CN106373622A - Active-and-passive-fusion reactor-core waste-heat leading-out system - Google Patents
Active-and-passive-fusion reactor-core waste-heat leading-out system Download PDFInfo
- Publication number
- CN106373622A CN106373622A CN201610866600.5A CN201610866600A CN106373622A CN 106373622 A CN106373622 A CN 106373622A CN 201610866600 A CN201610866600 A CN 201610866600A CN 106373622 A CN106373622 A CN 106373622A
- Authority
- CN
- China
- Prior art keywords
- residual heat
- active
- passive
- cooling
- heat removal
- 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.)
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Classifications
-
- 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
-
- 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
- G21C15/187—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps using energy from the electric grid
-
- 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 invention discloses an active-and-passive-fusion reactor-core waste-heat leading-out system. The active-and-passive-fusion reactor-core waste-heat leading-out system comprises a reactor and one-loop system, waste-heat discharging systems and cooling systems, wherein the reactor and one-loop system, the waste-heat discharging systems and the cooling systems are arranged in parallel. The reactor and one-loop system comprises main pumps, a reactor and vapor generators, wherein the main pumps, the reactor and the vapor generators are sequentially connected; inlet pipes of the waste-heat discharging systems are led out of inlets in the vapor generators, and pass through waste-heat discharging coolers, and then outlet pipes are introduced into inlets in the main pumps. The waste-heat discharging systems comprise two active-and-passive loop circuits sharing an inlet pipe system, the waste-heat discharging coolers and an output pipe system. The cooling systems comprise cooling sources and cooling pumps, the cooling sources are connected with the waste-heat discharging coolers in parallel, and the cooling systems comprise the two active-and-passive loop circuits sharing the inlet pipe system, the waste-heat discharging coolers and the output pipe system. According to the active-and-passive-fusion reactor-core waste-heat leading-out system, the system, the devices and arrangement space can be simplified while the safety of the reactor is improved.
Description
Technical field
The present invention relates to a kind of nuclear reactor engineered safety system is and in particular to one kind has merged active technology and passive
Technology, the engineered safety system of residual heat of nuclear core (include sensible heat and decay heat) can be derived after there is the universe loss of power accident.
Background technology
At present, domestic and international Generation Ⅲ is all improved to engineered safety system, and reactor safety obtains
To improving further.For example, the ap1000 in the western room of the U.S. employs passive technology, and the epr of French Areva Ta employs active
Technology simultaneously increased redundancy, and domestic Hua Longyi acp1000 employs active and passive technology combining etc., is all
Representative technical scheme.In fact, active technology and passive technology are respectively provided with respective advantage, the former energy density
Height, controllable, technology maturation are reliable, and the latter is independent of external impetus, is not required to simple, the domestic China of manual intervention, system configuration
Both are combined by an imperial acp1000, are conducive to comprehensive respective advantage, improve reactor safety.But, will be active
Related system complexity, number of devices, arrangement space can be led to and build maintenance cost increase with passive combining.In order to
Solve this problem, the present invention is merged the residual heat of nuclear core guiding system it is proposed that new by active with passive technology, both comprehensive
Close active and passive two kinds of technical advantages, and do not roll up equipment and arrangement space it is adaptable to nuclear power plant and naval vessel core
Power set.
Content of the invention
In order to overcome the disadvantages mentioned above of prior art, the invention provides a kind of active with the passive reactor core blending more than
Hot guiding system, while improving nuclear reactor safety, can simplify and optimize system, equipment and arrangement space.
The technical solution adopted for the present invention to solve the technical problems is: a kind of active with the passive reactor core blending more than
Hot guiding system, including the reactor being arranged in parallel and primary Ioops system, residual heat removal system and cooling system three subsystems；
Described reactor and primary Ioops system include main pump, reactor and the steam generator being sequentially connected；Described residual heat removal system
Inlet tube from steam generator entrance draw, after Residual heat removal cooler, its outlet access main pump entrance, described
Residual heat removal system includes active and passive two loops of common inlet piping, Residual heat removal cooler and outlet piping；
Described cooling system includes low-temperature receiver and cooling pump, and described low-temperature receiver is in parallel with Residual heat removal cooler, and described cooling system is included altogether
Active and passive two loops with import piping, low-temperature receiver and outlet piping.
Compared with prior art, the positive effect of the present invention is:
(1) reactor in the present invention and primary Ioops system, residual heat removal system and cooling system three subsystems are simultaneously
Connection connects it is not necessary to increase device configuration, by pump valve simple operationss, just can break in nominal situation, shutdown condition and universe
Switchover operation under the different operating mode of three kinds of electrification operating mode.
(2) main pump of reactor and primary Ioops system is contactless pump, can at utmost reduce loop flow resistance,
Have the advantages that under nominal situation and shutdown condition save electric power energy, have under accident conditions increase natural circulation flow,
Improving residual heat of nuclear core derives the effect of ability；Main pump and main check valve unitary design, can shorten main pipeline length, realize
Close-coupled is arranged；Main pump has top gear and two operational tapses of low or first gear, and nominal situation uses top gear, and shutdown condition uses
By main pump gear switch, low or first gear, achieves that system conditions switch.
(3) the Residual heat removal cooler in residual heat removal system is in parallel with steam generator, and its inlet tube is from steam generation
Device entrance is drawn, and after Residual heat removal cooler, accesses main pump entrance by outlet, this flow process is not only suitable for active waste heat
Discharge system, can be suitably used for Heat Discharging System of Chinese again, it is achieved thereby that active residual heat removal system and passive residual heat
Discharge system blends.In the case of opening residual heat removal system outlet valve, putting into residual heat removal system, if main pump is using low
During fast shelves, then system is run under shutdown condition；If there is universe loss of power accident main pump stall, system is under accident conditions
Run；It is not required to increase device configuration so that it may be automatically performed operating condition switching.
(4) low-temperature receiver in cooling system can be residing for the head-tank of nuclear power plant or naval nuclear power plant
Briny environment.Cooling pump be contactless pump, can at utmost reduce loop flow resistance, can forced circulation and from
So circulate and run it is achieved that active cooling system and passive cooling system blend under two kinds of operating modes.Put into cooling system
In the case of, if enable cooling pump, system is run under shutdown condition；If there is universe loss of power accident cooling pump stall
When, then system is run under accident conditions；It is not required to increase device configuration so that it may be automatically performed operating condition switching.
(5) in normal conditions, main pump operates in top gear, and residual heat removal system outlet valve cuts out, and cooling pump is in stops
Turn state, through steam generator, deriving does work to secondary circuit generates electricity reactor core heat；Under shutdown condition, main pump is transported in low or first gear
Turn, residual heat removal system outlet valve is opened, cooling pump is opened, residual heat removal system and cooling system set up forced circulation respectively,
Residual heat of nuclear core, through Residual heat removal cooler, is derived to cooling system with enabling fashion；Under universe loss of power accident operating mode, main pump stops
Turn, cooling pump stall, Natural Circulation set up respectively by residual heat removal system and cooling system, residual heat of nuclear core cools down through Residual heat removal
Device, is derived to cooling system in passive mode.
Brief description
Examples of the present invention will be described by way of reference to the accompanying drawings, wherein:
Fig. 1 is active and the passive residual heat of nuclear core guiding system flow chart blending.
Specific embodiment
As shown in figure 1, active with the passive residual heat of nuclear core guiding system blending, by reactor and primary Ioops system,
Residual heat removal system and cooling system three subsystems compose in parallel.Active with the passive residual heat of nuclear core guiding system blending
Contain two loops.
As shown in figure 1, reactor and primary Ioops system are by reactor 1, manostat 2, main pipeline inlet valve 3, steam generation
Device 4, main pump and main check valve 5, main pipeline outlet valve 6 and pipeline composition；Main pump is the contactless pumps such as electromagnetic pump, main check valve
For swing check valve, positioned at main pump outlet end, both adopt unitary design to main check valve, have top gear and low or first gear two
Individual operational tapses.Residual heat removal system is by residual heat removal system inlet valve 7, Residual heat removal cooler 8, residual heat removal system outlet
Valve 9 and pipeline composition；Residual heat removal system inlet tube is drawn from steam generator 4 entrance, after Residual heat removal cooler 8,
Its outlet accesses main pump entrance, and active residual heat removal system and Heat Discharging System of Chinese have shared import piping, remaining
Heat discharges cooler 8 and outlet piping.Cooling system is gone out by cooling system inlet valve 10, low-temperature receiver 11, cooling pump 12, cooling system
Mouth valve 13 and pipeline composition；Low-temperature receiver 11 is in parallel with Residual heat removal cooler 8, and cooling pump adopts the contactless pumps such as electromagnetic pump, energy
Dynamic cooling system and passive cooling system common inlet piping, low-temperature receiver 11 and outlet piping.
As shown in figure 1, in normal conditions, main pump 5 operates in top gear, drives reactor coolant to flow successively through reaction
Heap 1, inlet tube, main pipeline inlet valve 3, steam generator 4, outlet, main pump and main check valve 5, main pipeline inlet valve 6, warp
Cross above-mentioned flow process, reactor core heat derives to secondary circuit through steam generator 4, and driving steam turbine acting generates electricity.Under shutdown condition,
Main pump 5 operates in low or first gear, and residual heat removal system outlet valve 9 opens, and cooling pump 12 is opened, main pump drive reactor coolant according to
Secondary flow through residual heat removal system inlet tube, residual heat removal system inlet valve 7, Residual heat removal cooler 8, residual heat removal system outlet
Pipe, residual heat removal system outlet valve 9, cooling pump 12 drives cooling water flow cooling system inlet tube, cooling system inlet valve successively
10th, low-temperature receiver 11, cooling system outlet, cooling pump 12, cooling system outlet valve 13, through above-mentioned flow process, residual heat of nuclear core is through remaining
Heat discharges cooler 8, with active derivation to cooling system.Under universe loss of power accident operating mode, main pump 5 stall, cooling pump 12 is stopped
Turn, now residual heat removal system and cooling system Density-Dependent difference and difference in height all can set up Natural Circulation, and reactor cools down
Agent is identical with shutdown condition with the flow process of cooling water, and residual heat of nuclear core, through Residual heat removal cooler 8, is derived to cooling system with passive
System.
According to above-mentioned specific embodiment it is found that active residual heat removal system and Heat Discharging System of Chinese are realized
Merge, active cooling system and passive cooling system also achieve fusion, do not increase device configuration, only pass through pump valve simple
Single operation, just can run under nominal situation, three kinds of different operating modes of shutdown condition and universe loss of power accident operating mode.
The operation principle of the present invention is: the present invention is by reactor and primary Ioops system, residual heat removal system and cooling system
Three subsystems compose in parallel it is not necessary to increase device configuration, by pump valve simple operationss, just can be in nominal situation, shutdown
Switchover operation under three kinds of different operating modes of operating mode and universe loss of power accident operating mode.In normal conditions, main pump operates in top gear, remaining
Hot discharge system outlet valve 9 cuts out, and cooling pump 12 is in stop state, and reactor core heat derives through steam generator and does to secondary circuit
Work(generates electricity；Under shutdown condition, main pump operates in low or first gear, and residual heat removal system outlet valve 9 is opened, and cooling pump 12 is opened, heap
Core waste heat is derived to cooling system with enabling fashion through Residual heat removal cooler；Under universe loss of power accident operating mode, main pump stall,
Cooling pump stall, residual heat of nuclear core is derived to cooling system in passive mode through Residual heat removal cooler.
Claims (9)
1. a kind of active with the passive residual heat of nuclear core guiding system blending it is characterised in that: include the reaction being arranged in parallel
Heap and primary Ioops system, residual heat removal system and cooling system three subsystems；Described reactor and primary Ioops system include according to
The main pump of secondary connection, reactor and steam generator；The inlet tube of described residual heat removal system draws from steam generator entrance
Go out, after Residual heat removal cooler, its outlet accesses main pump entrance, and described residual heat removal system includes common inlet pipe
Active and passive two loops of system, Residual heat removal cooler and outlet piping；Described cooling system includes low-temperature receiver and cooling
Pump, described low-temperature receiver is in parallel with Residual heat removal cooler, and described cooling system includes common inlet piping, low-temperature receiver and outlet piping
Active and passive two loops.
2. according to claim 1 active with the passive residual heat of nuclear core guiding system blending it is characterised in that: described
Main pump is contactless pump, has top gear and two operational tapses of low or first gear.
3. according to claim 2 active with the passive residual heat of nuclear core guiding system blending it is characterised in that: remaining
Heat is discharged and is arranged residual heat removal system outlet valve between the outlet of cooler and main pump.
4. according to claim 3 active with the passive residual heat of nuclear core guiding system blending it is characterised in that: just
Often under operating mode, main pump operates in top gear, and residual heat removal system outlet valve cuts out, and cooling pump is in stop state, reactor core heat
Derive to do work to secondary circuit through steam generator and generate electricity.
5. according to claim 3 active with the passive residual heat of nuclear core guiding system blending it is characterised in that: stopping
Under heap operating mode, main pump operates in low or first gear, and residual heat removal system outlet valve is opened, and cooling pump is opened, residual heat removal system and cold
But system sets up forced circulation respectively, and residual heat of nuclear core is derived to cooling system with enabling fashion through Residual heat removal cooler.
6. according to claim 3 active with the passive residual heat of nuclear core guiding system blending it is characterised in that: complete
Under the loss of power accident operating mode of domain, main pump stall, cooling pump stall, residual heat removal system and cooling system set up Natural Circulation respectively,
Residual heat of nuclear core is derived to cooling system in passive mode through Residual heat removal cooler.
7. according to claim 2 active with the passive residual heat of nuclear core guiding system blending it is characterised in that: in institute
State main pump outlet end setting main check valve.
8. according to claim 7 active with the passive residual heat of nuclear core guiding system blending it is characterised in that: described
Main check valve is swing check valve, and described main pump and main check valve adopt integral type to arrange.
9. according to claim 1 active with the passive residual heat of nuclear core guiding system blending it is characterised in that: described
Cooling pump is contactless pump.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610866600.5A CN106373622A (en) | 2016-09-30 | 2016-09-30 | Active-and-passive-fusion reactor-core waste-heat leading-out system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610866600.5A CN106373622A (en) | 2016-09-30 | 2016-09-30 | Active-and-passive-fusion reactor-core waste-heat leading-out system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN106373622A true CN106373622A (en) | 2017-02-01 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610866600.5A Pending CN106373622A (en) | 2016-09-30 | 2016-09-30 | Active-and-passive-fusion reactor-core waste-heat leading-out system |
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| CN (1) | CN106373622A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107845434A (en) * | 2017-10-27 | 2018-03-27 | 中国核电工程有限公司 | A kind of passive reactor core auxiliary coolant system |
| CN111710446A (en) * | 2020-06-23 | 2020-09-25 | 中国核动力研究设计院 | System for discharging reactor core waste heat and thermoelectric heat exchanger for discharging reactor core waste heat |
| CN113299417A (en) * | 2021-05-25 | 2021-08-24 | 中国核动力研究设计院 | Safety injection triggering method, device and system for nuclear power plant under shutdown condition during operation of main pump |
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| CN104733060A (en) * | 2015-03-25 | 2015-06-24 | 东南大学 | Passive residual heat removal system of marine nuclear power device |
| EP2911156A1 (en) * | 2014-02-21 | 2015-08-26 | AREVA GmbH | Decay heat removal system for a pressurized water reactor and corresponding pressurized water reactor |
| CN204614459U (en) * | 2014-12-29 | 2015-09-02 | 国核华清（北京）核电技术研发中心有限公司 | A kind of non-active nuclear power station pressure release condensation heat exchange system |
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| CN102903403A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Active and non-active combined core water injection heat lead-out device |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107845434A (en) * | 2017-10-27 | 2018-03-27 | 中国核电工程有限公司 | A kind of passive reactor core auxiliary coolant system |
| CN107845434B (en) * | 2017-10-27 | 2022-03-04 | 中国核电工程有限公司 | Reactor core auxiliary cooling system of passive reactor |
| CN111710446A (en) * | 2020-06-23 | 2020-09-25 | 中国核动力研究设计院 | System for discharging reactor core waste heat and thermoelectric heat exchanger for discharging reactor core waste heat |
| CN113299417A (en) * | 2021-05-25 | 2021-08-24 | 中国核动力研究设计院 | Safety injection triggering method, device and system for nuclear power plant under shutdown condition during operation of main pump |
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Application publication date: 20170201 |
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