CN108665990A - A kind of device and method of reliable stoppage in transit reactor coolant pump - Google Patents
A kind of device and method of reliable stoppage in transit reactor coolant pump Download PDFInfo
- Publication number
- CN108665990A CN108665990A CN201810386642.8A CN201810386642A CN108665990A CN 108665990 A CN108665990 A CN 108665990A CN 201810386642 A CN201810386642 A CN 201810386642A CN 108665990 A CN108665990 A CN 108665990A
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- CN
- China
- Prior art keywords
- breaker
- reactor
- protection system
- coolant pump
- reactor coolant
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- 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
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/04—Pumping arrangements
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04D—NON-POSITIVE-DISPLACEMENT PUMPS
- F04D15/00—Control, e.g. regulation, of pumps, pumping installations or systems
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- 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
-
- 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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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of device and methods of reliable stoppage in transit reactor coolant pump; described device includes reactor protection system and breaker; the breaker is connected with reactor coolant pump power supply circuit; it is characterized in that; the breaker and reactor protection system are multiple, and each breaker is in series relationship between each other in the power supply circuit；In the breaker, the control command receiving terminal of part breaker is connected with the partial reaction heap protection system in the reactor protection system, and the control command receiving terminal of breaker in addition is connected with other reactor protection system.The realization of the method depends on described device.The device and method are realized simply, while cost of implementation is low, easy to maintain, and can reliably stop transport reactor coolant pump under accident conditions.
Description
Technical field
The present invention relates to the start-up and shut-down control technical fields of pump, more particularly to a kind of reliable stoppage in transit reactor coolant pump
Device and method.
Background technology
Nuclear power plant reactor circuit breaker screen is safety level electrical equipment, is the component part of reactor protection system, existing
In technology in nuclear reactor coolant pump normal start and stop, and realized by breaker.
In the operation of nuclear power station, need breaker have very high reliability and stability, can neither malfunction, can not
Tripping.Currently, realizing the start-up and shut-down control to reactor coolant pump using a circuit device in two Dai Jia nuclear power plants；In AP1000 tri-
In being related to for nuclear power plant, the upstream of reactor coolant pump is reactor coolant pump by two concatenated safety level circuit breaker screens
Power supply；In the design of the nuclear power stations such as one phase of ridge Australia, Daya Gulf and Qinshan second phase, circuit breaker screen uses four breakers, wherein
Two are main circuit breaker, and in unit normal operation, mainly the two breakers put into operation；Another two is bypass breaker,
It puts into operation when main circuit breaker carries out routine test or main circuit breaker failure.Main circuit breaker and bypass breaker are divided into two and are
Row, respectively by the control of reactor protection system (RPR) A, B series shutdown signal.Since the normal operation of coolant pump is related to
To the operational safety of nuclear reactor, in the start-up and shut-down control conceptual design of the above coolant pump, coolant pump start-up and shut-down control performance
Stability is important indicator, therefore, those skilled in the art it is necessary to the scheme of nuclear power plant's stoppage in transit reactor coolant pump into
Row optimization design.
Invention content
For those skilled in the art set forth above it is necessary to the scheme of nuclear power plant's stoppage in transit reactor coolant pump into
The problem of row optimization design, the present invention provides a kind of device and method of reliable stoppage in transit reactor coolant pump, the device and
Method is realized simply, while cost of implementation is low, easy to maintain, and can reliably stop transport reactor coolant pump under accident conditions.
To solve the above problems, a kind of device and method of reliable stoppage in transit reactor coolant pump provided by the invention passes through
Following technical essential solves the problems, such as：A kind of device of reliable stoppage in transit reactor coolant pump, including reactor protection system and
Breaker, the breaker are connected with reactor coolant pump power supply circuit, and the breaker and reactor protection system are
Multiple, each breaker is in series relationship between each other in the power supply circuit；
In the breaker, the control command receiving terminal of part breaker and the part in the reactor protection system are anti-
Heap protection system is answered to be connected, the control command receiving terminal of breaker in addition is connected with other reactor protection system.
In two current generations, add in design of nuclear power plant, and the upstream of reactor coolant pump only has a circuit breaker screen, above disconnected
Road device screen is usually the breaker of a non-security grade.The circuit breaker screen undertakes the normal start and stop of reactor coolant pump, electricity simultaneously
Gas shielded and the safety level breaking signal for receiving reactor protection system carry out the function of reactor coolant pump stoppage in transit.In earthquake
When occurring with other design basis accidents, the circuit breaker screen of non-security grade may be in the safety level for receiving reactor protection system
It fails when breaking signal, can not achieve so as to cause the termination of pumping order that reactor protection system is sent out.
In addition, in the design of AP1000 three generations's nuclear powers, reactor coolant pump is by two concatenated safety level circuit breaker screens
It powers for reactor coolant pump.Nuclear power plant can be improved so reliably to stop transport when earthquake and other design basis accidents occur
The ability of reactor coolant pump.But this two safety level breakers control letter in the reactor protection system for receiving safety level
Number and non-security grade nuclear power plant's control system signal while carry electric measurement and the defencive function of non-security grade.Function
It is various, it is complicated.Influence of the non-security order reaction heap protection system to safety level reactor protection system cannot be avoided completely.
It is above-mentioned in the design of the nuclear power stations such as one phase of ridge Australia, Daya Gulf and Qinshan second phase, using the disconnected of two or more quantity
Road device is actually also a kind of Redundancy Design.
The above safety level circuit breaker screen is made of safety level breaker, non-security grade circuit breaker screen is by non-security grade breaker
The reactor protection system of composition and safety level control signal derives from the reactor protection system of safety level, non-security grade
Nuclear power plant's control system signal derive from the reactor protection system of non-security grade, the above safety level and non-security grade can be according to
The items safety classification that the nuclear safety principle in China carries out is divided, and GB/T15474-1995 can be used in the criteria for classifying.
In the prior art, generally there are multiple reactor protection systems to protect the operational safety of nuclear power plant, carry above
In the prior art of confession, coolant pump stoppage in transit control is carried out using single breaker, is realized using more than two breakers
Redundancy Design is received using single breaker in the control Design of Signal schemes of multiple reactor protection systems, is needed individually disconnected
Road device is vdiverse in function, in this way, breaker structure and logic therein are complicated, for a certain breaker, cannot avoid difference completely
Influencing each other between the control command of reactor protection system output.
In the present solution, being serially connected using by multiple breakers, i.e., reactor coolant pump is connected most end in circuit breaks
The rear end of road device can ensure that reactor coolant pump is out of service in this way, after single breaker executes tripping action,
The generation for avoiding the excessive accident of reactor-loop dehydration, makes reactor unsafe condition occur.The i.e. above breaker setting side
Formula significantly reduces the probability for the heap primary Ioops loss of-coolant accident (LOCA) that reacts.
Further, the control command source for being set as multiple breakers comes from multiple reactor protection systems, meanwhile,
The single breaker control command that only receiving portion reactor protection system is sent out, all breakers are not identical control command
Source can effectively reduce the requirement to single breaker functional diversity and logical performance, can have for single breaker
Effect avoid or weakens differential responses heap protection system output control command between influence each other, such as such as earthquake and design
When basis accident, part breaker receives the control command of non-security order reaction heap protection system, remaining breaker receives safety
Order reaction heap protects the control command of system, in this way, present design can eliminate non-security order reaction heap protection system cannot be
The drawbacks of stoppage in transit reactor coolant pump function is reliably realized under earthquake and design basis accident avoids non-security order reaction heap
Influence of the protection system to safety level reactor protection system greatly improves the safe operation ability and confrontation thing of nuclear power plant
Therefore ability, be effectively guaranteed the safe operation of reactor.
To sum up, which realizes simple, while cost of implementation is low, easy to maintain, can reliably stop transport under accident conditions
Reactor coolant pump.
As a kind of above-described further technical solution of device of reliable stoppage in transit reactor coolant pump：
For the signal interference for avoiding differential responses heap from protecting system mutual, the breaker and reactor protection system
The quantity of the two is equal, and single breaker is only connected with single reactor protection system.
Protect system that cannot reliably realize that stoppage in transit is anti-under earthquake and design basis accident to eliminate non-security order reaction heap
The drawbacks of answering reactor coolant pumping function avoids non-security order reaction heap protection system from generating shadow to safety level reactor protection system
It rings, the reactor protection system includes non-security grade nuclear power plant control system and safety level nuclear power plant control system, described disconnected
In the device of road, part breaker is connected with non-security grade nuclear power plant control system, and breaker in addition is controlled with safety level nuclear power plant
System is connected.
As a kind of scheme that economic cost being arranged conducive to the present apparatus, what is be connected with non-security grade nuclear power plant control system breaks
Road device is non-security grade breaker, and the breaker being connected with safety level nuclear power plant control system is non-security grade breaker.
As a kind of scheme that economic cost being arranged conducive to the present apparatus, the quantity of the non-security grade breaker is one,
The quantity of the safety level breaker is two.
Meanwhile the invention also discloses a kind of method of reliable stoppage in transit reactor coolant pump, this method uses breaker
Realize reactor coolant pump operation out of service, which is characterized in that the quantity of the breaker used in this method to be multiple,
The control command that breaker executes the operation out of service of reactor coolant pump derives from multiple reactor protection systems, and more
A breaker is in that series relationship accesses in the power supply circuit of reactor coolant pump between each other, in the breaker, part
The control command receiving terminal of breaker is connected with the partial reaction heap protection system in reactor protection system, breaker in addition
Control command receiving terminal be connected with other reactor protection system.
Above method is the device that provides of this programme used method when carrying out coolant pump stoppage in transit action, use with
Upper method, can not only reliably stop transport reactor coolant pump under accident conditions, while used hardware when this method realization
It is simple in structure, maintenance cost is low.
As a kind of above-described further technical solution of method of reliable stoppage in transit reactor coolant pump, to avoid
Differential responses heap protection system has an impact same breaker, the quantity phase of both the breaker and reactor protection system
Deng single breaker is only connected with single reactor protection system.
Protect system that cannot reliably realize that stoppage in transit is anti-under earthquake and design basis accident to eliminate non-security order reaction heap
The drawbacks of answering reactor coolant pumping function avoids non-security order reaction heap protection system from generating shadow to safety level reactor protection system
It rings, the reactor protection system includes non-security grade nuclear power plant control system and safety level nuclear power plant control system, described disconnected
In the device of road, part breaker is connected with non-security grade nuclear power plant control system, and breaker in addition is controlled with safety level nuclear power plant
System is connected.Specifically, being set as the breaker being connected with non-security grade nuclear power plant control system receives non-security grade nuclear power plant
The control signal of control system, controls the operation and stopping of reactor coolant pump, while undertaking electric measurement and defencive function；
The breaker being connected with safety level nuclear power plant control system only receives the sub-gate signal of reactor protection system, in this way, safety level
Circuit breaker screen does not undertake measurement and the electic protection function of any non-security grade, by the circuit breaker screen for executing security function and non-peace
Full grade system is thoroughly isolated, and influence of the non-security system to safety level system is thoroughly avoided.
As a kind of technical solution for being conducive to reduce this method cost of implementation, it is connected with non-security grade nuclear power plant control system
Breaker be non-security grade breaker, the breaker being connected with safety level nuclear power plant control system is non-security grade breaker.
As a kind of technical solution for being conducive to reduce this method cost of implementation, the quantity of the non-security grade breaker is one
A, the quantity of the safety level breaker is two.
As the further technical solution of above method, by three auxiliary contact of each breaker in the breaker
After series connection, it is connected with reactor protection system, so that reactor protection system acquires the state of breaker, it is ensured that reactor is protected
Protecting system protection group is capable of the operating condition of accurate sensitive and reactive reactor coolant pump, to ensure the action message of protection system.
The invention has the advantages that：
In device scheme and method scheme that this programme provides, described device is realized that it controls purpose and depends on and is provided
Method scheme.In the present solution, being serially connected using by multiple breakers, i.e., reactor coolant pump is connected most end in circuit breaks
The rear end of road device can ensure that reactor coolant pump is out of service in this way, after single breaker executes tripping action,
The generation for avoiding the excessive accident of reactor-loop dehydration makes reactor be in unsafe condition.The i.e. above breaker setting side
Formula significantly reduces the probability for the heap primary Ioops loss of-coolant accident (LOCA) that reacts.
Further, the control command source for being set as multiple breakers comes from multiple reactor protection systems, meanwhile,
The single breaker control command that only receiving portion reactor protection system is sent out, all breakers are not identical control command
Source can effectively reduce the requirement to single breaker functional diversity and logical performance, can have for single breaker
Effect avoid or weakens differential responses heap protection system output control command between influence each other, such as such as earthquake and design
When basis accident, part breaker receives the control command of non-security order reaction heap protection system, remaining breaker receives safety
Order reaction heap protects the control command of system, in this way, present design can eliminate non-security order reaction heap protection system cannot be
The drawbacks of stoppage in transit reactor coolant pump function is reliably realized under earthquake and design basis accident avoids non-security order reaction heap
Influence of the protection system to safety level reactor protection system greatly improves the safe operation ability and confrontation thing of nuclear power plant
Therefore ability, be effectively guaranteed the safe operation of reactor.
To sum up, which realizes simple, while cost of implementation is low, easy to maintain, can reliably stop transport under accident conditions
Reactor coolant pump.
Description of the drawings
Fig. 1 is a kind of system of one specific embodiment of device of reliable stoppage in transit reactor coolant pump of the present invention
Topological diagram.
Specific implementation mode
With reference to embodiment, the present invention is described in further detail, but the present invention is not limited only to following implementation
Example：
Embodiment 1：
As shown in Figure 1, the present embodiment provides a kind of device or method of specific stoppage in transit reactor coolant pump, the device
Including three breakers and three reactor protection systems, it is cold that three breakers are connected to reactor in series relationship between each other
But on the current supply circuit of agent pump, three breakers include a non-security grade breaker and two safety level breakers, two
Safety level breaker is respectively A series of security grade breakers and B series of security grade breakers.Three reactor protection systems
It is DCS system, meanwhile, one of DCS system is non-security grade DCS system, which sends out non-security grade DCS controls life
It enables, other two DCS system is safety level DCS system, which sends out safety level DCS control commands, the non-peace
Full grade breaker receives non-security grade DCS control commands, and starting and running for control reactor protection coolant pump undertakes simultaneously
The measurement of non-security grade and electic protection function；Two safety level breakers receive what different safety level DCS systems were sent out respectively
Safety level DCS control commands only control starting and running for reactor coolant pump, do not undertake any non-security grade function.It is logical
The program is crossed, can eliminate non-security order reaction heap protection system cannot reliably realize that stoppage in transit is anti-under earthquake and design basis accident
The drawbacks of answering reactor coolant pumping function avoids non-security order reaction heap protection system from generating shadow to safety level reactor protection system
It rings.
Embodiment 2：
The present embodiment is further improved or limits to the scheme on the basis of embodiment 1：It will be in three breakers
After three auxiliary contact series connection of each breaker, it is connected with reactor protection system, so that reactor protection system acquires
The state of breaker, it is ensured that reactor protection system protection group is capable of the operating condition of accurate sensitive and reactive reactor coolant pump,
To ensure the action message of reactor protection system.
The above content is combine specific preferred embodiment to the further description of the invention made, and it cannot be said that originally
The specific implementation mode of invention is confined to these explanations.For those of ordinary skill in the art to which the present invention belongs,
The other embodiment obtained in the case where not departing from technical scheme of the present invention, should be included within the scope of the present invention.
Claims (10)
1. a kind of device of reliable stoppage in transit reactor coolant pump, including reactor protection system and breaker, the breaker
Be connected with reactor coolant pump power supply circuit, which is characterized in that the breaker and reactor protection system be it is multiple, respectively
Breaker is in series relationship between each other in the power supply circuit；
In the breaker, control command receiving terminal and the partial reaction heap in the reactor protection system of part breaker
Protection system is connected, and the control command receiving terminal of breaker in addition is connected with other reactor protection system.
2. a kind of device of reliable stoppage in transit reactor coolant pump according to claim 1, which is characterized in that the open circuit
The quantity of both device and reactor protection system is equal, and single breaker is only connected with single reactor protection system.
3. a kind of device of reliable stoppage in transit reactor coolant pump according to claim 1, which is characterized in that the reaction
Heap protection system includes non-security grade nuclear power plant control system and safety level nuclear power plant control system, in the breaker, part
Breaker is connected with non-security grade nuclear power plant control system, and other breaker is connected with safety level nuclear power plant control system.
4. a kind of device of reliable stoppage in transit reactor coolant pump according to claim 3, which is characterized in that with it is non-security
The connected breaker of grade nuclear power plant control system is non-security grade breaker, the open circuit being connected with safety level nuclear power plant control system
Device is non-security grade breaker.
5. a kind of device of reliable stoppage in transit reactor coolant pump according to claim 4, which is characterized in that the non-peace
The quantity of full grade breaker is one, and the quantity of the safety level breaker is two.
6. a kind of method of reliable stoppage in transit reactor coolant pump, this method realizes stopping for reactor coolant pump using breaker
Only operation operation, which is characterized in that for the quantity of the breaker used in this method to be multiple, breaker executes reactor coolant
The control command of the operation out of service of pump derives from multiple reactor protection systems, and multiple breakers are in series connection between each other
Relationship accesses in the power supply circuit of reactor coolant pump, in the breaker, the control command receiving terminal of part breaker
Be connected with the partial reaction heap protection system in reactor protection system, the control command receiving terminal of breaker in addition and in addition
Reactor protection system be connected.
7. a kind of method of reliable stoppage in transit reactor coolant pump according to claim 6, which is characterized in that the open circuit
The quantity of both device and reactor protection system is equal, and single breaker is only connected with single reactor protection system.
8. a kind of method of reliable stoppage in transit reactor coolant pump according to claim 6, which is characterized in that the reaction
Heap protection system includes non-security grade nuclear power plant control system and safety level nuclear power plant control system, in the breaker, part
Breaker is connected with non-security grade nuclear power plant control system, and other breaker is connected with safety level nuclear power plant control system.
9. a kind of method of reliable stoppage in transit reactor coolant pump according to claim 8, which is characterized in that with it is non-security
The connected breaker of grade nuclear power plant control system is non-security grade breaker, the open circuit being connected with safety level nuclear power plant control system
Device is non-security grade breaker.
10. a kind of method of reliable stoppage in transit reactor coolant pump according to claim 9, which is characterized in that described non-
The quantity of safety level breaker is one, and the quantity of the safety level breaker is two.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810386642.8A CN108665990A (en) | 2018-04-26 | 2018-04-26 | A kind of device and method of reliable stoppage in transit reactor coolant pump |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810386642.8A CN108665990A (en) | 2018-04-26 | 2018-04-26 | A kind of device and method of reliable stoppage in transit reactor coolant pump |
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| CN108665990A true CN108665990A (en) | 2018-10-16 |
Family
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| CN201810386642.8A Pending CN108665990A (en) | 2018-04-26 | 2018-04-26 | A kind of device and method of reliable stoppage in transit reactor coolant pump |
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Application publication date: 20181016 |