CN104505130A - Nuclear power station passive emergency water supply system - Google Patents
Nuclear power station passive emergency water supply system Download PDFInfo
- Publication number
- CN104505130A CN104505130A CN201410658879.9A CN201410658879A CN104505130A CN 104505130 A CN104505130 A CN 104505130A CN 201410658879 A CN201410658879 A CN 201410658879A CN 104505130 A CN104505130 A CN 104505130A
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- Prior art keywords
- steam
- emergency feedwater
- supply system
- pipeline
- power station
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a nuclear power station passive emergency water supply system, which is different with a traditional nuclear power station emergency water supply system, and the traditional nuclear power station emergency water supply system is characterized in that emergency water supply is provided by power-driven, steam-driven or a diesel engine pump. The water supply system employs a steam jet pump, steam generated in a reactor steam generator is taken as a driving source, under loss of main feed water and factory electric accident, the passive emergency water supply system takes water from emergency water supply source, then the water passes through the steam jet pump for boosting and then is conveyed to a steam generator, and a loop of sensible heat and decay heat can be outwardly taken through a main steam pipe. the steam jet pump is the supercharging equipment without direct consumption of mechanical energy and without motion parts, compared with traditional machinery supercharging equipment, the supercharging equipment has the advantages of simple and reliable performaces. The system uses passive equipment to take the loop of sensible heat and decay heat, cooling of the loop can be realized, and the system has good feasibility and reliability.
Description
Technical field
The present invention relates to nuclear plant safety protection system, particularly relate to a kind of non-active emergency feedwater supply system.
Background technology
The emergency feedwater supply system of conventional pressurized water heap is as back-up system use when main feedwater was lost efficacy of main feed system.Under the breakdown operating mode of power station, emergency feedwater supply system is used for maintaining power station hot shutdown operating mode with time enough, and reactor is cooled to the state that residual heat removal system can put into operation.Emergency feedwater supply system belongs to engineered safeguards features, and under the transient state losing main feedwater or secondary side steam line break, emergency feedwater supply system is used to prevent reactor core from damaging, and discharges reactor core decay heat, until residual heat removal system puts into operation.Non-security relevant startup water supply system is provided with in AP1000 presurized water reactor, this system layout is at conventional island, in the main feedwater of forfeiture and forfeiture normal communication electricity event, feedwater is provided to steam generator from the water suction of condensate water tank, thus realize the depth defense function of discharging reactor coolant loop heat, prevent passive safety system action.In above process, the heat of reactor coolant loop passes to secondary coolant circuit system by steam generator, and secondary coolant circuit system is by taking heat out of to turbine bypass system or airborne release.
Chinese utility model patent (application number 201220447271.8, notification number CN202855318U) discloses a kind of non-active startup cooling system, it can under accident conditions, due to factor impacts such as main feed pump tripping operation and the changes of steam generator secondary side pressure, break the pressure equilibrium that reason density lock keeps, thus realize the startup of cooling system, emergency power pack without the need to prior art starts, and improves the reliability of system, security and economy.Chinese utility model patent (application number 201220540653.5, notification number CN202948736U) is a kind of Heat Discharging System of Chinese, it is under station blackout operating mode, derive reactor core decay heat, ensure the safety of reactor, reduce the requirement to arrangement space, decrease the pipeline be directly connected with reactor coolant loop simultaneously, reduce the probability of pipe breakage, improve security.The essence of above-mentioned two utility models is the heats utilizing the condensation of steam to discharge primary Ioops.
In existing presurized water reactor emergency feedwater supply system, drive unit comprises electrodynamic pump, Diesel engine pump and pneumatic pump, in different nuclear power stations, adopts dissimilar combination of drive means, realizes diversity.The feature of above-mentioned three kinds of drive units is using power supply or diesel engine as drive source, and realizes feedwater conveying with rotating machinery.If can design a kind of have non-can dynamic characteristic and do not have the emergency feedwater supply system of moving component, by making, the safety system of nuclear power station is more safe and reliable.
Summary of the invention
In view of the problems referred to above that prior art exists, the object of the present invention is to provide the non-active emergency feedwater supply system of a kind of nuclear power station, do not need power drives and the Diesel Driven of traditional core power plant, and do not have rotating machinery and moving component, system is simple and reliable.
Decay heat after reactor shutdown is taken away by the chilled water passed into from main feed water pipe road under normal circumstances, chilled water becomes steam at the steam generator place of reactor and discharges from main steam line, enter condenser by the by-pass valve on pipeline, or enter air by main steam safety valve.
In order to realize object of the present invention, the technical solution used in the present invention is the non-active emergency feedwater supply system of a kind of nuclear power station, comprise steam jet pump assembly and emergency feedwater source, steam jet pump assembly described in the activated vapor utilizing the steam generator of reactor to discharge, be transported in the steam generator of described reactor after the emergency feedwater entered from described emergency feedwater source and course is boosted, the steam produced is discharged through the main steam line of described steam generator again, thus takes away the damp and hot of primary Ioops and decay heat.
Further, the non-active emergency feedwater supply system of described nuclear power station can also comprise following assembly: admission pipeline, back with water inlet line and water outlet pipeline; Described admission pipeline one end is connected with the main steam line of described steam generator, and the other end is connected with the steam inlet of described steam jet pump assembly; Described back with water inlet line one end is connected with described emergency feedwater source, and the other end is connected with the water inlet of described steam jet pump assembly; Described water outlet pipeline one end is connected with the water delivering orifice of described steam jet pump assembly, and the other end is connected with described steam generator; Wherein said admission pipeline is provided with emergency feedwater admission isolation valve, described water outlet pipeline is provided with emergency feedwater isolation valve.
Under normal operation, described non-active emergency feedwater supply system is in stand-by state, described emergency feedwater admission isolation valve and described emergency feedwater isolation valve are closed, the cooling water temperature that described reactor is passed into by main feed water pipe road, chilled water produces steam after described steam generator, described steam is discharged from described main steam line, enters condenser, or enter air by main steam safety valve by the by-pass valve on pipeline; When occurring to lose main water supply accident, emergency feedwater admission isolation valve and emergency feedwater isolation valve are opened, some vapor in main steam line enters steam jet pump assembly through described admission pipeline, mixes after boosting enter steam generator through described water outlet pipeline with the emergency feedwater flowed into from described back with water inlet line.
Further, described steam jet pump assembly can be single-stage jetting pump, also can be multistage jet pump group; As shown in Figures 3 to 5, described steam jet pump assembly can be single-stage jetting pump, two-stage or plural serial stage jetting pump, or two-stage or plural parallel stage jetting pump.
Further, the water outlet pipeline of the non-active emergency feedwater supply system of described nuclear power station can be the pipeline of the described steam generator of direct access arranged separately, also can pass into the main feed water pipe road of described steam generator or the startup feedwater piping of described reactor, be connected with described steam generator by described main feed water pipe road or described startup feedwater piping.
Preferably, described back with water inlet line is also provided with emergency feedwater water inlet isolation valve.
Preferably, described admission pipeline is also provided with emergency feedwater admission variable valve, described water outlet pipeline is also provided with emergency feedwater variable valve.
Further, the control signal of described emergency feedwater admission variable valve and emergency feedwater variable valve is liquid level in steam generator and pressure.
Preferably, described admission pipeline is also provided with emergency feedwater admission non-return valve, described water outlet pipeline is also provided with emergency feedwater non-return valve.
Preferably, the non-active emergency feedwater supply system of described nuclear power station also comprises reflux pipeline and test pipeline, and described reflux pipeline one end is connected with described emergency feedwater source, and the other end is connected with the water delivering orifice of described steam jet pump assembly; Described test pipeline one end exports with auxiliary steam and is connected, and the other end is connected with the steam inlet of described steam jet pump assembly; Wherein said reflux pipeline is provided with emergency feedwater backflow isolation valve, described test pipeline is provided with auxiliary steam isolation valve.Described reflux pipeline and test pipeline can realize the routine test of emergency feedwater supply system.During routine test, emergency feedwater admission isolation valve and emergency feedwater isolation valve are closed, open auxiliary steam isolation valve and emergency feedwater backflow isolation valve, by the drive source of auxiliary steam as steam jet pump, checking steam jet pump meets performance requirement.
Preferably, described reflux pipeline is also provided with emergency feedwater backflow orifice plate.
Preferably, described test pipeline is also provided with auxiliary steam variable valve.
Preferably, described reflux pipeline is also provided with emergency feedwater backflow non-return valve, test pipeline is also provided with auxiliary steam non-return valve.
The non-active emergency feedwater supply system of nuclear power station provided by the invention can be arranged as: a steam generator configures a non-active emergency feedwater supply system, also can be configured as required, a such as multiple non-active emergency feedwater supply system of steam generator configuration, or multiple stage steam generator configures a non-active emergency feedwater supply system.
System provided by the invention can be applied to the relevant system of safety, also can be applied to the non-safety-related system performing depth defense function.
The present invention has following beneficial effect:
The present invention proposes the non-active emergency feedwater supply system design of a kind of new nuclear power station, this design from rely on electronic, steam-operating in the emergency feedwater supply system of traditional core power station or Diesel engine pump provides the feature of emergency feedwater different, adopt steam jet pump, the steam produced in reactor steam generator is as drive source, when losing main feedwater and losing electrification outside factory, non-active emergency feedwater supply system is fetched water from emergency feedwater source, after steam jet pump boosting, be transported to steam generator, and outwards take away sensible heat and the decay heat of primary Ioops by main steam line.Steam jet pump is that one does not directly consume mechanical energy, the pressure generating equipment of movement-less part, has more simple and reliable advantage than the pressure generating equipment of tradition machinery.This system utilizes non-active equipment to take away decay heat and the sensible heat of primary Ioops, realizes the cooling of primary Ioops, has good feasibility and reliability.
Be described further below with reference to the technique effect of accompanying drawing to design of the present invention, concrete structure and generation, to understand object of the present invention, characteristic sum effect fully.
Accompanying drawing explanation
Fig. 1 is the general flow chart of the non-active emergency feedwater supply system of nuclear power station in embodiment 1;
Fig. 2 is the general flow chart of the non-active emergency feedwater supply system of nuclear power station in embodiment 2;
Fig. 3 is the schematic diagram of single-stage vapor jetting pump;
Fig. 4 is the schematic diagram of two-stage or plural serial stage steam jet pump;
Fig. 5 is the schematic diagram of two-stage or plural parallel stage steam jet pump.
Embodiment
Embodiment 1
As shown in Figure 1, in the present embodiment, under normal circumstances, reactor is by the cooling water temperature passed into from main feed water pipe road 2, chilled water becomes steam at steam generator 1 place of reactor and discharges from main steam line 3, condenser (not shown) is entered after steam turbine acting, described main steam line 3 is also provided with main steam safety valve 4, atmospheric rilief valve 5 and main steam isolation valve 6, described main feed water pipe road 2 is provided with main feed check (valve) 7, main feed-regulating valve 8 and main feed water isolating valve 9.
Non-active emergency feedwater supply system is arranged on outside the containment of reactor, comprises steam jet pump assembly 15, emergency feedwater case 26, long-term water source 27, admission pipeline, back with water inlet line, water outlet pipeline, reflux pipeline and test pipeline.Described admission pipeline one end is connected with main steam line 3, and the other end is connected with the steam inlet of described steam jet pump assembly 15; Described back with water inlet line one end is connected with described emergency feedwater case 26 and long-term water source 27, and the other end is connected with the water inlet of described steam jet pump assembly 15; Described water outlet pipeline one end is connected with the water delivering orifice of described steam jet pump assembly 15, and the other end is directly connected with described steam generator 1; Described reflux pipeline one end is connected with described emergency feedwater case 26, and the other end is connected with the water delivering orifice of described steam jet pump assembly 15; Described test pipeline one end exports 22 with auxiliary steam and is connected, and the other end is connected with the steam inlet of described steam jet pump assembly 15.
Described admission pipeline is provided with emergency feedwater admission variable valve 10, emergency feedwater admission isolation valve 11 and emergency feedwater admission non-return valve 12, described back with water inlet line is provided with emergency feedwater water inlet isolation valve 13 and emergency feedwater water inlet non-return valve 14, described water outlet pipeline is provided with emergency feedwater non-return valve 16, emergency feedwater variable valve 17 and emergency feedwater isolation valve 18, described reflux pipeline is provided with emergency feedwater backflow orifice plate 19, emergency feedwater backflow non-return valve 20 and emergency feedwater backflow isolation valve 21, described test pipeline is provided with auxiliary steam variable valve 23, auxiliary steam isolation valve 24 and auxiliary steam non-return valve 25.
Under normal operation, non-active emergency feedwater supply system is in stand-by state, by emergency feedwater admission isolation valve 11 and emergency feedwater isolation valve 18, itself and steam generator 1 and main steam line 3 are isolated, by auxiliary steam isolation valve 24, auxiliary steam and emergency feedwater supply system are isolated.
When occurring to lose main water supply accident, emergency feedwater admission isolation valve 11 and emergency feedwater isolation valve 18 are opened, steam in part main steam line 3 enters steam jet pump 15 through emergency feedwater admission pipeline, mixes after boosting enter steam generator 1 through water outlet pipeline with the emergency feedwater flowed into from back with water inlet line.The heat energy that feedwater absorbs primary Ioops in a vapor generator becomes steam, overwhelming majority steam enters condenser by other row, or enter air by atmospheric rilief valve 3 (main steam safety valve 4), take away decay heat and the sensible heat of primary Ioops, fraction steam is as the drive source of jetting pump 15.The water yield meeting cooling and require is housed in emergency feedwater case 26, also enough feedwater can be provided to meet extra cooling needs by long-term water source 27.Said process utilizes non-active equipment to take away decay heat and the sensible heat of primary Ioops, realizes the cooling of primary Ioops, has good feasibility and reliability.
Liquid level in steam generator 1 and pressure are as the control signal of emergency feedwater admission variable valve 10 and emergency feedwater variable valve 17.
The routine test of emergency feedwater supply system is by testing pipeline and reflux pipeline realization.During routine test, confirm that emergency feedwater admission isolation valve 11 and emergency feedwater isolation valve 18 are closed, open auxiliary steam isolation valve 24 and emergency feedwater backflow isolation valve 21, by the drive source of auxiliary steam 22 as jetting pump 15, checking jetting pump 15 meets performance requirement.
The connection of former components is only exemplary illustration of the present invention and non-limitative illustration, also can be other connected modes.
Embodiment 2
As shown in Figure 2, the present embodiment is substantially identical with the structure of embodiment 1, difference is that the water outlet pipeline of described emergency feedwater supply system passes in described main feed water pipe road 2, be connected with described steam generator by main feed water pipe road 2, now do not need to arrange emergency feedwater variable valve in addition, the described main feed-regulating valve 8 in main feed water pipe road 2 can double as emergency feedwater variable valve.
More than describe preferred embodiment of the present invention in detail.Should be appreciated that those of ordinary skill in the art just design according to the present invention can make many modifications and variations without the need to creative work.Therefore, all technician in the art, all should by the determined protection domain of claims under this invention's idea on the basis of existing technology by the available technical scheme of logical analysis, reasoning, or a limited experiment.
Claims (10)
1. the non-active emergency feedwater supply system of nuclear power station, it is characterized in that, comprise steam jet pump assembly and emergency feedwater source, steam jet pump assembly described in the activated vapor utilizing the steam generator of reactor to discharge, be transported in the steam generator of described reactor after the emergency feedwater entered from described emergency feedwater source and course is boosted, the steam produced is discharged through the main steam line of described steam generator again, thus takes away the damp and hot of primary Ioops and decay heat.
2. the non-active emergency feedwater supply system of nuclear power station as claimed in claim 1, is characterized in that, also comprise admission pipeline, back with water inlet line and water outlet pipeline; Described admission pipeline one end is connected with the main steam line of described steam generator, and the other end is connected with the steam inlet of described steam jet pump assembly; Described back with water inlet line one end is connected with described emergency feedwater source, and the other end is connected with the water inlet of described steam jet pump assembly; Described water outlet pipeline one end is connected with the water delivering orifice of described steam jet pump assembly, and the other end is connected with described steam generator; Wherein said admission pipeline is provided with emergency feedwater admission isolation valve, described water outlet pipeline is provided with emergency feedwater isolation valve.
3. the non-active emergency feedwater supply system of nuclear power station as claimed in claim 1 or 2, it is characterized in that, described steam jet pump assembly is single-stage jetting pump or multistage jet pump group.
4. the non-active emergency feedwater supply system of nuclear power station as claimed in claim 2, it is characterized in that, described water outlet pipeline directly accesses described steam generator, or pass into the main feed water pipe road of described steam generator or the startup feedwater piping of described reactor, be connected with described steam generator by described main feed water pipe road or described startup feedwater piping.
5. the non-active emergency feedwater supply system of nuclear power station as claimed in claim 2, is characterized in that, described admission pipeline is also provided with emergency feedwater admission variable valve, described water outlet pipeline is also provided with emergency feedwater variable valve.
6. the non-active emergency feedwater supply system of nuclear power station as claimed in claim 5, is characterized in that, the control signal of described emergency feedwater admission variable valve and emergency feedwater variable valve is liquid level in steam generator and pressure.
7. the non-active emergency feedwater supply system of nuclear power station as claimed in claim 2, is characterized in that, also comprises reflux pipeline and test pipeline; Described reflux pipeline one end is connected with described emergency feedwater source, and the other end is connected with the water delivering orifice of described steam jet pump assembly; Described test pipeline one end exports with auxiliary steam and is connected, and the other end is connected with the steam inlet of described steam jet pump assembly; Wherein said reflux pipeline is provided with emergency feedwater backflow isolation valve, described test pipeline is provided with auxiliary steam isolation valve.
8. the non-active emergency feedwater supply system of nuclear power station as claimed in claim 7, is characterized in that, described reflux pipeline is also provided with emergency feedwater backflow orifice plate, described test pipeline is also provided with auxiliary steam variable valve.
9. the non-active emergency feedwater supply system of nuclear power station as claimed in claim 1 or 2, it is characterized in that, a described steam generator configures a non-active emergency feedwater supply system, or a multiple non-active emergency feedwater supply system of described steam generator configuration, or steam generator described in multiple stage configures a non-active emergency feedwater supply system.
10. the non-active emergency feedwater supply system of nuclear power station as claimed in claim 1 or 2 is in safety-related systems and the application performed in the non-safety-related system of depth defense function.
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| CN201410658879.9A CN104505130B (en) | 2014-11-18 | 2014-11-18 | A kind of passive emergency feedwater supply system of nuclear power station |
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| CN201410658879.9A CN104505130B (en) | 2014-11-18 | 2014-11-18 | A kind of passive emergency feedwater supply system of nuclear power station |
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| CN104505130B CN104505130B (en) | 2017-11-10 |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104934079A (en) * | 2015-06-26 | 2015-09-23 | 上海核工程研究设计院 | Long-term passive emergency water supply system for floating nuclear power plant |
| CN104952496A (en) * | 2015-06-26 | 2015-09-30 | 上海核工程研究设计院 | Emergent water supply system of floating nuclear power station |
| CN104952495A (en) * | 2015-06-26 | 2015-09-30 | 上海核工程研究设计院 | Secondary side residual heat removal system for twin-reactor nuclear power plant |
| CN104966535A (en) * | 2015-06-26 | 2015-10-07 | 上海核工程研究设计院 | Sea water desalination and residual heat removal dual-purpose system of floating nuclear power plant |
| CN105070325A (en) * | 2015-08-14 | 2015-11-18 | 上海核工程研究设计院 | Nuclear power station safety injection system adopting steam-jet pump |
| CN105070326A (en) * | 2015-08-18 | 2015-11-18 | 上海核工程研究设计院 | Primary loop feeding and discharging system for nuclear power plant |
| CN105401611A (en) * | 2015-11-18 | 2016-03-16 | 中国核电工程有限公司 | System and method for supplying water to radioactive regions of nuclear chemical engineering plant |
| CN105427903A (en) * | 2015-12-11 | 2016-03-23 | 哈尔滨工程大学 | Recycling safety injection system adopting gas-liquid booster pump and applied to nuclear power plant |
| CN108087093A (en) * | 2017-12-31 | 2018-05-29 | 沪东重机有限公司 | The cooling water off-line equipment of nuclear power diesel emergency generating set |
| CN109767852A (en) * | 2019-02-22 | 2019-05-17 | 西安热工研究院有限公司 | A kind of secondary circuit security system and its working method for reactor emergency shut-down |
| CN113421667A (en) * | 2021-05-10 | 2021-09-21 | 中广核研究院有限公司 | Reactor primary loop spraying system |
| CN114234173A (en) * | 2021-12-17 | 2022-03-25 | 华能山东石岛湾核电有限公司 | Nuclear power station steam generator cooling system |
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Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104934079A (en) * | 2015-06-26 | 2015-09-23 | 上海核工程研究设计院 | Long-term passive emergency water supply system for floating nuclear power plant |
| CN104952496A (en) * | 2015-06-26 | 2015-09-30 | 上海核工程研究设计院 | Emergent water supply system of floating nuclear power station |
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| CN105401611A (en) * | 2015-11-18 | 2016-03-16 | 中国核电工程有限公司 | System and method for supplying water to radioactive regions of nuclear chemical engineering plant |
| CN105427903A (en) * | 2015-12-11 | 2016-03-23 | 哈尔滨工程大学 | Recycling safety injection system adopting gas-liquid booster pump and applied to nuclear power plant |
| CN108087093A (en) * | 2017-12-31 | 2018-05-29 | 沪东重机有限公司 | The cooling water off-line equipment of nuclear power diesel emergency generating set |
| CN109767852A (en) * | 2019-02-22 | 2019-05-17 | 西安热工研究院有限公司 | A kind of secondary circuit security system and its working method for reactor emergency shut-down |
| CN109767852B (en) * | 2019-02-22 | 2024-06-04 | 西安热工研究院有限公司 | Two-loop safety system for reactor emergency shutdown and working method thereof |
| CN113421667A (en) * | 2021-05-10 | 2021-09-21 | 中广核研究院有限公司 | Reactor primary loop spraying system |
| WO2022237216A1 (en) * | 2021-05-10 | 2022-11-17 | 中广核研究院有限公司 | Reactor primary circuit spray system |
| CN114234173A (en) * | 2021-12-17 | 2022-03-25 | 华能山东石岛湾核电有限公司 | Nuclear power station steam generator cooling system |
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