CN202549318U - Residual heat removable system of nuclear reactor - Google Patents
Residual heat removable system of nuclear reactor Download PDFInfo
- Publication number
- CN202549318U CN202549318U CN2012200721232U CN201220072123U CN202549318U CN 202549318 U CN202549318 U CN 202549318U CN 2012200721232 U CN2012200721232 U CN 2012200721232U CN 201220072123 U CN201220072123 U CN 201220072123U CN 202549318 U CN202549318 U CN 202549318U
- Authority
- CN
- China
- Prior art keywords
- residual heat
- reactor
- tank
- heat exchanger
- nuclear reactor
- 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.)
- Expired - Fee Related
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
Abstract
The utility model aims at providing a residual heat removable system of a nuclear reactor to enhance the reliability of residual heat removable of the nuclear reactor, wherein the residual heat removable system of the nuclear reactor comprises a reactor main coolant, a residual heat exchanger, a passive water feeding tank and a sprayer, and a working medium flows from the passive water feeding tank to an inlet of the residual heat removable system to absorb the heat of the reactor main coolant transferred by the residual heat exchanger, flows from an outlet of the residual heat exchanger to the sprayer and then is sprayed in the passive water feeding tank through the sprayer; and the passive water feeding tank is higher than the residual heat exchanger.
Description
Technical field
The utility model relates to the safety system of nuclear reactor, relates in particular to the nuclear reactor residual heat removal system.
Background technology
Residual heat removal system is important measures of reactor safety protection.When having an accident, because shutdown afterreaction heap continues to produce decay heat, need decay heat be discharged, in order to avoid the reactor thermal accumlation, reactor core and pressure boundary are damaged owing to temperature and pressure is too high.
China utility model patent 201020227239.X (document 1) discloses a kind of security system that guarantees nuclear plant safety; Relate to the security system that is used to guarantee nuclear plant safety, through the spray subsystem that is provided with on containment top, after security incident takes place; Equipment in the containment and space are sprayed cooling; Can take away the heat in the containment, reduce the pressure in the containment, play the effect of prevention containment superpressure.Further, can absorb heat, guarantee not superpressure of containment through the melt pit endothermic water tank.And can be through injecting chilled water in the subsystem inner pressure vessel when having an accident, thereby derive the heat of reactor in-core.This system is through taking away the heat of reactor core to the high pressure of reactor pressure vessel, middle pressure, low pressure water injection, and heat is spurted in the containment, and the spray through containment reduces the temperature and pressure in the containment again; Effectively heat is not taken away; Also a cover system need be set, the heat of shower water is brought to the outer ultimate heat sink of containment, system complex; Pilot process is many, and the thrashing probability must increase.
China's utility application 201110037783.7 discloses this system of the non-active engineered safety system of a kind of nuclear power station and comprises secondary side passive residual heat discharge heat exchanger, steam condensate (SC) case, non-active heap chamber waterflood system, non-active high pressure reactor core water supply tank and relevant valve and pipeline.When nuclear power station generation design basis accident and super design reference accident; Through a series of non-active and active MP of input in steps; In time with rapidly reactor-loop and reactor core are effectively cooled off, make nuclear power station get into safe cold shut state smoothly.This system takes away decay heat from the steam generator secondary side of nuclear power plant system, and the heat of taking away is discharged heat exchanger through the secondary side passive residual heat and passed in the steam condensate (SC) case in the containment, and the decrease temperature and pressure function of containment is realized by the spray in the containment; That is to say; And have at the beginning of the deficiency of document 1 similar at the beginning of, promptly just the heat of reactor core is brought in the containment, reactor designing requirement heat must be passed to ultimate heat sink; Therefore need other a set of equipment could heat be brought to the outer ultimate heat sink of containment; System complex, pilot process is many, and the thrashing probability must increase; In addition, do not have the reserve tank device because the secondary side passive residual heat is discharged heat exchanger, so its intrasystem water loading amount is less, only relies on the initial water loading amount of steam generator, is difficult to the reliability service of the system that guarantees;
The utility model content
The purpose of the utility model is to provide a kind of nuclear reactor residual heat removal system, the reliability of discharging with the waste heat that strengthens nuclear reactor.
For realizing the nuclear reactor residual heat removal system of said purpose; Be characterized in; Comprise reactor Main Coolant, afterheat heat exchanger, non-active feed-tank and sprinkler, working medium flow to the inlet of afterheat heat exchanger from non-active feed-tank, absorbs the heat of the reactor coolant that is transmitted by afterheat heat exchanger; Flow to sprinkler from the outlet of afterheat heat exchanger, be sprayed at the non-active feed-tank from sprinkler again; The position of the position height ratio afterheat heat exchanger of non-active feed-tank wants high.
Described nuclear reactor residual heat removal system, its further characteristics are that non-active feed-tank is an open container, its top and atmosphere.
Described nuclear reactor residual heat removal system, its further characteristics are that said working medium is water.
Described nuclear reactor residual heat removal system, its further characteristics are that said afterheat heat exchanger is the steam generator of reactor.
Described nuclear reactor residual heat removal system, its further characteristics are that the part pipeline that is exported to sprinkler of steam generator is the main steam line of reactor.
Described nuclear reactor residual heat removal system, its further characteristics are that the part pipeline of non-active feed-tank to the inlet of steam generator is the main feed water pipe road of reactor.
Described nuclear reactor residual heat removal system, its further characteristics are that sprinkler is immersed in the non-active feed-tank.
The residual heat removal system of the utility model; Can be under some special operation conditions of reactor; After having an accident; Efficiently the heat of reactor Main Coolant is brought to ultimate heat sink over a period to come, owing to directly heat is brought to ultimate heat sink, this system has advantages such as system is simple, reliability is high, pilot process is few.
Description of drawings
Fig. 1 is the system chart of the nuclear reactor residual heat removal system of the utility model embodiment 1.
Fig. 2 is the system chart of the nuclear reactor residual heat removal system of the utility model embodiment 2.
Embodiment
Embodiment 1
Shown in Figure 1, the residual heat removal system of nuclear reactor comprises that reactor Main Coolant 1, afterheat heat exchanger 2, non-active feed-tank 4, sprinkler 5 form.Reactor Main Coolant 1 is formed the loop with reactor core, and to take away the reactor core heat, reactor Main Coolant 1 contacts with afterheat heat exchanger 2, to carry out heat interchange.Afterheat heat exchanger 2, non-active feed-tank 4, sprinkler 5 constitute the heat-exchange working medium flow circuits through pipeline, non-active feed-tank 4 and with it the working medium in the residual heat removal system of UNICOM be water, also can replace with other feasible working medium.
On the residual heat removal system pipeline 3 valve is set, valve can be taked different types of valve (like non-return valve, motorized valve, explosive valve etc.) and the combination of (adding series connection etc. like series, parallel, parallel connection) of different arrangements, to realize various functional controls.
As shown in Figure 2, afterheat heat exchanger 2 can be the steam generator of reactor, also can be that the independent waste heat that is provided with is discharged heat interchanger.
Non-active feed-tank 4 is open container, its top and atmosphere, the water in the non-active water tank 4 is heated back evaporation, with heat discharge in atmosphere.
The bottom of non-active feed-tank 4 directly links to each other with the inlet of afterheat heat exchanger 2 with valve through pipeline, forms circulation, and such system can take away the waste heat of reactor Main Coolant over a period to come efficiently.
Position height ratio afterheat heat exchanger 2 height of non-active feed-tank 4 are to realize segregation drive.
Working medium absorbs the heat of the reactor coolant 1 of afterheat heat exchanger 2 transmission; Flow to sprinkler 5 from the outlet of afterheat heat exchanger 2; Be sprayed at the non-active feed-tank 4 from sprinkler 5 again, to heat the working medium in the non-active feed-tank 4, at the inlet that from non-active feed-tank 4, flow to afterheat heat exchanger 2 by means of gravity; Cycle heat exchange like this, directly the heat with the reactor in-core brings in the atmosphere.
As shown in Figure 2; In embodiment 2; With the steam generator 24 of reactor as afterheat heat exchanger; The import and export of afterheat heat exchanger 24 are connected respectively on the main feed water pipe road 9 and main steam line 28 of reactor, utilize main steam line 28 and main feed water pipe road 29 near the part of the steam generator part as residual heat removal system.
After reactor has an accident, can discharge the waste heat of reactor core through residual heat removal system, detailed process is following:
The reactor shutdown that has an accident, the isolation valve between main steam line 28 and the steam turbine cuts out, and isolates main steam line, so that main steam line 28 only plays the effect of the part of residual heat removal system.Same main feed water isolating valve is closed, and isolates main feed water pipe road 29, so that main feed water pipe road 29 only plays the effect of the part of residual heat removal system.
Reactor Main Coolant 22 reactor core 21 of flowing through; Take away the reactor core heat through pipeline 23; And get in the steam generator 24, the heat-transfer pipe through steam generator 24 is with the heat transferred secondary side, and secondary side (for example is a water with the working medium in the main feed water pipe road 29; Also can be other working medium that are suitable for) produce steam, and be sprayed in the non-active feed-tank 26 by sprinkler 27 by the pipeline (comprising part main steam line 28) of residual heat removal system.
Working medium in the non-active feed-tank 26 is taken away the heat of primary side of steam generator Main Coolant once more because segregation drive gets into steam generator 24 through piping, flows out steam generator 24, gets into non-active feed-tank 26 through sprinkler 27.
Sustained delivery along with heat; Temperature in the non-active feed-tank 26 slowly raises; Pressure keeps atmospheric pressure, and the water source start vaporizer in the non-active feed-tank 26 also reduces gradually, forms circulation until its gravity deficiency to drive residual heat removal system; Arrive this, the reactor waste that residual heat removal system was accomplished in one period is efficiently discharged.
Embodiment illustrated in figures 1 and 2 is not the restriction to the utility model, and the connected mode between above-mentioned each parts does not limit this a kind of, and all connected modes that can reach similar effect all belong within the scope of the utility model.
Claims (7)
1. nuclear reactor residual heat removal system; It is characterized in that; Comprise reactor Main Coolant, afterheat heat exchanger, non-active feed-tank and sprinkler, working medium flow to the inlet of afterheat heat exchanger from non-active feed-tank, absorbs the heat of the reactor coolant that is transmitted by afterheat heat exchanger; Flow to sprinkler from the outlet of afterheat heat exchanger, be sprayed at the non-active feed-tank from sprinkler again; The position of the position height ratio afterheat heat exchanger of non-active feed-tank wants high.
2. nuclear reactor residual heat removal system as claimed in claim 1 is characterized in that, non-active feed-tank is an open container, its top and atmosphere.
3. nuclear reactor residual heat removal system as claimed in claim 1 is characterized in that, said working medium is water.
4. nuclear reactor residual heat removal system as claimed in claim 1 is characterized in that, said afterheat heat exchanger is the steam generator of reactor.
5. nuclear reactor residual heat removal system as claimed in claim 4 is characterized in that, the part pipeline that is exported to sprinkler of steam generator is the main steam line of reactor.
6. nuclear reactor residual heat removal system as claimed in claim 4 is characterized in that, the part pipeline of non-active feed-tank to the inlet of steam generator is the main feed water pipe road of reactor.
7. nuclear reactor residual heat removal system as claimed in claim 1 is characterized in that, sprinkler is immersed in the non-active feed-tank.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012200721232U CN202549318U (en) | 2012-02-29 | 2012-02-29 | Residual heat removable system of nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012200721232U CN202549318U (en) | 2012-02-29 | 2012-02-29 | Residual heat removable system of nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN202549318U true CN202549318U (en) | 2012-11-21 |
Family
ID=47169911
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012200721232U Expired - Fee Related CN202549318U (en) | 2012-02-29 | 2012-02-29 | Residual heat removable system of nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN202549318U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103295657A (en) * | 2012-02-29 | 2013-09-11 | 上海核工程研究设计院 | Residual heat removal system of nuclear reactor |
| CN106887263A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | The secondary laterally opened Heat Discharging System of Chinese of once through steam generator |
| CN107179169A (en) * | 2017-06-14 | 2017-09-19 | 中广核工程有限公司 | A kind of nuclear power station check valve action test set and test method |
-
2012
- 2012-02-29 CN CN2012200721232U patent/CN202549318U/en not_active Expired - Fee Related
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103295657A (en) * | 2012-02-29 | 2013-09-11 | 上海核工程研究设计院 | Residual heat removal system of nuclear reactor |
| CN106887263A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | The secondary laterally opened Heat Discharging System of Chinese of once through steam generator |
| CN107179169A (en) * | 2017-06-14 | 2017-09-19 | 中广核工程有限公司 | A kind of nuclear power station check valve action test set and test method |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN105810257B (en) | A kind of passive nuclear power station pressure release condensation heat exchange system | |
| CN202887748U (en) | Passive heat discharge device for dealing with plant switch-off accident | |
| CA2954136C (en) | Containment cooling system and containment and reactor pressure vessel joint cooling system | |
| CN105810256B (en) | A kind of nuclear power station passive residual heat removal system | |
| 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 | |
| CN202948738U (en) | Kinetic and non-kinetic combined waste heat discharging system | |
| US20180350472A1 (en) | Passive safe cooling system | |
| CN103413581B (en) | passive containment cooling system | |
| KR101242746B1 (en) | Integrated passive safety system outside containment for nuclear power plants | |
| CN204480678U (en) | A kind of nuclear power station Heat Discharging System of Chinese | |
| US10134493B2 (en) | Reactor and operating method for the reactor | |
| CN204242601U (en) | Non-passive safety cooling system | |
| CN107393605A (en) | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor | |
| CN103617815A (en) | Passive residual heat exhausting system of pressurized water reactor nuclear power plant | |
| WO2014048292A1 (en) | Combined active and passive reactor core water injection and heat removal apparatus | |
| CN102867548A (en) | Active and passive combined secondary side reactor core heat derivation device | |
| CN103295657A (en) | Residual heat removal system of nuclear reactor | |
| CN201698776U (en) | Continuous-operation safety injection and spray system for nuclear power station | |
| CN201788707U (en) | Safety system for ensuring safety of nuclear power station | |
| CN106297915B (en) | Passive safety injection system for nuclear power station | |
| CN110517796A (en) | A kind of improved passive residual heat removal system | |
| CN107767973A (en) | Spent nuclear fuel in nuclear power plant pond supplements cooling device | |
| CN204029396U (en) | Non-active concrete containment cooling system | |
| CN106328223A (en) | Novel passive safety shell energy control system |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C17 | Cessation of patent right | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20121121 Termination date: 20140229 |