CN203338769U - Protective device for nuclear power plant reactor coolant system - Google Patents
Protective device for nuclear power plant reactor coolant system Download PDFInfo
- Publication number
- CN203338769U CN203338769U CN2013204656006U CN201320465600U CN203338769U CN 203338769 U CN203338769 U CN 203338769U CN 2013204656006 U CN2013204656006 U CN 2013204656006U CN 201320465600 U CN201320465600 U CN 201320465600U CN 203338769 U CN203338769 U CN 203338769U
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- China
- Prior art keywords
- pipeline
- reactor coolant
- tank
- peace
- pressure
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- 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.)
- Expired - Fee Related
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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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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The utility model discloses a protective device for a nuclear power plant reactor coolant system. The protective device is connected with the reactor coolant system which is formed by connecting a pressure vessel, a pressure stabilizer and a steam generator through pipelines. The protective device for the nuclear power plant reactor coolant system comprises an injection tank, wherein one end of the injection tank is connected with the upstream of the pressure vessel through a first pipeline, a first separation valve and a check valve, the first separation valve and the check valve are connected to the first pipeline in series, an adjustment valve is arranged at the other end of the injection tank, the injection tank is further provided with a second pipeline connected with the first pipeline in parallel, one end of the second pipeline is connected to the position, between the check valve and the reactor coolant system, of the first pipeline, the other end of the second pipeline is connected to the position, between the injection tank and the first separation valve, of the first pipeline, and the second pipeline is provided with two or more second separation valves connected in series.
Description
Technical field
The utility model belongs to the nuclear power technology field, and more particularly, the utility model relates to a kind of protective device of nuclear power plant reactor coolant system.
Background technology
Pressurized-water reactor nuclear power plant opens in the heap process, need to carry out the water-filling exhaust to reactor coolant loop, and after the non-condensable gas emptying of question response reactor coolant system, reactor coolant loop enters the real state of watertight.In reactor shutdown process, when the voltage stabilizer Hou，Yi loop, vapour chamber of going out enters the real state of watertight.
Under the real state of watertight, the pressure of reactor coolant loop is controlled by chemical volume control system.The compressibility coefficient of reactor coolant is less, it is more difficult that pressure is controlled, therefore in the disturbance situation, if filling letdown flow on chemical volume control system does not mate, can cause the pressure of reactor coolant loop significantly to change: under the real state of watertight, after the charging stream amount of chemical volume control system is greater than letdown flow, will cause the pressure of reactor coolant loop to rise rapidly; When the charging stream amount of chemical volume control system is less than letdown flow, will cause the pressure of reactor coolant loop to descend rapidly.The pressure surge meeting increases the times of fatigue that the major equipment of reactor coolant loop stands, and the integrality of the pressure boundary of reactor coolant loop is caused to negative effect.
During existing unit starting or shutdown, will inevitably experience the water at low temperature dense state, reactor coolant loop is all water, without the coercible gas space.Now, the pressure that peace is annotated tank is higher, be connected to reactor coolant loop if will pacify the notes tank under the water at low temperature dense state, can cause the superpressure under reactor coolant loop water at low temperature dense state, superpressure may affect the integrality (generation brittle fracture) of reactor pressure vessel.Therefore, in shutdown and opening the heap process, when the pressure of reactor coolant loop, during lower than certain certain value, peace need be annotated to tank and be isolated.
Can control the pressure of reactor coolant loop under the water at low temperature dense state by chemical volume control system, but, the compressibility of water is lower, if the therefore flow generation disturbance of chemical volume control system, larger fluctuation can occur in the pressure of reactor coolant loop, and there is to negative impact the pressure boundary of reactor coolant loop.
Can also be to nitrogen injection in the voltage stabilizer of reactor coolant loop, form nitrogen cushion, make voltage stabilizer form the nitrogen stabilization pressure device, avoid the running status that reactor coolant loop can be not closely knit in water at low temperature.Although utilize in voltage stabilizer and to inject non-condensable gas nitrogen and can avoid reactor coolant loop to enter the water at low temperature dense state,, can increase waste gas and the wastewater flow rate of nuclear power station.
In view of this, the necessary protective device that a kind of nuclear power plant reactor coolant system is provided, it can control the pressure of reactor coolant loop easily, and realizes the protection to reactor coolant loop.
Summary of the invention
The purpose of this utility model is: a kind of protective device of nuclear power plant reactor coolant system is provided, and it is easier that it can make the pressure of reactor coolant loop control, to realize the protection to reactor coolant loop.
In order to realize the foregoing invention purpose, the utility model provides a kind of protective device of nuclear power plant reactor coolant system, be connected in pressure vessel, on the reactor coolant loop that voltage stabilizer and steam generator are connected to form by pipeline, it comprises peace notes tank, peace is annotated an end of tank by the first pipeline, series connection is arranged at the upstream that the first isolation valve on the first pipeline and check (non-return) valve are connected in pressure vessel, the other end that peace is annotated tank is provided with variable valve, peace is annotated tank and also is provided with the second pipeline be arranged in parallel with the first pipeline, one end of the second pipeline is connected on the first pipeline between check (non-return) valve and reactor coolant loop, the other end is connected to peace and annotates on the first pipeline between tank and the first isolation valve, and the second pipeline is provided with the second isolation valve.
As a kind of improvement of the protective device of the utility model nuclear power plant reactor coolant system, described the second pipeline is provided with the second isolation valve of 2 or a plurality of series connection.
The protective device of the utility model nuclear power plant reactor coolant system can guarantee in reactor coolant loop to exist all the time gas-liquid two-phase, when the charging stream amount of chemical volume control system is greater than letdown flow, the pressure of reactor coolant loop raises, reactor coolant enters peace by pipeline and annotates tank, further alleviates the pressure rise of reactor coolant loop; When the charging stream amount of chemical volume control system is less than letdown flow, the pressure drop of reactor coolant loop, the fluid that peace is annotated in tank enters reactor coolant loop, alleviates the pressure drop of reactor coolant loop.So, can reduce the pressure surge of reactor coolant loop, realize the protection to reactor coolant loop.
The accompanying drawing explanation
Below in conjunction with the drawings and specific embodiments, the protective device of the utility model nuclear power plant reactor coolant system is elaborated, in accompanying drawing:
The schematic diagram of the protective device that Fig. 1 is the utility model nuclear power plant reactor coolant system.
Embodiment
In order to make goal of the invention of the present utility model, technical scheme and technique effect thereof more clear, below in conjunction with the drawings and specific embodiments, the utility model is further described.Should be understood that, the embodiment of describing in this instructions is only in order to explain the utility model, not in order to limit the utility model.
Please refer to shown in Fig. 1; the protective device of the utility model nuclear power plant reactor coolant system; be connected on the reactor coolant loop that pressure vessel 10, voltage stabilizer 20 and steam generator 30 be connected to form by pipeline; wherein; the upstream line of pressure vessel 10 is provided with peace and annotates tank 40; the end that peace is annotated tank 40 is arranged at by the first pipeline, series connection the upstream that the first isolation valve 50 on the first pipeline and check (non-return) valve 60 are connected in pressure vessel 10, and the other end that peace is annotated tank 40 is provided with variable valve 70.
The first isolation valve 50 and check (non-return) valve 60 arranged on the first pipeline and the first pipeline, peace is annotated tank 40 and also is provided with the second pipeline be arranged in parallel with the first pipeline, one end of the second pipeline is connected on the first pipeline between check (non-return) valve 60 and reactor coolant loop, the other end is connected to peace and annotates on the first pipeline between tank 40 and the first isolation valve 50, and the second pipeline is provided with the second isolation valve 80 of 2 or a plurality of series connection.
Shown in Fig. 1, describe the protective device of the utility model nuclear power plant reactor coolant system in detail:
At power of the assembling unit run duration, two the second isolation valves 80 on the second pipeline are in closed condition, and the first isolation valve 50 on the first pipeline is in opening, and variable valve 70 is in closed condition.
During the unit shutdown, the pressure of reactor coolant loop reduces gradually.The first isolation valve 60 that to pacify to a certain extent the time on the first pipeline of annotating tank 40 downstreams when its pressure decreased cuts out, open variable valve 70, discharge peace and annotate the nitrogen in tank 40, make peace annotate the pressure decreased of tank 40 to setting (setting is higher than the minimum permission operating pressure of reactor coolant pump).Annotate the pressure of tank 40 when identical when the pressure of reactor coolant loop and peace, the second isolation valve 80 on the second pipeline is opened, make peace annotate tank 40 and be connected with reactor coolant loop, now, the voltage stabilizer 20 of reactor coolant loop is vapour-liquid two-phase state.When the further decrease temperature and pressure of reactor coolant loop, voltage stabilizer 20 goes out behind the vapour chamber, and peace is annotated the function that tank 40 is born the nitrogen stabilization pressure device, can alleviate the pressure surge of reactor coolant loop.
Before unit starting, the water that peace is annotated in tank 40 keeps certain water level, it is nitrogen that peace is annotated tank 40 tops, bottom is BAS, and now, the nitrogen pressure in peace notes tank 40 is identical with the pressure of the atmosphere in containment, the first isolation valve 50 on the first pipeline be connected with peace notes tank 40 cuts out, variable valve 70 cuts out, and the second isolation valve 80 on the second pipeline is opened, and chemical volume control system is to the reactor coolant loop moisturizing.When the charging stream amount of chemical volume control system is greater than letdown flow, a part of cooling medium enters peace by associated line and annotates tank 40, makes nitrogen compressed, makes pressure rise more mild of reactor coolant loop.When the charging stream amount of chemical volume control system is less than letdown flow, peace is annotated tank 40 mesoboric acid solution and enter reactor coolant loop under the pressure of nitrogen, further stops decline more mild of reactor coolant loop pressure.
When the pressure in reactor coolant loop is annotated the pressure in tank 40 higher than peace, the pipeline that cooling medium is annotated tank 40 downstreams by peace enters in peace notes tank 40, and the pressure that peace is annotated tank 40 also increases.When the pressure of reactor coolant loop after minimum permission starting pressure, starts reactor coolant pump higher than reactor coolant pump, voltage stabilizer 20 is set up the vapour chamber.After voltage stabilizer vapour chamber is set up, two the second isolation valves 80 on the second pipeline cut out, peace is annotated to tank 40 carries out nitrogen pressure and water level is regulated, when pressure and water level within the limits prescribed after, the first isolation valve 50 on the first pipeline is opened.
In conjunction with the above detailed description to the utility model embodiment, can find out; with respect to prior art; the protective device of the utility model nuclear power plant reactor coolant system has following useful technique effect: in shutdown and opening the heap process; can make peace annotate tank 40 and be connected with reactor coolant loop, the nitrogen that peace is annotated in tank 40 provides the buck mitigation capability for reactor coolant loop.So; can make reactor coolant loop can not experience the water at low temperature dense state at normal operating phase; there is all the time the gas-liquid two-phase state in reactor coolant loop under low temperature condition; therefore better control the pressure of reactor coolant loop; reduce the pressure surge of reactor coolant loop, realize the protection to reactor coolant loop.
Be understandable that; according to other embodiments of the present utility model; also can not adopt the second isolation valve 80 of two series connection that arrange on the second pipeline and the second pipeline; but the reverse checkvalve 60 on the first pipeline is redesigned; make and can manually force reverse checkvalve 60 to open; so, also can realize the purpose of protective reaction reactor coolant system.
The announcement of book and instruction according to the above description, the utility model those skilled in the art can also carry out suitable change and modification to above-mentioned embodiment.Therefore, the utility model is not limited to embodiment disclosed and described above, to modifications and changes more of the present utility model, also should fall in the protection domain of claim of the present utility model.In addition, although used some specific terms in this instructions, these terms just for convenience of description, do not form any restriction to the utility model.
Claims (2)
1. the protective device of a nuclear power plant reactor coolant system, be connected in pressure vessel, on the reactor coolant loop that voltage stabilizer and steam generator are connected to form by pipeline, it is characterized in that: described protective device comprises peace notes tank, peace is annotated an end of tank by the first pipeline, series connection is arranged at the upstream that the first isolation valve on the first pipeline and check (non-return) valve are connected in pressure vessel, the other end that peace is annotated tank is provided with variable valve, peace is annotated tank and also is provided with the second pipeline be arranged in parallel with the first pipeline, one end of the second pipeline is connected on the first pipeline between check (non-return) valve and reactor coolant loop, the other end is connected to peace and annotates on the first pipeline between tank and the first isolation valve, and the second pipeline is provided with the second isolation valve.
2. the protective device of nuclear power plant reactor coolant system according to claim 1 is characterized in that: described the second pipeline is provided with the second isolation valve of 2 or a plurality of series connection.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013204656006U CN203338769U (en) | 2013-07-31 | 2013-07-31 | Protective device for nuclear power plant reactor coolant system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013204656006U CN203338769U (en) | 2013-07-31 | 2013-07-31 | Protective device for nuclear power plant reactor coolant system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203338769U true CN203338769U (en) | 2013-12-11 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2013204656006U Expired - Fee Related CN203338769U (en) | 2013-07-31 | 2013-07-31 | Protective device for nuclear power plant reactor coolant system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN203338769U (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
| CN109300556A (en) * | 2018-09-19 | 2019-02-01 | 中广核研究院有限公司 | A kind of reactor voltage-stabilizing system having peace pouring functions |
| CN109473185A (en) * | 2018-11-13 | 2019-03-15 | 中国核动力研究设计院 | A kind of test device and its test method of robotics reactor shut-off system |
| CN111584109A (en) * | 2020-04-26 | 2020-08-25 | 岭东核电有限公司 | Cavity building control method and device for voltage stabilizer of nuclear power unit |
-
2013
- 2013-07-31 CN CN2013204656006U patent/CN203338769U/en not_active Expired - Fee Related
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
| CN109300556A (en) * | 2018-09-19 | 2019-02-01 | 中广核研究院有限公司 | A kind of reactor voltage-stabilizing system having peace pouring functions |
| CN109473185A (en) * | 2018-11-13 | 2019-03-15 | 中国核动力研究设计院 | A kind of test device and its test method of robotics reactor shut-off system |
| CN111584109A (en) * | 2020-04-26 | 2020-08-25 | 岭东核电有限公司 | Cavity building control method and device for voltage stabilizer of nuclear power unit |
| CN111584109B (en) * | 2020-04-26 | 2022-05-24 | 岭东核电有限公司 | Cavity building control method and device for voltage stabilizer of nuclear power unit |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20131211 |