CN205751539U - A kind of special non-kinetic safety equipment of nuclear power station - Google Patents
A kind of special non-kinetic safety equipment of nuclear power station Download PDFInfo
- Publication number
- CN205751539U CN205751539U CN201620406362.5U CN201620406362U CN205751539U CN 205751539 U CN205751539 U CN 205751539U CN 201620406362 U CN201620406362 U CN 201620406362U CN 205751539 U CN205751539 U CN 205751539U
- Authority
- CN
- China
- Prior art keywords
- injection
- pipeline
- power station
- tank
- nuclear power
- 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
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
This utility model provides the special non-kinetic safety equipment of a kind of nuclear power station, comprising: discharge pipe line；Heat exchanger；Bubbler；Fast pressure relief valve and injection house steward.The special non-kinetic safety equipment of the nuclear power station that this utility model provides; different from the engineered safeguards features in traditional core power station; the adapter concentrated setting of special non-kinetic safety equipment is on pressure vessel; directly reactor core is cooled down and water filling by special non-kinetic safety equipment; increase natural-circulation capacity, make safety system more safe and reliable.
Description
Technical field
This utility model relates to nuclear power station safety full guard system, is specifically related to the special non-kinetic safety equipment of a kind of nuclear power station.
Background technology
In presurized water reactor nuclear power unit, primary Ioops system is a loop, when there is loss of-coolant accident (LOCA) or Non-LOCA accident, it is crucial that core deluge to be ensured, and take away reactor core heat.When there is Non-LOCA accident, taking away reactor core heat mainly by auxiliary feedwater system and residual heat removal system in the design of existing presurized water reactor, generation Ⅲ nuclear power station uses the Heat Discharging System of Chinese of primary Ioops or secondary circuit to take reactor core heat out of.When there is loss of-coolant accident (LOCA), mainly utilizing safety injection system alleviation accident, the safety injection system of nuclear power station is to ensure that reactor occurs without the important engineered safeguards features of accident upgrading when accident conditions.The system that High-pressure injection system is usually separately provided, is furnished with electronic safety injection pump, when reactor coolant loop generation loss of-coolant accident (LOCA), to reactor pressure vessel water filling, it is ensured that core deluge.Devising Core makeup tank in third generation advanced person's nuclear power, be connected cold to Core makeup tank and main pipeline section by balance pipe, when reactor coolant loop generation loss of-coolant accident (LOCA), Core makeup tank passes through gravity to reactor pressure vessel water filling.Meanwhile, the safety injection tank pressurizeed by nitrogen is to reactor pressure vessel water filling, when reactor pressure vessel pressure drops to normal pressure, is injected to reactor core water filling by gravity.
Using the High-pressure injection system of safety injection pump, if after loss of power, safety injection pump will be unable to start, and peace pouring functions also will be unable to ensure, ultimately results in reactor core and damages.The passive system of generation Ⅲ nuclear power is connected on cold and hot section of pressure vessel, steam generator and main pipeline; if by the adapter concentrated setting of special non-kinetic safety equipment on pressure vessel; directly reactor core is cooled down and water filling by special non-kinetic safety equipment; natural-circulation capacity will be increased; reduce adapter quantity simultaneously; the system making nuclear power station simplifies, and safety system is more safe and reliable.
Utility model content
This utility model, for the deficiencies in the prior art, proposes the special non-kinetic safety equipment of a kind of nuclear power station.
The special non-kinetic safety equipment of nuclear power station includes:
Discharge pipe line；Described discharge pipe line is arranged on top cover of reactor pressure vessel；Connect on described discharge pipe line and have automatically unloading pipeline, fast pressure relief pipeline and passive residual heat removal pipeline；
Heat exchanger；Described heat exchanger is arranged on the downstream of described passive residual heat removal pipeline, and is positioned in water tank；
Bubbler；Described bubbler is arranged on the downstream of described automatically unloading pipeline；
Fast pressure relief valve；Described fast pressure relief valve is arranged on described fast pressure relief pipeline, is configured for controlling described fast pressure relief pipeline and directly discharges in containment；
Balance pipeline；Described balance pipeline is arranged on reactor pressure vessel, and is connected with Core makeup tank entrance, is configured to make reactor pressure vessel maintain pressure balance；
Injection house steward；Described injection house steward is arranged on reactor pressure vessel, and connection has Core makeup tank, safety injection tank, described passive residual heat removal pipe, low head injection pipeline and recirculation injection pipeline.
Preferably, described recirculation injection pipeline is provided with recirculation injection pipeline isolating valve and recirculation injection pipeline check-valves.
Preferably, recirculation filter screen is also included；Described recirculation filter screen is arranged on the downstream of described recirculation injection pipeline.
Preferably, heat exchanger outlet isolating valve is also included；Described heat exchanger outlet isolating valve is arranged on the downstream of described heat exchanger.
Preferably, described Core makeup tank is connected with described injection house steward by Core makeup tank injection pipeline.
Preferably, described safety injection tank is connected with described injection house steward by safety injection tank injection pipeline.
Preferably, described safety injection tank injection pipeline is provided with safety injection tank injection pipeline isolating valve and safety injection tank injection pipeline check-valves.
Compared with prior art, this utility model has the advantages that
1, the special non-kinetic safety equipment of the nuclear power station that this utility model provides; different from the engineered safeguards features in traditional core power station; the adapter concentrated setting of special non-kinetic safety equipment is on pressure vessel; directly reactor core is cooled down and water filling by special non-kinetic safety equipment; increase natural-circulation capacity, make safety system more safe and reliable.
2, the special non-kinetic safety equipment of the nuclear power station that this utility model provides, directly cools down reactor core and water filling.Being provided with discharge pipe line at top cover of reactor pressure vessel, discharge pipe line connects automatically unloading pipeline, fast pressure relief pipeline and passive residual heat removal pipeline.Being provided with injection house steward on pressure vessel, passive residual heat removal pipeline, Core makeup tank, safety injection tank, low head injection pipeline and long-term recirculation injection pipeline all inject water into reactor core by injection house steward, it is ensured that core deluge also takes away reactor core heat.
Accompanying drawing explanation
Fig. 1 is the schematic diagram of the special non-kinetic safety equipment of the nuclear power station meeting this utility model preferred embodiment.
Wherein, 1 reactor pressure vessel；2 discharge pipe lines；3 passive residual heat removal pipelines；
4 heat exchanger entrance isolating valves；5 heat exchangers；6 heat exchanger outlet isolating valves；
7 injection house stewards；8 automatically unloading pipelines；9 automatic relief valves；10 bubblers；11 water tanks；
12 fast pressure relief pipelines；13 fast pressure relief valves；14 balance pipelines；
15 Core makeup tank inlet isolation valve；16 Core makeup tanks；17 Core makeup tank injection pipelines；
18 Core makeup tank injection pipeline isolating valves；19 Core makeup tank injection pipeline check-valves；
20 gravity injection pipelines；21 gravity injection pipeline check-valves；22 gravity injection pipeline isolating valves；
23 safety injection tanks；24 safety injection tank injection pipelines；25 safety injection tank injection pipeline isolating valves；
26 safety injection tank injection pipeline check-valves；27 recirculation injection pipelines；
28 recirculation injection pipeline isolating valves；29 recirculation injection pipeline check-valves；30 recirculation filter screens
Detailed description of the invention
Understandable for enabling above-mentioned purpose of the present utility model, feature and advantage to become apparent from, with detailed description of the invention, this utility model is described in further detail below in conjunction with the accompanying drawings.
As it is shown in figure 1, the special non-kinetic safety equipment of nuclear power station includes:
Discharge pipe line 2；Described discharge pipe line 2 is arranged on the top cover of reactor pressure vessel 1；Connect on described discharge pipe line 2 and have automatically unloading pipeline 8, fast pressure relief pipeline 12 and passive residual heat removal pipeline 3；
Heat exchanger 5；Described heat exchanger 5 is arranged on the downstream of described passive residual heat removal pipeline 3, and is positioned in water tank 11；
Bubbler 10；Described bubbler 10 is arranged on the downstream of described automatically unloading pipeline 8；
Fast pressure relief valve 13；Described fast pressure relief valve 13 is arranged on described fast pressure relief pipeline 8, is configured for controlling described fast pressure relief pipeline 8 and directly discharges in containment；
Balance pipeline 14；Described balance pipeline 14 is arranged on reactor pressure vessel 1, and is connected with Core makeup tank 16 entrance, is configured to make reactor pressure vessel 1 maintain pressure balance；
Injection house steward 7；Described injection house steward 7 is arranged on reactor pressure vessel 1, and connection has Core makeup tank 16, safety injection tank 23, described passive residual heat removal pipe 3, low head injection pipeline and recirculation injection pipeline 27.
Preferably, described recirculation injection pipeline 27 is provided with recirculation injection pipeline isolating valve 28 and recirculation injection pipeline check-valves 29.
Preferably, recirculation filter screen 30 is also included；Described recirculation filter screen 30 is arranged on the downstream of described recirculation injection pipeline 27.
Preferably, heat exchanger outlet isolating valve 6 is also included；Described heat exchanger outlet isolating valve 6 is arranged on the downstream of described heat exchanger 5.
Preferably, described Core makeup tank 16 is connected with described injection house steward 7 by Core makeup tank injection pipeline 17.
Preferably, described safety injection tank 23 is connected with described injection house steward 7 by safety injection tank injection pipeline 24.
Preferably, described safety injection tank injection pipeline 24 is provided with safety injection tank injection pipeline isolating valve 25 and safety injection tank injection pipeline check-valves 26.
Compared with prior art, the present embodiment has the advantages that
1, the special non-kinetic safety equipment of the nuclear power station that the present embodiment provides; different from the engineered safeguards features in traditional core power station; the adapter concentrated setting of special non-kinetic safety equipment is on pressure vessel; directly reactor core is cooled down and water filling by special non-kinetic safety equipment; increase natural-circulation capacity, make safety system more safe and reliable.
2, the special non-kinetic safety equipment of the nuclear power station that the present embodiment provides, directly cools down reactor core and water filling.Being provided with discharge pipe line at top cover of reactor pressure vessel, discharge pipe line connects automatically unloading pipeline, fast pressure relief pipeline and passive residual heat removal pipeline.Being provided with injection house steward on pressure vessel, passive residual heat removal pipeline, Core makeup tank, safety injection tank, low head injection pipeline and long-term recirculation injection pipeline all inject water into reactor core by injection house steward, it is ensured that core deluge also takes away reactor core heat.
The operation principle of the special non-kinetic safety equipment of the nuclear power station of the present embodiment is as follows: time properly functioning, engineered safeguards features is in resting state, heat exchanger entrance isolating valve 4 and Core makeup tank inlet isolation valve 15 are in the open position, to ensure the quick execution of passive residual heat removal and peace pouring functions.When there is Non-LOCA accident, heat exchanger outlet isolating valve 6 is opened, the hot fluid of reactor pressure vessel 1 enters heat exchanger 5 through heap top discharge pipe line 2 and passive residual heat removal pipeline 3, transfer heat to the water in water tank 11, enter reactor pressure vessel 1 through injection house steward 7 after with, complete Natural Circulation.
When there is loss of-coolant accident (LOCA), Core makeup tank injection pipeline isolating valve 18 is opened, and the water in Core makeup tank 16 enters reactor pressure vessel 1 through Core makeup tank injection pipeline 17 and injection house steward 7 under gravity；Automatic relief valve 9 is opened simultaneously, and the hot fluid in reactor pressure vessel 1 enters water tank 11 by automatically unloading pipeline 8 and bubbler 10, thus reduces system pressure.Along with the development of accident, safety injection tank injection pipeline isolating valve 25 is opened, and safety injection tank 23 injects water by safety injection tank injection pipeline 24 and injection house steward 7 to reactor pressure vessel 1.If accident still can not get alleviating, fast pressure relief valve 13 will be opened, system pressure is quickly down to atmospheric pressure state, and gravity injection pipeline isolating valve 22 is opened, and the water in water tank 11 enters reactor pressure vessel 1 through gravity injection pipeline 20 and injection house steward 7 under gravity.In post incident, recirculation injection pipeline isolating valve 28 will be opened, and water enters reactor pressure vessel 1 through recirculation injection pipeline 27 and injection house steward 7, discharges from fast pressure relief pipeline 12, thus taken out of by the heat of reactor core after heat absorption.
The containment cooling system of said process utilizes high-pressure injection that water is spread across containment outer surface and cools down containment, it is ensured that containment not superpressure, maintains the integrity of containment, has simple and reliable advantage.
In this specification, each embodiment uses the mode gone forward one by one to describe, and what each embodiment stressed is the difference with other embodiments, and between each embodiment, identical similar portion sees mutually.For system disclosed in embodiment, owing to corresponding to the method disclosed in Example, so describe is fairly simple, relevant part sees method part and illustrates.
Those skilled in the art specifically should can be used for using different methods to realize described function to each, but this realization is it is not considered that exceed scope of the present utility model.
Obviously, those skilled in the art can carry out various change and modification without deviating from spirit and scope of the present utility model to utility model.So, if these amendments of the present utility model and modification belong within the scope of this utility model claim and equivalent technologies thereof, then this utility model is also intended to change and including modification include these.
Claims (7)
1. the special non-kinetic safety equipment of a nuclear power station, it is characterised in that including:
Discharge pipe line；Described discharge pipe line is arranged on top cover of reactor pressure vessel；Connect on described discharge pipe line
It is connected to automatically unloading pipeline, fast pressure relief pipeline and passive residual heat removal pipeline；
Heat exchanger；Described heat exchanger is arranged on the downstream of described passive residual heat removal pipeline, and is positioned at
In water tank；
Bubbler；Described bubbler is arranged on the downstream of described automatically unloading pipeline；
Fast pressure relief valve；Described fast pressure relief valve is arranged on described fast pressure relief pipeline, is configured for control
Make described fast pressure relief pipeline directly to discharge in containment；
Balance pipeline；Described balance pipeline is arranged on reactor pressure vessel, and with Core makeup tank entrance
Connect, be configured to make reactor pressure vessel maintain pressure balance；
Injection house steward；Described injection house steward be arranged on reactor pressure vessel, and connect have Core makeup tank,
Safety injection tank, described passive residual heat removal pipe, low head injection pipeline and recirculation injection pipeline.
2. the special non-kinetic safety equipment of nuclear power station as claimed in claim 1, it is characterised in that described
Recirculation injection pipeline is provided with recirculation injection pipeline isolating valve and recirculation injection pipeline check-valves.
3. the special non-kinetic safety equipment of nuclear power station as claimed in claim 1, it is characterised in that also wrap
Include recirculation filter screen；Described recirculation filter screen is arranged on the downstream of described recirculation injection pipeline.
4. the special non-kinetic safety equipment of nuclear power station as claimed in claim 1, it is characterised in that also wrap
Include heat exchanger outlet isolating valve；Described heat exchanger outlet isolating valve is arranged on the downstream of described heat exchanger.
5. the special non-kinetic safety equipment of nuclear power station as claimed in claim 1, it is characterised in that described
Core makeup tank is connected with described injection house steward by Core makeup tank injection pipeline.
6. the special non-kinetic safety equipment of nuclear power station as claimed in claim 1, it is characterised in that described
Safety injection tank is connected with described injection house steward by safety injection tank injection pipeline.
7. the special non-kinetic safety equipment of nuclear power station as claimed in claim 6, it is characterised in that described
Safety injection tank injection pipeline is provided with safety injection tank injection pipeline isolating valve and safety injection tank injection pipeline check-valves.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620406362.5U CN205751539U (en) | 2016-05-06 | 2016-05-06 | A kind of special non-kinetic safety equipment of nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620406362.5U CN205751539U (en) | 2016-05-06 | 2016-05-06 | A kind of special non-kinetic safety equipment of nuclear power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN205751539U true CN205751539U (en) | 2016-11-30 |
Family
ID=57371086
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201620406362.5U Active CN205751539U (en) | 2016-05-06 | 2016-05-06 | A kind of special non-kinetic safety equipment of nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN205751539U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105788676A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Passive special safety facility of nuclear power station |
| CN109765067A (en) * | 2017-11-10 | 2019-05-17 | 国核华清（北京）核电技术研发中心有限公司 | The large-scale passive core cooling system overall performance test platform of advanced pressurized water reactor nuclear power plant |
| CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
-
2016
- 2016-05-06 CN CN201620406362.5U patent/CN205751539U/en active Active
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105788676A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Passive special safety facility of nuclear power station |
| CN109765067A (en) * | 2017-11-10 | 2019-05-17 | 国核华清（北京）核电技术研发中心有限公司 | The large-scale passive core cooling system overall performance test platform of advanced pressurized water reactor nuclear power plant |
| CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| 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 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN102169733B (en) | Passive and active combined special safety system for nuclear power plant | |
| CN102903404B (en) | The reactor core surplus heat of the active and non-active combination of a kind of nuclear power station discharges system | |
| CN201689688U (en) | System for cooling reactor core, filling water in reactor cavity and guiding out heat of containment | |
| CN202102728U (en) | Safety system used for guaranteeing safety of nuclear power plant | |
| CN110097982B (en) | Safe injection and waste heat discharge system of nuclear power plant | |
| WO2014048292A1 (en) | Combined active and passive reactor core water injection and heat removal apparatus | |
| CN111081399B (en) | Emergency reactor core cooling system of nuclear power plant | |
| CN103632736B (en) | A kind of nuclear power station Reactor cavity flooding cooling system | |
| US4587079A (en) | System for the emergency cooling of a pressurized water nuclear reactor core | |
| WO2014090106A1 (en) | High-pressure safe injection system for nuclear power stations | |
| CN205751539U (en) | A kind of special non-kinetic safety equipment of nuclear power station | |
| CN103632737A (en) | Passive waste heat discharge system of nuclear power station steam generator secondary side | |
| CN201788707U (en) | Safety system for ensuring safety of nuclear power station | |
| CN113808764B (en) | Method and system for guiding out residual heat of reactor core in containment | |
| CN205751540U (en) | Major accident mitigation system of nuclear | |
| CN104361913A (en) | Secondary side passive waste heat removal system | |
| WO2014048290A1 (en) | Combined active and passive reactor cavity water injection cooling system | |
| CN201698776U (en) | Continuous-operation safety injection and spray system for nuclear power station | |
| KR101463441B1 (en) | High concentration boron injection system and safety injection system having the same | |
| CN105489257A (en) | Nitrogen pressure stabilization and high-pressure safety injection system for nuclear power plant | |
| CN105788676A (en) | Passive special safety facility of nuclear power station | |
| CN203026169U (en) | Reactor cooling agent system of pressurized water reactor nuclear power plant | |
| CN214624452U (en) | Novel reactor based on double-layer pipeline technology | |
| CN209625811U (en) | A kind of safety injection system and nuclear power station | |
| CN203026162U (en) | Entrance pipeline structure of residual heat removal system capable of avoiding 'dead pipeline' phenomenon |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |
|
| CP01 | Change in the name or title of a patent holder |