CN106297915B - Passive safety injection system for nuclear power station - Google Patents
Passive safety injection system for nuclear power station Download PDFInfo
- Publication number
- CN106297915B CN106297915B CN201510238671.6A CN201510238671A CN106297915B CN 106297915 B CN106297915 B CN 106297915B CN 201510238671 A CN201510238671 A CN 201510238671A CN 106297915 B CN106297915 B CN 106297915B
- Authority
- CN
- China
- Prior art keywords
- steam
- injection
- secondary side
- pipe
- passive safety
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention relates to a passive safety injection system for a nuclear power station, which comprises a reservoir in a containment, a water supply pipe, a water supply isolation valve, a passive safety injection turbine pump, a pressure release valve on the secondary side of an evaporator, a steam discharge pipe, an injection pipe, cooling water and a safety injection isolation valve. When the liquid level of the secondary side of the steam generator is reduced to a low liquid level, reliable passive water replenishing is carried out on the secondary side of the steam generator, so that the secondary side of the steam generator continuously carries out the waste heat of the reactor core.
Description
Technical Field
The invention relates to a passive safety injection system, in particular to a passive safety injection system for a nuclear power station.
Background
Safe nuclear power is clean energy with high energy density, and plays an important role in protecting ecological environment, adjusting energy structure and guaranteeing energy safety. However, once a safety problem occurs in the nuclear power plant, a great threat is brought to workers, surrounding residents, the ecological environment and the like. Therefore, the safety problem of the nuclear power station is a problem which needs to be considered when people apply nuclear power. At present, nuclear power plants tend to adopt passive safety technology to deal with accidents. The passive safety technology is to utilize natural force to complete various cooling functions in case of accident, wherein the natural force can be generated by gravity, pressure of accumulated gas, driving force generated by natural circulation and the like without a pump or an external power supply. Therefore, the safety reliability of the nuclear power plant is improved, and meanwhile, the safety system of the nuclear power plant is greatly simplified.
The nuclear power plant in the prior art comprises a main loop system and a reactor core emergency cooling system communicated with the main loop system, wherein the reactor core emergency cooling system is used for taking away reactor core waste heat generated by the residual fission of a reactor core in the main loop system when an accident occurs.
Fig. 1 shows a main circuit system of a current passive nuclear power plant. As shown in fig. 1, a main loop system of a current passive nuclear power station includes a steam generator 6, a U-shaped tube 5, a main loop system cold section 3, a main loop system hot section 4, a main pump 9, a reactor pressure vessel 2, a reactor core 1 located in the reactor pressure vessel 2, a surge tube 10 and a pressurizer 11, wherein the U-shaped tube 5 is disposed in the steam generator 6, an outlet end of the U-shaped tube is collected to a cold chamber compartment 7 at the bottom of the steam generator, the cold chamber compartment 7 is communicated with the main loop system cold section 3 through the main pump 9, the main loop system cold section 3 is communicated with the reactor pressure vessel 2, the reactor pressure vessel 2 is further communicated with the main loop system hot section 4, the main loop system hot section 4 is communicated with the pressurizer 11 through the surge tube 10 and is communicated with an inlet end of the U-shaped tube 5 through a hot chamber compartment 8 at the bottom of the steam generator, a coolant enters the reactor pressure vessel 2 through the main loop system cold section 3, to the inlet of the reactor core 1, the nuclear reaction energy generated by the reactor core is taken away when flowing through the reactor core 1, the heated coolant (e.g. at a temperature of about 321 ℃) flows through the hot section 4 of the primary loop system, to the hot compartment 8 at the bottom of the steam generator and enters the inlet end of the U-tubes 5, the heat is transferred to the coolant inside the steam generator 6 and outside the U-tubes 5 through the U-tubes 5, the coolant temperature inside the U-tubes 5 is reduced (e.g. coolant temperature of 280 ℃) and converges to the cold compartment 7 at the bottom of the steam generator through the outlet end of the U-tubes, and the coolant inside the cold compartment 7 is pumped into the cold section 3 of the primary loop system through the primary pump 9 and returns to the reactor pressure vessel 2 again, forming a closed cooling cycle of the primary loop system. In fig. 1, arrow F1 indicates a lower temperature coolant flow, and arrow F2 indicates a higher temperature coolant flow.
In order to stabilize the pressure of the main loop system, the hot section 4 of the main loop system is communicated with a pressure stabilizer 11 through a surge pipe 10, and saturated liquid and saturated steam (for example, saturated liquid and saturated steam of cooling water) are contained in the pressure stabilizer 11, so that the pressure stabilizing requirement of the main loop system is met. The pressurizer 11 is used to maintain the pressure of the primary loop system at a high pressure for normal operation (e.g., about 15.5 MPa) so that the coolant in the reactor pressure vessel 2 does not boil during reaction of the reactor core 1 under normal operating conditions. When the cooling water heated by the reactor core 1 flows through the U-shaped pipe 5, heat is transferred to the cooling water in the steam generator 6 and outside the U-shaped pipe 5, so that the cooling water in the steam generator 6 is evaporated to form steam, the steam in the steam generator 6 is conveyed to a steam wheel pump (not shown in fig. 1) through a main steam isolation valve 13 which is normally open through a main steam pipeline 12, the steam wheel pump is driven to generate electricity, and the heat generated by the reactor core is converted into electric energy.
In the case of a complete power failure in a nuclear power plant, because the main steam isolation valve 13 is closed, steam generated by evaporation of saturated water in the secondary side of the steam generator (the space inside the steam generator 6 and outside the U-shaped tube 5) cannot be delivered to a steam turbine pump (not shown in fig. 1), and the secondary side of the steam generator cannot take away reactor core waste heat generated by residual fission of the reactor core by using a normal working mode. At this moment, the passive nuclear power station firstly depends on the natural circulation of the main loop system, transmit a part of reactor core waste heat to the secondary side of the steam generator through the U-shaped heat transfer pipe in the steam generator, make the saturated cooling water in the secondary side of the steam generator continuously absorb heat and evaporate, lead to the rise of the pressure in the secondary side of the steam generator, when the pressure rises to the opening pressure set by the secondary side pressure relief valve of the steam generator (such as 7.8 MPa), the pressure relief valve of the secondary side of the steam generator is opened, to the high-pressure steam discharged in the containment, give the pressure relief of the secondary side of the steam generator, when the pressure drops to the closing pressure set by the secondary side pressure relief valve of the steam generator (such as 7. After the secondary side pressure release valve of the steam generator is closed, the secondary side of the steam generator absorbs the internal pressure of the reactor core waste heat due to continuous heat exchange of the U-shaped pipe, the secondary side pressure release valve of the steam generator is opened and closed in a reciprocating mode, steam is discharged until the liquid level of the secondary side of the steam generator is reduced to the low liquid level set by the secondary side of the steam generator. At this time, if the reactor core waste heat cannot be taken away continuously, an accident will occur.
Therefore, it is necessary to provide a passive safety injection system for a nuclear power station, which performs reliable passive water replenishment when the liquid level of the secondary side of the steam generator is reduced to a low liquid level, so that the secondary side of the steam generator continuously carries out the reactor core waste heat, the risk of the reactor core being exposed is reduced, the response time after an accident is prolonged, and the safety margin of the nuclear power station is improved.
Disclosure of Invention
The invention aims to provide a passive safety injection system for a nuclear power station, which can continuously supplement water to the secondary side of an evaporator in a passive mode under the condition that the nuclear power station is completely powered off, so that the secondary side of a steam generator continuously carries out reactor core waste heat, and accidents are avoided.
One embodiment of the invention provides a passive safety injection system for a nuclear power station, a main loop system of the nuclear power station comprises a steam generator and a U-shaped pipe which are arranged in a containment vessel, the passive safety injection system for the nuclear power station comprises an in-containment reservoir, a water supply pipe, a water supply isolation valve, a passive safety injection turbine pump, a pressure release valve on the secondary side of an evaporator, a steam discharge pipe, an injection pipe, cooling water and a safety injection isolation valve, wherein the bottom of the in-containment reservoir is higher than the top of a U-shaped pipe, the cooling water is stored in the in-containment reservoir, the in-containment reservoir is communicated with the passive safety injection turbine pump through the water supply pipe and the water supply isolation valve arranged on the water supply pipe, and the passive safety injection turbine pump is communicated with the secondary side of the evaporator through the steam discharge pipe and the pressure release valve on the secondary side of the evaporator arranged on the steam discharge pipe and is communicated with the secondary side of the evaporator through the injection pipe and the safety injection isolation valve arranged on the injection pipe.
According to the passive safety injection system for the nuclear power station provided by the embodiment of the invention, when an accident occurs, the pressure of the secondary side of the steam generator rises, the pressure relief valve on the secondary side of the evaporator is opened, steam is discharged through the steam discharge pipe, and the discharged steam takes away decay heat of the reactor core; the discharged steam is led into a passive safety steam injection turbine pump to push the passive safety steam injection turbine pump, the passive safety steam injection turbine pump pumps cooling water in a water storage tank in the containment to the secondary side of the steam generator for water supplement through a water supply pipe and a water supply isolation valve arranged on the water supply pipe and through the safety pipe and the safety steam injection isolation valve arranged on the safety pipe, the secondary side of the steam generator is continuously supplemented with the cooling water, and the U-shaped pipe is kept submerged; at the moment, the hot water on the primary side in the U-shaped pipe is cooled, the cooling water on the secondary side of the steam generator is heated to be saturated and generates steam, the generated steam is discharged by the pressure release valve on the secondary side of the steam generator, the discharged steam is guided into the passive safety steam injection turbine pump to push the passive safety steam injection turbine pump, and the passive safety steam injection turbine pump continuously supplements the cooling water in the water storage tank in the containment to the steam generator.
According to one embodiment of the invention, the passive safety injection system for the nuclear power plant is provided, wherein the nuclear power plant comprises a main loop system and a reactor core emergency cooling system communicated with the main loop system, and the reactor core emergency cooling system is used for taking away reactor core waste heat generated by the residual fission of the reactor core in the main loop system when an accident occurs.
In another embodiment of the invention, a passive safety injection system for a nuclear power plant is provided, wherein a main loop system of the nuclear power plant comprises a steam generator and a U-shaped pipe which are arranged in a containment vessel, the passive safety injection system for the nuclear power station comprises an in-containment reservoir, a water supply pipe, a water supply isolation valve, a passive safety injection jet pump, a pressure release valve on the secondary side of an evaporator, a steam discharge pipe, an injection pipe, cooling water and a safety injection isolation valve, wherein the bottom of the in-containment reservoir is higher than the top of a U-shaped pipe, the cooling water is stored in the in-containment reservoir, the in-containment reservoir is communicated with the passive safety injection jet pump through the water supply pipe and the water supply isolation valve arranged on the water supply pipe, and the passive safety injection jet pump is communicated with the secondary side of the evaporator through the steam discharge pipe and the pressure release valve on the secondary side of the evaporator arranged on the steam discharge pipe and is communicated with the secondary side of the evaporator through the injection pipe and the safety injection isolation valve on the injection pipe.
According to another embodiment of the present invention, there is provided a passive safety injection system for a nuclear power plant, wherein in the event of an accident, a pressure at a secondary side of a steam generator is increased, a pressure relief valve at a secondary side of an evaporator is opened, and steam is discharged through a steam discharge pipe, and decay heat of a reactor core is taken away by the discharged steam; the discharged steam is led into a passive safety injection jet pump to push the passive safety injection jet pump, the passive safety injection jet pump pumps cooling water in a reservoir in a containment to the secondary side of the steam generator for water supplement through a water supply pipe and a water supply isolation valve arranged on the water supply pipe and through an injection pipe and a safety injection isolation valve arranged on the injection pipe, the secondary side of the steam generator is continuously supplemented with the cooling water, and the U-shaped pipe is submerged; at the moment, the hot water on the primary side in the U-shaped pipe is cooled, the cooling water on the secondary side of the steam generator is heated to be saturated and generates steam, the generated steam is discharged by the pressure release valve on the secondary side of the steam generator, the discharged steam is guided into the passive safety injection jet pump to push the passive safety injection jet pump, and the passive safety injection jet pump continuously supplements the cooling water in the water storage tank in the containment to the steam generator.
The passive safety injection system for the nuclear power station operates in a passive mode, the liquid level in the secondary side of the evaporator is always kept in a normal liquid level range, so that the coolant in the U-shaped pipe is cooled, the steam generated by heating and evaporating saturated water in the secondary side of the evaporator is discharged into the containment by the pressure release valve on the secondary side of the evaporator, and the cooling water in the water storage tank in the containment is continuously supplemented into the secondary side of the steam generator, so that the heat generated by the reactor core in the main loop system is continuously taken away, the reactor core is continuously cooled, and the safety of the nuclear power station is ensured.
Drawings
The above and other aspects of the invention will be discussed in detail below with reference to the attached drawings, wherein:
FIG. 1 is a schematic diagram of a passive nuclear power plant primary circuit system in the prior art.
Fig. 2 is a passive safety injection system for a nuclear power plant according to the present invention.
Part number and list
| 1 | Reactor core |
| 2 | Reactor pressure vessel |
| 3 | Main loop system cold section |
| 4 | Hot section of main loop system |
| 5 | U-shaped |
| 6 | Steam generator |
| 7 | Steam generator cold chamber compartment |
| 8 | Steam generator hot chamber compartment |
| 9 | |
| 10 | |
| 11 | |
| 12 | |
| 13 | Main |
| 20 | Passive safety steam |
| 21 | Pressure release valve at secondary side of |
| 22 | Steam |
| 23 | Safety |
| 24 | |
| 25 | |
| 26 | Reservoir in |
| 27 | Water supply isolation valve |
Detailed Description
Fig. 1-2 and the following description depict alternative embodiments of the invention to teach those skilled in the art how to make and reproduce the invention. Some conventional aspects have been simplified or omitted for the purpose of teaching the present invention. Those skilled in the art will appreciate that variations or substitutions from these embodiments will fall within the scope of the invention. Those skilled in the art will appreciate that the features described below can be combined in various ways to form multiple variations of the invention. Thus, the present invention is not limited to the following alternative embodiments, but is only limited by the claims and their equivalents.
Fig. 2 is a passive safety injection system for a nuclear power plant according to the present invention. The passive safety injection system for the nuclear power station comprises an in-containment reservoir 26, a water supply pipe 25, a water supply isolation valve 27, a passive safety injection turbine pump 20, a pressure relief valve 21 on the secondary side of an evaporator, a steam discharge pipe 22, a safety injection pipe 24, cooling water and a safety injection isolation valve 23. The bottom of the reservoir 26 in the containment is higher than the top of the U-shaped pipe 5, cooling water is stored in the reservoir 26 in the containment, the reservoir 26 in the containment is communicated with the passive safety injection turbine pump 20 through a water supply pipe 25 and a water supply isolation valve 27 arranged on the water supply pipe 25, and the passive safety injection turbine pump 20 is communicated with the secondary side of the evaporator through a steam discharge pipe 22 and a pressure relief valve 21 arranged on the secondary side of the evaporator and communicated with the secondary side of the evaporator through an injection pipe 24 and a safety injection isolation valve 23 arranged on the injection pipe 24.
In normal operating conditions, the safety injection isolation valve 23 is in the closed position. When an accident occurs, the pressure of the secondary side of the steam generator rises, the pressure release valve 21 of the secondary side of the evaporator is opened, steam is discharged through the steam discharge pipe 22, and the discharged steam takes away decay heat of the reactor core 1; the discharged steam is led into a passive safety steam injection turbine pump 20 to push the passive safety steam injection turbine pump 20, the passive safety steam injection turbine pump 20 pumps cooling water in a reservoir 26 in a containment to the secondary side of the steam generator for water supplement through a water supply pipe 25 and a water supply isolation valve 27 arranged on the water supply pipe 25 and through an safety injection pipe 24 and a safety steam injection isolation valve 23 arranged on the safety injection pipe 24, the secondary side of the steam generator is continuously supplemented with the cooling water, and the U-shaped pipe 5 is kept submerged; at this time, the hot water on the primary side in the U-shaped tube 5 is cooled, the cooling water on the secondary side of the steam generator is heated to saturation to generate steam, the generated steam is discharged by the pressure release valve 21 on the secondary side of the steam generator, the discharged steam is guided into the passive safety steam injection turbine pump 20 to push the passive safety steam injection turbine pump 20, and the cooling water in the reservoir 26 in the containment vessel is continuously supplemented into the steam generator 6 by the passive safety steam injection turbine pump 20. The heat generated by the reactor core 1 in the reactor pressure vessel 2 is continuously taken away, and the reactor core 1 is continuously cooled, so that the safety of the reactor core is ensured.
In another embodiment of the present invention, unlike the passive safety injection system for a nuclear power plant provided in fig. 2, the passive safety injection pump 20 is replaced with a passive safety injection pump. In normal operating conditions, the safety injection isolation valve 23 is in the closed position. When an accident occurs, the pressure of the secondary side of the steam generator rises, the pressure release valve 21 of the secondary side of the evaporator is opened, steam is discharged through the steam discharge pipe 22, and the discharged steam takes away decay heat of the reactor core 1; the discharged steam is led into a passive safety injection jet pump to push the passive safety injection jet pump, the passive safety injection jet pump pumps cooling water in a reservoir 26 in a containment to the secondary side of the steam generator for water supplement through a water supply pipe 25 and a water supply isolation valve 27 arranged on the water supply pipe 25 and through an injection pipe 24 and a safety injection isolation valve 23 arranged on the injection pipe 24, the secondary side of the steam generator is continuously supplemented with the cooling water, and the U-shaped pipe 5 is kept submerged; at the moment, the hot water on the primary side in the U-shaped pipe 5 is cooled, the cooling water on the secondary side of the steam generator is heated to saturation to generate steam, the generated steam is discharged by the pressure release valve 21 on the secondary side of the steam generator, the discharged steam is guided into the passive safety jet pump to push the passive safety jet pump, and the cooling water in the reservoir 26 in the containment is continuously supplemented into the steam generator 6 by the passive safety jet pump. The heat generated by the reactor core 1 in the reactor pressure vessel 2 is continuously taken away, and the reactor core 1 is continuously cooled, so that the safety of the reactor core is ensured.
The passive safety injection system for the nuclear power station operates in a passive mode, the liquid level in the secondary side of the evaporator is always kept in a normal liquid level range, so that the coolant in the U-shaped pipe is cooled, the steam generated by heating and evaporating saturated water in the secondary side of the evaporator is discharged into the containment by the pressure release valve on the secondary side of the evaporator, and the cooling water in the water storage tank in the containment is continuously supplemented into the secondary side of the steam generator, so that the heat generated by the reactor core in the main loop system is continuously taken away, the reactor core is continuously cooled, and the safety of the nuclear power station is ensured.
Claims (5)
1. A passive safety injection system for a nuclear power station is characterized in that a main loop system of the nuclear power station comprises a steam generator and a U-shaped pipe which are arranged in a containment vessel, the passive safety injection system for the nuclear power station is characterized by comprising an in-containment reservoir, a water supply pipe, a water supply isolation valve, a passive safety injection turbine pump, a pressure release valve on the secondary side of an evaporator, a steam discharge pipe, an injection pipe, cooling water and an injection isolation valve, wherein the bottom of the in-containment reservoir is higher than the top of a U-shaped pipe, the cooling water is stored in the in-containment reservoir, the in-containment reservoir is communicated with the passive safety injection turbine pump through the water supply pipe and the water supply isolation valve arranged on the water supply pipe, and the passive safety injection turbine pump is communicated with the secondary side of the evaporator through the steam discharge pipe and the pressure release valve on the secondary side of the evaporator arranged on the steam discharge pipe and is communicated with the secondary side of the evaporator through the injection pipe and the injection isolation valve on the injection pipe.
2. The passive safety injection system for a nuclear power plant according to claim 1, wherein in the event of an accident, the pressure at the secondary side of the steam generator rises, the pressure relief valve at the secondary side of the evaporator opens to discharge steam through the steam discharge pipe, and the discharged steam takes away decay heat of the reactor core; the discharged steam is led into a passive safety steam injection turbine pump to push the passive safety steam injection turbine pump, the passive safety steam injection turbine pump pumps cooling water in a water storage tank in the containment to the secondary side of the steam generator for water supplement through a water supply pipe and a water supply isolation valve arranged on the water supply pipe and through the safety pipe and the safety steam injection isolation valve arranged on the safety pipe, the secondary side of the steam generator is continuously supplemented with the cooling water, and the U-shaped pipe is kept submerged; at the moment, the hot water on the primary side in the U-shaped pipe is cooled, the cooling water on the secondary side of the steam generator is heated to be saturated and generates steam, the generated steam is discharged by the pressure release valve on the secondary side of the steam generator, the discharged steam is guided into the passive safety steam injection turbine pump to push the passive safety steam injection turbine pump, and the passive safety steam injection turbine pump continuously supplements the cooling water in the water storage tank in the containment to the steam generator.
3. The passive safety injection system for a nuclear power plant of claim 1, wherein the nuclear power plant includes a primary loop system and a reactor core emergency cooling system in communication therewith for removing reactor core waste heat from residual fission of the reactor core in the primary loop system in the event of an accident.
4. A passive safety injection system for a nuclear power station is characterized in that a main loop system of the nuclear power station comprises a steam generator and a U-shaped pipe which are arranged in a containment vessel, the passive safety injection system for the nuclear power station is characterized by comprising an in-containment reservoir, a water supply pipe, a water supply isolation valve, a passive safety injection jet pump, a pressure release valve on the secondary side of an evaporator, a steam discharge pipe, an injection pipe, cooling water and an injection isolation valve, wherein the bottom of the in-containment reservoir is higher than the top of a U-shaped pipe, the cooling water is stored in the in-containment reservoir, the in-containment reservoir is communicated with the passive safety injection jet pump through the water supply pipe and the water supply isolation valve arranged on the water supply pipe, and the passive safety injection jet pump is communicated with the secondary side of the evaporator through the steam discharge pipe and the pressure release valve on the secondary side of the evaporator arranged on the steam discharge pipe and is communicated with the secondary side of the evaporator through the injection pipe and the injection isolation valve on the injection pipe.
5. The passive safety injection system for the nuclear power plant according to claim 4, wherein in the event of an accident, the pressure of the secondary side of the steam generator rises, the pressure relief valve on the secondary side of the evaporator opens, steam is discharged through the steam discharge pipe, and the discharged steam takes away decay heat of the reactor core; the discharged steam is led into a passive safety injection jet pump to push the passive safety injection jet pump, the passive safety injection jet pump pumps cooling water in a reservoir in a containment to the secondary side of the steam generator for water supplement through a water supply pipe and a water supply isolation valve arranged on the water supply pipe and through an injection pipe and a safety injection isolation valve arranged on the injection pipe, the secondary side of the steam generator is continuously supplemented with the cooling water, and the U-shaped pipe is submerged; at the moment, the hot water on the primary side in the U-shaped pipe is cooled, the cooling water on the secondary side of the steam generator is heated to be saturated and generates steam, the generated steam is discharged by the pressure release valve on the secondary side of the steam generator, the discharged steam is guided into the passive safety injection jet pump to push the passive safety injection jet pump, and the passive safety injection jet pump continuously supplements the cooling water in the water storage tank in the containment to the steam generator.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510238671.6A CN106297915B (en) | 2015-05-12 | 2015-05-12 | Passive safety injection system for nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510238671.6A CN106297915B (en) | 2015-05-12 | 2015-05-12 | Passive safety injection system for nuclear power station |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106297915A CN106297915A (en) | 2017-01-04 |
| CN106297915B true CN106297915B (en) | 2020-04-17 |
Family
ID=57631549
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201510238671.6A Active CN106297915B (en) | 2015-05-12 | 2015-05-12 | Passive safety injection system for nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106297915B (en) |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR102044832B1 (en) * | 2018-01-04 | 2019-11-15 | 한국원자력연구원 | Safety injection device and nuclear power plant having the same |
| CN209232422U (en) * | 2018-11-14 | 2019-08-09 | 中广核研究院有限公司 | The coolant of reactor and reactor emergency injected system |
| CN111446013A (en) * | 2020-04-24 | 2020-07-24 | 上海核工程研究设计院有限公司 | Marine environment secondary side passive waste heat removal system and use method |
| CN112071454B (en) * | 2020-09-15 | 2023-01-03 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| CN113421660A (en) * | 2021-05-31 | 2021-09-21 | 上海核工程研究设计院有限公司 | Novel automatic pressure relief system and method for nuclear power plant |
| CN115376395B (en) * | 2022-08-05 | 2023-11-10 | 国家电投集团科学技术研究院有限公司 | Full-process simulation test system for water loss accident |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102426864A (en) * | 2011-12-12 | 2012-04-25 | 曾祥炜 | Passive emergency cooling system for severe accident in reactor |
| CN102693673A (en) * | 2012-06-04 | 2012-09-26 | 华北电力大学 | Simulation running apparatus for passive safety master system of pressurized water reactor nuclear island |
| CN102903404A (en) * | 2012-08-20 | 2013-01-30 | 中国核电工程有限公司 | Active-passive combined reactor core residual heat removal system for nuclear power station |
| JP2013104729A (en) * | 2011-11-11 | 2013-05-30 | Hitachi-Ge Nuclear Energy Ltd | Nuclear reactor core cooling system and nuclear power plant facility equipped with the same |
| CN104064231A (en) * | 2013-03-21 | 2014-09-24 | 中广核（北京）仿真技术有限公司 | Low replacement material water-tank emergency coolant system outside nuclear reactor containment vessel |
-
2015
- 2015-05-12 CN CN201510238671.6A patent/CN106297915B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2013104729A (en) * | 2011-11-11 | 2013-05-30 | Hitachi-Ge Nuclear Energy Ltd | Nuclear reactor core cooling system and nuclear power plant facility equipped with the same |
| CN102426864A (en) * | 2011-12-12 | 2012-04-25 | 曾祥炜 | Passive emergency cooling system for severe accident in reactor |
| CN102693673A (en) * | 2012-06-04 | 2012-09-26 | 华北电力大学 | Simulation running apparatus for passive safety master system of pressurized water reactor nuclear island |
| CN102903404A (en) * | 2012-08-20 | 2013-01-30 | 中国核电工程有限公司 | Active-passive combined reactor core residual heat removal system for nuclear power station |
| CN104064231A (en) * | 2013-03-21 | 2014-09-24 | 中广核（北京）仿真技术有限公司 | Low replacement material water-tank emergency coolant system outside nuclear reactor containment vessel |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106297915A (en) | 2017-01-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106297915B (en) | Passive safety injection system for nuclear power station | |
| CN105810256B (en) | A kind of nuclear power station passive residual heat removal system | |
| CN103903659B (en) | Floating nuclear power plant Heat Discharging System of Chinese | |
| CN105810257B (en) | A kind of passive nuclear power station pressure release condensation heat exchange system | |
| US20120294407A1 (en) | Nuclear Power Plant, Fuel Pool Water Cooling Facility and Method Thereof | |
| US20180350472A1 (en) | Passive safe cooling system | |
| CN204480678U (en) | A kind of nuclear power station Heat Discharging System of Chinese | |
| CN111128414B (en) | Active and passive combined safety system and method for nuclear power plant | |
| KR101463440B1 (en) | Passive safety system and nuclear power plant having the same | |
| CN202110832U (en) | Top-positioned type non-dynamic emergency waste heat discharging system for pressurized water reactor | |
| KR102115043B1 (en) | Underwater electricity generation module | |
| US10762995B2 (en) | Shutdown cooling system and nuclear facility having same | |
| CN107644693B (en) | Naval reactor and once through steam generator Passive residual heat removal system | |
| CN104508753A (en) | Defense in depth safety paradigm for nuclear reactor | |
| CN113808764B (en) | Method and system for guiding out residual heat of reactor core in containment | |
| CN105957567A (en) | Steam generator secondary side passive residual heat removal system | |
| CN107665742B (en) | It is active to meet an urgent need residual heat removal system with the passive naval reactor that combines | |
| CN102903402A (en) | Advanced secondary side core heat lead-out device | |
| CN104205239A (en) | System for discharging residual power of pressurized water nuclear reactor | |
| KR20200027883A (en) | Nuclear reactor long-term cooling system and nuclear plant having the same | |
| CN210837199U (en) | Waste heat discharge system and nuclear power system | |
| KR101897985B1 (en) | Emergency power production system and nuclear power plant having the same | |
| KR102109991B1 (en) | Electricity generation module | |
| CN110726132B (en) | Method and system for supplying water to steam generator of nuclear power station under low-power working condition | |
| CN209149827U (en) | A kind of secondary side residual heat removal system of active and passive combination |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |