CN109903863A - A kind of safety injection system and nuclear power system - Google Patents
A kind of safety injection system and nuclear power system Download PDFInfo
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- CN109903863A CN109903863A CN201711309416.1A CN201711309416A CN109903863A CN 109903863 A CN109903863 A CN 109903863A CN 201711309416 A CN201711309416 A CN 201711309416A CN 109903863 A CN109903863 A CN 109903863A
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- 238000002347 injection Methods 0.000 title claims abstract description 166
- 239000007924 injection Substances 0.000 title claims abstract description 166
- 239000002826 coolant Substances 0.000 claims abstract description 57
- 230000001960 triggered effect Effects 0.000 claims abstract description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 39
- 239000000941 radioactive substance Substances 0.000 abstract description 2
- 238000001816 cooling Methods 0.000 description 7
- 230000003020 moisturizing effect Effects 0.000 description 6
- 239000000446 fuel Substances 0.000 description 5
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 4
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 4
- 229910052796 boron Inorganic materials 0.000 description 4
- 230000005574 cross-species transmission Effects 0.000 description 4
- 230000002285 radioactive effect Effects 0.000 description 4
- 238000011084 recovery Methods 0.000 description 4
- 238000004781 supercooling Methods 0.000 description 4
- 239000002918 waste heat Substances 0.000 description 4
- 230000007774 longterm Effects 0.000 description 3
- 238000006424 Flood reaction Methods 0.000 description 2
- 230000006837 decompression Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 229910052757 nitrogen Inorganic materials 0.000 description 2
- 238000004064 recycling Methods 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- 230000000630 rising effect Effects 0.000 description 2
- 239000000243 solution Substances 0.000 description 2
- 238000010025 steaming Methods 0.000 description 2
- 239000013589 supplement Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 238000002425 crystallisation Methods 0.000 description 1
- 230000008025 crystallization Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000002045 lasting effect Effects 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The embodiment of the invention provides a kind of safety injection system and nuclear power system, safety injection system includes: Core makeup tank, safety injection tank, safety injection pump and secondary circuit pressure relief device；The first interface of the first interface of Core makeup tank, the first interface of safety injection pump and safety injection tank is connected to cold tube section respectively, the second interface of Core makeup tank and the third orifice of steam generator；Secondary circuit pressure relief device passes through the 4th orifice of jet chimney and steam generator；When safety signal is triggered, the first coolant is injected into pressure vessel by Core makeup tank by cold tube section；When the pressure of primary Ioops is lower than pressure at the top of safety injection tank, the second coolant is injected into pressure vessel by safety injection tank by cold tube section；And/or when the pressure of primary Ioops is lower than first predetermined value, third coolant is injected into pressure vessel by safety injection pump.The safety injection system and nuclear power system reduce the release of radioactive substance, and the power plant after being conducive to cut class accident restores.
Description
Technical field
The present invention relates to npp safety facilities design field, in particular to a kind of safety injection system and nuclear power system.
Background technique
There are many existing safety injection systems, and existing safety injection system includes: the injection of AP1000 non-passive safety
The safety injection system of system (Passive Core Cooling System, PXS), CPR1000 safety injection system and EPR
Deng.
Wherein, AP1000 passive safety injection system include: Core makeup tank, safety injection tank (Accumulators,
ACC), material-changing water tank built in containment (In-containment Refueling Water Storage Tank, IRWST) with
And passive residual heat removal heat exchanger.Meanwhile the Automatic Depressurization System valve and sprinkler of a part as primary Ioops
It is equally the critical function component part of PXS.In minor break accident, initial stage Core makeup tank is to reactor core moisturizing, but primary Ioops
Insufficient pressure is to be down to the injection pressure of ACC, IRWST.As primary Ioops automatically unloading system starts, pacify note after primary Ioops decompression
The relatively new water filling of case, long periods then provide peace note by the water from IRWST.In large break accident, safety injection tank is provided down
Drop section ring cavity floods again is partially flooded with peace beam amount required for condition with reactor core.Subsequent IRWST provides peace note, final to establish peace
Full shell effluent recycling to realize long-term cooling.But after there is generation minor break accident in AP1000 passive safety injection system
It will lead to the radioactive coolant of primary Ioops band largely to enter in containment and the problem of accident recovery difficulty.
CPR1000 safety injection system injects by high-voltage safety, safety injection tank and low-voltage safety injected system totally three subsystems
System composition.Under minor break accident, start high pressure safety injection system to primary Ioops moisturizing, to re-establish voltage-stablizer water level；?
In middle cut accident, high-pressure safety injection injected system and safety injection tank starting, to guarantee that primary Ioops coolant floods fuel always；Big
Under cut accident, mainly it is respectively started by safety injection tank and low-voltage safety injected system to reactor core water filling, to flood again and cold
But reactor core limits the rising of fuel element temperature.But the error safety injection accident that existing CPR1000 safety injection system may cause
And damaged steam generator spill-over under SGTR accident.
EPR safety injection system is made of middle pressure safety injection system, low head injection system and safety injection tank, wherein low head injection system
Same set of system is shared with waste heat guiding system.Under minor break accident, by the steam atmosphere release device release of secondary circuit, make
After obtaining primary Ioops decrease temperature and pressure, press safety injection system to primary Ioops moisturizing in starting, to re-establish voltage-stablizer water level；Big
Under cut accident, safety injection tank, middle pressure safety injection system and low head injection system are respectively started to reactor core and fill the water, to flood again and cold
But reactor core limits the rising of fuel element temperature.In the safe shutdown stage, low head injection system starts waste heat exported schema, can
Realize residual heat of nuclear core export and unit recession.
Summary of the invention
The embodiment of the invention provides a kind of safety injection system and nuclear power systems, it can be ensured that after minor break accident occurs
Peace note can inject in time, while avoiding will lead to the radioactive coolant of primary Ioops band after minor break accident occurs and largely enter
In containment and the problem of accident recovery difficulty.
In order to solve the above-mentioned technical problem, the embodiment of the invention provides a kind of safety injection systems, are applied to nuclear power system
System, the nuclear power system includes: primary Ioops and secondary circuit；The primary Ioops include: steam generator, main pump, cold tube section and heat
Pipeline section；The first interface of the main pump is connected to by the cold tube section with the first interface of pressure vessel, the steam generator
First interface be connected to by the hot pipe section with the second interface of the pressure vessel, the second interface of the steam generator
It is connected to the second interface of the main pump；The secondary circuit includes: jet chimney, the steam generator and the jet chimney
First interface connection, the safety injection system include: Core makeup tank, safety injection tank, safety injection pump and for nuclear power system send out
The secondary circuit pressure relief device being depressured when raw cut accident to secondary circuit；Wherein,
The first interface of the first interface of the Core makeup tank, the first interface of the safety injection pump and the safety injection tank
It is connected to respectively with the cold tube section, the third orifice of the second interface of the Core makeup tank and the steam generator；
The secondary circuit pressure relief device passes through the 4th orifice of the jet chimney and the steam generator；
When safety signal is triggered, the Core makeup tank injects the first coolant of storage by the cold tube section
Into the pressure vessel；When the pressure of the primary Ioops is lower than pressure at the top of the safety injection tank, the safety injection tank will be deposited
Second coolant of storage is injected into the pressure vessel by the cold tube section；And/or when the pressure of the primary Ioops is lower than
When first predetermined value, third coolant is injected into the pressure vessel by the safety injection pump.
Optionally, the first interface of the Core makeup tank is connected to the first interface of the first valve member, and described first
The connection of cold tube section described in the second interface of valve member.
Optionally, the second interface of the Core makeup tank is connected to the first interface of first check-valve, and described first stops
The second interface for returning valve is connected to the first interface of the second valve member, the second interface and the steaming of second valve member
The third orifice of vapour generator.
Optionally, the first interface of the safety injection tank is connected to the first interface of isolating valve, and the second of the isolating valve connects
Mouth is connected to the first interface of second check-valve, and the second interface of the second check-valve is connected to the cold tube section.
Optionally, the secondary circuit pressure relief device includes: steam control valve and steam control valve；The steam generator
4th interface is connected to the first interface of steam control valve, and the first of the second interface of the steam control valve and steam control valve
The second interface of orifice, the steam control valve is connected to secondary circuit pressure relief device；When the water level of Core makeup tank is lower than
First watermark threshold, steam control valve are opened, adjust the aperture of steam control valve, make the pressure of secondary circuit according to scheduled pressure
Curve reduces.
Optionally, the first interface of the safety injection pump is connected to the first interface of heat exchanger, and the of the heat exchanger
Two interfaces are connected to the first interface of third valve member, and the second interface and the cold tube section of the third valve member connect
It is logical；The second interface of the third valve member is connected by the 4th valve member with the hot pipe section.
Optionally, the second interface of the safety injection pump is connected to the first interface of the 5th valve member, the 5th valve
The second interface of component is connected to the first interface of the first interface of the 6th valve member and the 7th valve member respectively, and described
The second interface of six valve members is connected to material-changing water tank, and the second interface of the 7th valve member is connected to melt pit；
When the water level of material-changing water tank is lower than the second watermark threshold, closes the 6th valve member and open the 7th valve
The source of third coolant is switched to melt pit from material-changing water tank by component.
Optionally, the steam generator, the main pump, the pressure vessel, the Core makeup tank and peace note
Case is located in the containment of hollow structure, and the safety injection pump is located at outside the containment.
Optionally, the safety injection system further include: safety valve, the first interface of the safety valve respectively with the steaming
4th interface of vapour generator is connected to the first interface of the steam control valve.
The embodiment of the invention also provides a kind of nuclear power system, including the first circuit and second servo loop, the nuclear power systems
Further include: safety injection system as described above, the first interface of the Core makeup tank, the safety injection pump first interface with
And the first interface of the safety injection tank is connected to the cold tube section of the primary Ioops respectively, the second interface of the Core makeup tank with
The third orifice of the steam generator of the primary Ioops；The secondary circuit pressure relief device passes through the steam pipe of the secondary circuit
4th orifice of the steam generator of road and the primary Ioops.
The embodiment of the present invention has the following beneficial effects:
In embodiments of the present invention, secondary circuit pressure relief device, Core makeup tank, safety injection tank, safety injection pump and corresponding are utilized
Pipeline and valve form the safety injection system of secondary circuit buck, to ensure that primary Ioops can be fast under nuclear power plant's loss of-coolant accident (LOCA)
Fast release provides enough coolants to primary Ioops, and reactor core is preferably cooled down under guarantee accident, limits fuel element temperature
Rise.The safety injection system can supplement B solution to primary Ioops in primary Ioops supercooling accident simultaneously, maintain reactor core
It is critical.It can effectively be infused ensuring that primary Ioops are depressurized to safety injection tank and safety injection pump in the case where not losing primary Ioops coolant more
The pressure entered.In the case where LOCA class accident, primary Ioops supercooling accident occur for reactor, which can guarantee that reactor core decays
Continuous and effective discharge in hot certain time, until nuclear power plant enters safe condition.
Relative to CPR1000 safety injection system, the safety injection system of the embodiment of the present invention prevents the mistake that may cause
Pacify damaged steam generator spill-over under note accident and SGTR accident, avoid high-pressure safety injection pump execute peace note and on fill function；Relatively
In AP1000 safety injection system, the safety injection system of the embodiment of the present invention is avoided artificially to be made after minor break accident occurs
At large break, the radioactive coolant of primary Ioops band is caused largely to enter in containment, accident recovery is difficult；Pacify relative to EPR
Full injected system, the safety injection system of the embodiment of the present invention is using passive reactor core hutch water device instead of pressing in active component
Safety injection pump improves the reliability and economy of system.
Detailed description of the invention
Fig. 1 is a kind of safety injection system schematic diagram provided in an embodiment of the present invention；
Fig. 2 is a kind of drawdown curve schematic diagram provided in an embodiment of the present invention.
Specific embodiment
In order to make the object, technical scheme and advantages of the embodiment of the invention clearer, below in conjunction with the embodiment of the present invention
In attached drawing, technical scheme in the embodiment of the invention is clearly and completely described, it is clear that described embodiment is
A part of the embodiment of the present invention, instead of all the embodiments.The present invention being usually described and illustrated herein in the accompanying drawings is implemented
The component of example can be arranged and be designed with a variety of different configurations.
Therefore, the detailed description of the embodiment of the present invention provided in the accompanying drawings is not intended to limit below claimed
The scope of the present invention, but be merely representative of selected embodiment of the invention.Based on the embodiments of the present invention, this field is common
Technical staff's every other embodiment obtained without creative efforts belongs to the model that the present invention protects
It encloses.
It should also be noted that similar label and letter indicate similar terms in following attached drawing, therefore, once a certain Xiang Yi
It is defined in a attached drawing, does not then need that it is further defined and explained in subsequent attached drawing.
In the description of the present invention, it should be noted that term " center ", "upper", "lower", "left", "right", "inner",
The orientation or positional relationship of the instructions such as "outside" be based on the orientation or positional relationship shown in the drawings or the invention product use
When the orientation or positional relationship usually put, be merely for convenience of description of the present invention and simplification of the description, rather than indication or suggestion
Signified device or element must have a particular orientation, be constructed and operated in a specific orientation, therefore should not be understood as to this
The limitation of invention.In addition, term " first ", " second ", " third " etc. are only used for distinguishing description, and it should not be understood as instruction or dark
Show relative importance.
In the description of the present invention, it is also necessary to which explanation is unless specifically defined or limited otherwise, term " setting ",
" installation ", " coupling ", " connection " shall be understood in a broad sense, for example, it may be fixedly connected, may be a detachable connection or one
Connect to body；It can be mechanical connection, be also possible to be electrically connected；It can be directly connected, it can also be indirect by intermediary
It is connected, can be the connection inside two elements.For the ordinary skill in the art, on being understood with concrete condition
State the concrete meaning of term in the present invention.
The embodiment of the invention provides a kind of safety injection system, the safety injection system is applied to nuclear power system, institute
State the PWR nuclear power plant that safety injection system is applicable to 600,000 kilowatts~2,000,000 kilowatts (electrical power) ranks, presurized water reactor core
Power plant generally configures the safety injection system of 2~4 sets of embodiment of the present invention, is certainly not limited to this.
Shown in Figure 1, the nuclear power system includes: safety injection system, primary Ioops and secondary circuit；The primary Ioops packet
It includes: steam generator 11, main pump 12, cold tube section 14 and hot pipe section 15；The steam generator 11 is three big equipment in nuclear island
One of, the steam generator 11 is the boundary of primary Ioops and secondary circuit, and the steam generator 11 is for passing through the pressure
The heat that container 13 (or being reactor) generates is sent out to generate steam by the Steam Actuation steam turbine generator of generation
Electricity.The main pump 12 is for driving coolant in the pump of reactor coolant loop internal circulation flow.Pressure vessel 13 is for pacifying
It sets nuclear reactor 131 and bears the closed container of its huge operating pressure.The cold tube section 14 is for being connected to the main pump
12 and the pressure vessel 13, the hot pipe section 15 is for being connected to the steam generator 11 and the pressure vessel 13.
In embodiments of the present invention, the first interface of the main pump 12 passes through the cold tube section 14 and the pressure vessel 13
First interface connection, the first interface of the steam generator 11 pass through the hot pipe section 15 and the pressure vessel 13 the
Two orifices, the second interface of the steam generator 11 are connected to the second interface of the main pump 12.With continued reference to Fig. 1,
The secondary circuit includes: jet chimney 41, and the steam generator 11 is connected to the first interface of the jet chimney 41；Except this
Except, the secondary circuit further include: steam header (does not regard out) in figure.The second interface and steam header of the jet chimney 41
First interface be connected.
With continued reference to Fig. 1, the safety injection system includes: Core makeup tank 21, safety injection tank 22, safety injection pump 23 and two times
Road pressure relief device 38, the Core makeup tank 21, the safety injection tank 22 and the safety injection pump 23 are used to the pressure vessel
13 provide coolant, such as boron water.The Core makeup tank 21 is the cylindrical container of ball end socket, and inside is full of coolant.
The top of the safety injection tank 22 can be 4.5MPa~5MPa or so filled with the nitrogen of scheduled pressure value, the scheduled pressure value, together
Shi Suoshu safety injection tank 22 is also the container for storing coolant.The secondary circuit pressure relief device 38 is used for nuclear power system
It is depressured when cut accident to secondary circuit.
Wherein, the first interface of the Core makeup tank 21, the first interface of the safety injection pump 23 and the safety injection tank
22 first interface is connected to the cold tube section 14 respectively, the second interface of the Core makeup tank 21 and the steam generator
11 third orifice；The secondary circuit pressure relief device passes through the 4th interface of the jet chimney and the steam generator
Connection.The steam generator 11, the main pump 12, the pressure vessel 13, the Core makeup tank and the safety injection tank point
Wei Yu not be in the containment 16 of hollow structure, the safety injection pump is located at outside the containment 16.It is described when safety signal triggering
First coolant of storage is injected into the pressure vessel 13 by Core makeup tank 21 by the cold tube section 14；When described one
When the pressure in circuit is lower than the pressure at 22 top of safety injection tank, the safety injection tank 22 passes through the second coolant of storage described
Cold tube section 14 is injected into the pressure vessel 13；It is described and/or when the pressure of the primary Ioops is lower than first predetermined value
Third coolant is injected into the pressure vessel 13 by safety injection pump 23.
In embodiments of the present invention, the safety signal can be voltage-stablizer pressure low signal, the triggering of the safety signal
Condition can be lower than second predetermined value for the pressure of primary Ioops, it should be noted that not specific in embodiments of the present invention to limit
The trigger condition of the form of the safety signal and the safety signal.
In embodiments of the present invention, by the Core makeup tank 21, safety injection tank 22 and safety injection pump 23 respectively with primary Ioops
Cooperation, while in accident process, secondary circuit pressure relief device is depressured secondary circuit, to ensure that the pressure of primary Ioops can make to pacify
Note pump continues to be efficiently injected into coolant to primary Ioops, reduces the release of radioactive substance, the electricity after being conducive to minor break accident
Factory restores, and improves the availability of unit.Also, the safety injection system of the embodiment of the present invention is relative to existing Safety Injection
System simplifies safety injection system under the premise of ensuring npp safety, reduces the active equipment of safety level, can larger journey
Degree reduces the construction and O&M cost of nuclear power plant, advantageously reduces the risk of piping failure, reduces human error, improves core
Economy of power plant；Meanwhile the safety injection system of the embodiment of the present invention also helps and avoids steam under error safety injection and SGTR accident
11 spill-over of generator.
In embodiments of the present invention, secondary circuit pressure relief device, Core makeup tank, safety injection tank, safety injection pump and corresponding are utilized
Pipeline and valve form the safety injection system of secondary circuit buck, to ensure that primary Ioops can be fast under nuclear power plant's loss of-coolant accident (LOCA)
Fast release provides enough coolants to primary Ioops, and reactor core is preferably cooled down under guarantee accident, limits fuel element temperature
Rise.B solution is supplemented to primary Ioops in primary Ioops supercooling accident simultaneously, maintains reactor core subcritical.Ensuring not more
It loses primary Ioops are depressurized to safety injection tank and safety injection pump can be efficiently injected into pressure in the case where primary Ioops coolant.In reactor
Occur under LOCA class accident, primary Ioops supercooling accident, which can guarantee holding in reactor core decay heat certain time
Continuous effectively discharge, until nuclear power plant enters safe condition.
Relative to CPR1000 safety injection system, the safety injection system of the embodiment of the present invention, which prevents, be may cause
Damaged steam generator spill-over under error safety injection accident and SGTR accident, avoid high-pressure safety injection pump execute peace note and on fill function；Phase
For AP1000 safety injection system, the safety injection system of the embodiment of the present invention is avoided to be thought after minor break accident occurs
Large break is caused, the radioactive coolant of primary Ioops band is caused largely to enter in containment, accident recovery is difficult；Relative to EPR
Safety injection system, the safety injection system of the embodiment of the present invention is using passive reactor core hutch water device instead of in active component
Safety injection pump is pressed, the reliability of system is improved.Optionally, the first interface of the Core makeup tank 21 and the first valve member 24
First interface connection, cold tube section 14 described in the second interface of first valve member 24 is connected to.First valve member
24 can be a valve or multiple valves with serial or parallel connection.For example, first valve member 24 wraps with continued reference to Fig. 1
The first valve is included, the first interface of the Core makeup tank 21 is connected to the first interface of the first valve, first valve
The connection of cold tube section 14 described in second interface.It should be noted that not limiting first valve specifically in embodiments of the present invention
The structure of door component 24.
Optionally, the second interface of the Core makeup tank 21 is connected to the first interface of first check-valve 25, and described
The second interface of one check-valves 25 is connected to the first interface of the second valve member 26, and the second of second valve member 26 connects
The third orifice of mouth and the steam generator 11.Second valve member 26 can be for a valve or with series connection or simultaneously
Multiple valves of connection.For example, second valve member 26 includes the second valve 261 and third valve in parallel with continued reference to Fig. 1
Door 262, the second interface of the first check-valve 25 respectively with the first interface of second valve 261 and the third valve
262 first interface connection, the second interface of the second interface of second valve 261 and the third valve 262 is and institute
The third orifice of steam generator 11 is stated, if one of them can damage in the second valve 261 or third valve 262 in this way
In the case where bad, guarantee the normal work of the safety injection system by another valve.It should be noted that at this
The structure of second valve member 26 is not limited in inventive embodiments specifically.
Specifically, the upper end of the Core makeup tank 21 is connected to the cold tube section of primary Ioops by pressure balance suction line
At 14 low pressure peace note decanting point, lower end is connected to 11 outlet chamber of steam generator by injecting outlet line.The cold pipe
Section 14 is normally opened, so that Core makeup tank 21 be maintained to be in the pressure of primary Ioops.After safety signal is triggered, it is located at reactor core
The second valve 261 and third valve 262 of 21 outlet line of water supply tank are opened, and connect Core makeup tank 21 and primary Ioops, heap
Core water supply tank 21 is automatically injected primary Ioops by injection pipeline pressure difference and the difference in height of itself, the coolant stored up and down
In.
With continued reference to Fig. 1, optionally, the first interface of the safety injection tank 22 is connected to the first interface of isolating valve 27, institute
The second interface for stating isolating valve 27 is connected to the first interface of second check-valve 30, the second interface of the second check-valve 30 with
The cold tube section 14 is connected to.
Specifically, the first interface of the safety injection tank 22 is pacified note injection pipeline by low pressure and is connected to the cold tube section 14.
When nitrogen pressure of the pressure of primary Ioops lower than 22 top of safety injection tank, coolant passes through upper and lower in the safety injection tank 22
Pressure difference coolant is rapidly injected in the pressure vessel 13 by cold tube section 14.In large-break LOCA, peace
The coolant that note case 22 injects can quickly flood the active section of 13 lower chambers of pressure vessel and part reactor core 131.
With continued reference to Fig. 1, the secondary circuit pressure relief device 38 includes: steam control valve 28 and steam control valve 29；It is described
4th interface of steam generator 11 is connected to the first interface of steam control valve 28, the second interface of the steam control valve 28
It is connected to the first interface of steam control valve 29, the second interface and secondary circuit pressure relief device 38 of the steam control valve 29 connect
It is logical.
It should be noted that under normal circumstances, steam control valve 28 remains off.When the water level of Core makeup tank 21
Lower than the first watermark threshold, 21 water level low signal of Core makeup tank is triggered, and steam control valve 28 is opened, and steam control valve 29 is not
Disconnected adjustment aperture, reduces secondary circuit pressure according to scheduled pressure curve, so that the temperature and pressure of primary Ioops
It reduces simultaneously, the pressure reduction of primary Ioops is finally made to be efficiently injected into pressure head to low-voltage safety injected system, it is ensured that one time
The sufficient coolant of road injection.Wherein, the scheduled pressure curve can be curve shown in Fig. 2, be of course not solely limited to this.
Optionally, the first interface of the safety injection pump 23 is connected to the first interface of heat exchanger 31, the heat exchanger
31 second interface is connected to the first interface of third valve member 32, the second interface of the third valve member 32 with it is described
Cold tube section 14 is connected to.It should be noted that the third valve member 32 can be for a valve or with the multiple of serial or parallel connection
Valve.For example, the third valve member 32 includes the 4th valve, the second interface of the heat exchanger 31 with continued reference to Fig. 1
It is connected to the first interface of the 4th valve, the second interface of the 4th valve is connected to the cold tube section 14.It needs to illustrate
It is not limit the structure of the third valve member 32 specifically in embodiments of the present invention.
It is sustainable to primary Ioops injection and core deluge and Residual heat removal by the safety injection pump 23 under low backpressure condition
It is required that the coolant of flow is adapted, to ensure the lasting moisturizing ability of coolant loss post incident.After safe shutdown
Or the long periods in coolant loss accident, waste heat can also be discharged by the heat exchanger 31, recycled in melt pit 40
The heat of coolant can be transferred to component cooling water system, to prevent melt pit 40 from recycling the coolant temperature mistake in stage
It is high.
It should be noted that the low backpressure condition refers to the pressure of the primary Ioops lower than first predetermined value, for example, institute
Stating first predetermined value can be 4MPa.
Optionally, the second interface of the 4th valve is also connected with the hot pipe section 15 by the 4th valve member 33
It is logical.Multiple valves that 4th valve member 33 can connect for a valve or in the form of in parallel or series, for example, continuing to join
See that Fig. 1, the 4th valve member 33 include: the 5th valve 331, the 6th valve 332 and the 7th valve 333 being sequentially connected in series,
The second interface of 4th valve pass through the 5th valve 331, the 6th valve 332 and the 7th valve 333 that are sequentially connected in series also with
The hot pipe section 15 is connected, and is of course not solely limited to this.It should be noted that not specific in embodiments of the present invention limit
The structure of 4th valve member 33.
Optionally, the second interface of the safety injection pump 23 is connected to the first interface of the 5th valve member 34, and the described 5th
The second interface of valve member 34 first interface with the first interface of the 6th valve member 35 and the 7th valve member 36 respectively
Connection, the second interface of the 6th valve member 35 are connected to material-changing water tank 39, and the second of the 7th valve member 36 connects
Mouth is connected to melt pit 40.When the water level of material-changing water tank 39 is lower than the second watermark threshold, the 6th valve member 35 is closed simultaneously
The 7th valve member 36 is opened, the source of third coolant is switched into melt pit 40 from material-changing water tank 39.
For example, with continued reference to Fig. 1, the 5th valve member 34 includes the 7th valve, and the 6th valve member 35 includes the
Eight valves, the 7th valve member 36 include the 9th valve, the second interface of the safety injection pump 23 and the first of the 7th valve
Orifice, the second interface of the 7th valve connect with the first interface of the first interface of the 8th valve and the 9th valve respectively
Logical, the second interface of the 8th valve is connected to material-changing water tank 39, and the second interface of the 9th valve is connected to melt pit 40.
It should be noted that not limiting the 5th valve member 34,35 and of the 6th valve member specifically in embodiments of the present invention
The structure of 7th valve member 36.
It should be noted that first coolant, second coolant and the third coolant can be same
Coolant or different coolants, do not limit specifically in embodiments of the present invention.
Optionally, the safety injection system further include: safety valve 37, the first interface of the safety valve 37 respectively with institute
The 4th interface for stating steam generator 11 is connected to the first interface of the steam control valve 28.
Safety injection system described in embodiment to facilitate the understanding of the present invention, next to the operation of safety injection system
Mode describes in detail.
Under nuclear power plant's normal power operating condition, any subsystem of the safety injection system does not start, but locates
In available mode；After nuclear power plant's unit is dropped back to safe shutdown state, starts heat exchanger 31, pass through the heat exchanger 31
Export residual heat of nuclear core.
If non-LOCA (Loss of Coolant Accident, coolant loss) class accident occurs for nuclear power plant, due to
When the energy increase that non-LOCA class accident causes secondary circuit to be taken away and the reduction of primary Ioops temperature and pressure occur for nuclear power plant, open first
Second valve member 26 is opened, coolant is injected to pressure vessel 13 by Core makeup tank 21, alleviates reactivity transients simultaneously
Enough Shutdown margins are provided.
If minor break accident or SGTR (Steam Generator Tube Rupture, steam in nuclear power plant's generation
11 heat transfer pipe break accident of generator) accident when, first turn on second valve member 26, by Core makeup tank 21 to
Pressure vessel 13 injects coolant, when CMT (Core Makeup Tank, Core makeup tank 21) water level is lower than the second watermark threshold
When, peace note signal is triggered, opens steam control valve 28 at this time, the aperture of steam control valve 29 is controlled, so that the pressure of secondary circuit
It being changed according to curve shown in Fig. 2, the steam atmosphere depressurized system movement executes secondary circuit decompression movement, so that
Primary Ioops cooling and be depressured, and then open third valve member 32, by the safety injection tank 22 and the safety injection pump 23 quickly to
Coolant is injected in the pressure vessel 13, the flow of injection can keep the short-term and long-term cooling of Core cooling.
If nuclear power plant occur large break accident, large break after the accident, the pressure of primary Ioops reduces quickly, first
Second valve member 26 is opened, coolant is injected from trend primary Ioops by Core makeup tank 21 and safety injection tank 22, and mention
For biggish injection flow to fill 13 lower head of pressure vessel, later on third valve member 32 rapidly, while passing through peace
Note pump 23 persistently injects coolant to primary Ioops, to ensure that reactor core obtains continuing cooling.A period of time occurs in large break accident
Afterwards, start the 4th valve member 33, so that the second interface of the 4th valve passes through the 4th valve member 33 and the heat pipe
Section 15 is connected, and realizes that cold tube section 14 and hot pipe section 15 are injected simultaneously, prevents Boron crystallization in the core.When the water level of material-changing water tank 39 is lower than
When third watermark threshold, while closing the 6th valve member 35, and start the 7th valve member 36, peace is filled the water
Source switches to melt pit 40 from material-changing water tank 39, it is ensured that peace note is had abundant water resources.
For the long periods of cut class accident, start heat exchanger 31, by the safety injection system by peace injection-molded
It is switched to Residual heat removal mode, the waste heat of reactor core is discharged by heat exchanger 31, while providing necessary peace by safety injection pump 23
Beam amount.
In embodiments of the present invention, the major function of the safety injection system is to mend in time when accident occurs to primary Ioops
It fills coolant, such as when coolant is boron water, rapidly moisturizing and boron can be mended for primary Ioops, it is ensured that reactor core safety.For non-
Accident is subcooled in the primary Ioops of LOCA, can supplement coolant to primary Ioops in time by the safety injection system, guarantee primary Ioops
Water capacity and Shutdown margin meet safety requirements；For cut class accident, then infused by Core makeup tank 21, peace in temporary stage
Case 22 and the first backward reactor core moisturizing of safety injection pump 23；Residual heat removal function is provided by heat exchanger 31 in long periods, realizes reactor core
It is long-term cooling.
The above is a preferred embodiment of the present invention, it is noted that for those skilled in the art
For, without departing from the principles of the present invention, it can also make several improvements and retouch, these improvements and modifications
It should be regarded as protection scope of the present invention.
Claims (10)
1. a kind of safety injection system is applied to nuclear power system, the nuclear power system includes: primary Ioops and secondary circuit；Described one
Circuit includes: steam generator, main pump, cold tube section and hot pipe section；The first interface of the main pump passes through the cold tube section and pressure
The first interface of force container is connected to, the first interface of the steam generator pass through the hot pipe section and the pressure vessel the
Two orifices, the second interface of the steam generator are connected to the second interface of the main pump；The secondary circuit includes: to steam
Steam pipe road, the steam generator are connected to the first interface of the jet chimney, which is characterized in that the safety injection system
The secondary circuit for including: Core makeup tank, safety injection tank, safety injection pump and being depressured when cut accident occurs for nuclear power system to secondary circuit
Pressure relief device；Wherein,
The first interface of the first interface of the Core makeup tank, the first interface of the safety injection pump and the safety injection tank is distinguished
It is connected to the cold tube section, the third orifice of the second interface of the Core makeup tank and the steam generator；It is described
Secondary circuit pressure relief device passes through the 4th orifice of the jet chimney and the steam generator；
When safety signal is triggered, the first coolant of storage is injected into institute by the cold tube section by the Core makeup tank
It states in pressure vessel；When the pressure of the primary Ioops is lower than pressure at the top of the safety injection tank, the safety injection tank is by storage
Second coolant is injected into the pressure vessel by the cold tube section；And/or when the pressure of the primary Ioops is lower than first
When predetermined value, third coolant is injected into the pressure vessel by the safety injection pump.
2. safety injection system according to claim 1, which is characterized in that the first interface of the Core makeup tank and
The first interface of one valve member is connected to, the connection of cold tube section described in the second interface of first valve member.
3. safety injection system according to claim 1, which is characterized in that the second interface of the Core makeup tank and the
The first interface of one check-valves is connected to, and the second interface of the first check-valve is connected to the first interface of the second valve member,
The second interface of second valve member and the third orifice of the steam generator.
4. safety injection system according to claim 1, which is characterized in that the first interface and isolating valve of the safety injection tank
First interface connection, the second interface of the isolating valve is connected to the first interface of second check-valve, the second check-valve
Second interface be connected to the cold tube section.
5. safety injection system according to claim 1, which is characterized in that the secondary circuit pressure relief device includes: steam
Control valve and steam control valve；
4th interface of the steam generator is connected to the first interface of steam control valve, and the second of the steam control valve connects
Mouth is connected to the first interface of steam control valve, and the second interface of the steam control valve is connected to secondary circuit pressure relief device；
When the water level of Core makeup tank is lower than the first watermark threshold, steam control valve is opened, adjusts the aperture of steam control valve, make
The pressure of secondary circuit is reduced according to scheduled pressure curve.
6. safety injection system according to claim 1, which is characterized in that the first interface of the safety injection pump and heat exchange
The first interface of device is connected to, and the second interface of the heat exchanger is connected to the first interface of third valve member, the third
The second interface of valve member is connected to the cold tube section, and the second interface of the third valve member passes through the 4th valve member
It is connected with the hot pipe section.
7. safety injection system according to claim 1, which is characterized in that the second interface of the safety injection pump and the 5th valve
The first interface of door component is connected to, the second interface of the 5th valve member respectively with the first interface of the 6th valve member and
The first interface of 7th valve member is connected to, and the second interface of the 6th valve member is connected to material-changing water tank, and the described 7th
The second interface of valve member is connected to melt pit；
When the water level of material-changing water tank is lower than the second watermark threshold, closes the 6th valve member and open the 7th valve group
The source of third coolant is switched to melt pit from material-changing water tank by part.
8. safety injection system according to claim 1, which is characterized in that the steam generator, the main pump, described
Pressure vessel, the Core makeup tank and the safety injection tank are located in the containment of hollow structure, and the safety injection pump is located at
Outside the containment.
9. safety injection system according to claim 1, which is characterized in that the safety injection system further include: safety
Valve, the first interface of the safety valve connect with the first of the 4th interface of the steam generator and the steam control valve respectively
Mouth connection.
10. a kind of nuclear power system, including primary Ioops and secondary circuit, which is characterized in that the nuclear power system further include: as right is wanted
Seek 1~9 described in any item safety injection systems；
The first interface of the first interface of the Core makeup tank, the first interface of the safety injection pump and the safety injection tank is distinguished
It is connected to the cold tube section of the primary Ioops, the of the steam generator of the second interface of the Core makeup tank and the primary Ioops
Three orifices；The secondary circuit pressure relief device passes through the jet chimney of the secondary circuit and the steam generator of the primary Ioops
The 4th orifice.
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110689973A (en) * | 2019-09-18 | 2020-01-14 | 上海电力大学 | Nuclear power station primary circuit pressure reduction control method under heat transfer pipe fracture accident |
| CN111753394A (en) * | 2020-05-20 | 2020-10-09 | 中国核电工程有限公司 | Design method for rapid cooling function debugging of primary circuit of advanced pressurized water reactor nuclear power plant |
| CN111863293A (en) * | 2020-08-24 | 2020-10-30 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Injection system suitable for ocean nuclear power platform |
| CN113421662A (en) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | Natural circulation cooling method under failure of liquid level indication of pressure vessel of nuclear power plant |
| CN113421661A (en) * | 2021-05-18 | 2021-09-21 | 中国核电工程有限公司 | System for preventing steam generator from overflowing |
| CN114068048A (en) * | 2021-11-18 | 2022-02-18 | 中国核动力研究设计院 | Low-pressure safety injection system, method and medium for reactor core pressure vessel of nuclear reactor |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20110158371A1 (en) * | 2008-09-30 | 2011-06-30 | Kabushiki Kaisha Toshiba | Pressurized water reactor plant |
| CN102169733A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
| KR20140009835A (en) * | 2012-07-13 | 2014-01-23 | 한국원자력연구원 | Passive safety system of integral reactor |
| US20140226778A1 (en) * | 2013-02-14 | 2014-08-14 | Korea Atomic Energy Research Institute | Multi stage safety injection device and passive safety injection system having the same |
| DE102013222272A1 (en) * | 2013-11-01 | 2014-11-20 | Areva Gmbh | Pressure relief system for a nuclear power plant and associated method |
| CN107068214A (en) * | 2017-05-09 | 2017-08-18 | 中广核研究院有限公司 | Nuclear power plant steam air tapping equipment and secondary circuit pressure method for releasing |
| CN207529679U (en) * | 2017-12-11 | 2018-06-22 | 华龙国际核电技术有限公司 | A kind of safety injection system and nuclear power system |
-
2017
- 2017-12-11 CN CN201711309416.1A patent/CN109903863B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20110158371A1 (en) * | 2008-09-30 | 2011-06-30 | Kabushiki Kaisha Toshiba | Pressurized water reactor plant |
| CN102169733A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
| KR20140009835A (en) * | 2012-07-13 | 2014-01-23 | 한국원자력연구원 | Passive safety system of integral reactor |
| US20140226778A1 (en) * | 2013-02-14 | 2014-08-14 | Korea Atomic Energy Research Institute | Multi stage safety injection device and passive safety injection system having the same |
| DE102013222272A1 (en) * | 2013-11-01 | 2014-11-20 | Areva Gmbh | Pressure relief system for a nuclear power plant and associated method |
| CN107068214A (en) * | 2017-05-09 | 2017-08-18 | 中广核研究院有限公司 | Nuclear power plant steam air tapping equipment and secondary circuit pressure method for releasing |
| CN207529679U (en) * | 2017-12-11 | 2018-06-22 | 华龙国际核电技术有限公司 | A kind of safety injection system and nuclear power system |
Non-Patent Citations (3)
| Title |
|---|
| XIAO, ZJ, ET AL: "Experimental research progress on passive safety systems of Chinese advanced PWR", NUCLEAR ENGINEERING AND DESIGN, vol. 225, no. 2, pages 305 - 313 * |
| 杨俊辉等: "变频式水压试验泵调试问题分析及改进", 电工技术, no. 01, pages 119 - 120 * |
| 游曦鸣;邵舸;佟立丽;曹学武;: "非能动堆芯冷却***LOCA下冷却能力分析", 原子能科学技术, no. 01, pages 111 - 118 * |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110689973A (en) * | 2019-09-18 | 2020-01-14 | 上海电力大学 | Nuclear power station primary circuit pressure reduction control method under heat transfer pipe fracture accident |
| CN110689973B (en) * | 2019-09-18 | 2023-04-28 | 上海电力大学 | Nuclear power station primary loop depressurization control method under heat transfer pipe rupture accident |
| CN111753394A (en) * | 2020-05-20 | 2020-10-09 | 中国核电工程有限公司 | Design method for rapid cooling function debugging of primary circuit of advanced pressurized water reactor nuclear power plant |
| CN111753394B (en) * | 2020-05-20 | 2024-05-14 | 中国核电工程有限公司 | Design method for debugging primary loop rapid cooling function of advanced pressurized water reactor nuclear power plant |
| CN111863293A (en) * | 2020-08-24 | 2020-10-30 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Injection system suitable for ocean nuclear power platform |
| CN113421661A (en) * | 2021-05-18 | 2021-09-21 | 中国核电工程有限公司 | System for preventing steam generator from overflowing |
| CN113421662A (en) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | Natural circulation cooling method under failure of liquid level indication of pressure vessel of nuclear power plant |
| CN114068048A (en) * | 2021-11-18 | 2022-02-18 | 中国核动力研究设计院 | Low-pressure safety injection system, method and medium for reactor core pressure vessel of nuclear reactor |
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