: 20201106 |
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