CN109686465A - A kind of diagnostic method of reactor shutdown failure - Google Patents
A kind of diagnostic method of reactor shutdown failure Download PDFInfo
- Publication number
- CN109686465A CN109686465A CN201811421509.8A CN201811421509A CN109686465A CN 109686465 A CN109686465 A CN 109686465A CN 201811421509 A CN201811421509 A CN 201811421509A CN 109686465 A CN109686465 A CN 109686465A
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- Prior art keywords
- shutdown
- signal
- emergency shut
- reactor
- diagnostic method
- 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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- 238000002405 diagnostic procedure Methods 0.000 title claims abstract description 18
- 230000001052 transient effect Effects 0.000 claims abstract description 39
- 230000003466 anti-cipated effect Effects 0.000 claims abstract description 38
- 238000012544 monitoring process Methods 0.000 claims abstract description 20
- 230000000116 mitigating effect Effects 0.000 claims abstract description 18
- 238000013461 design Methods 0.000 claims description 11
- 238000000926 separation method Methods 0.000 claims description 5
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 claims description 3
- 239000004327 boric acid Substances 0.000 claims description 3
- 238000001514 detection method Methods 0.000 claims description 3
- 238000000034 method Methods 0.000 abstract description 7
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 238000012935 Averaging Methods 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 239000002918 waste heat Substances 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 238000012790 confirmation Methods 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000003745 diagnosis Methods 0.000 description 1
- 230000002708 enhancing effect Effects 0.000 description 1
- JEGUKCSWCFPDGT-UHFFFAOYSA-N h2o hydrate Chemical compound O.O JEGUKCSWCFPDGT-UHFFFAOYSA-N 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The present invention provides a kind of diagnostic method of reactor shutdown failure, and described method includes following steps: heap plug level monitoring system carries out the monitoring of nuclear power station shutdown state, receives the starting shutdown signal that nuclear power station unit station issues；Heap plug level monitoring system receives and detects control rod position according to the starting shutdown signal, determines whether shutdown success according to the comparison result of the control rod position and predeterminated position threshold value that detect, and generate shutdown state signal；Determined whether to issue the anticipated transient signal for failing emergency shut-down according to the starting shutdown signal and shutdown state signal；It receives and subsequent accident mitigation is entered according to the anticipated transient signal for failing emergency shut-down, accident mitigation is carried out according to default accident mitigation strategy.The present invention passes through, and is capable of deciding whether to fail emergency shut-down due to mechanical card rod.
Description
Technical field
The present invention relates to nuclear-power reactor technical security fields, and in particular to a kind of diagnosis side of reactor shutdown failure
Method.
Background technique
In nuclear power plant accident, realize that emergency shutdown is to protect the important prerequisite of reactor safety.Tradition is pressed
For water-water reactor design, the main realization means for shutdown of meeting an urgent need are that insertion is made to react by the control rod that neutron poison forms into reactor core
Heap immediately enters subcritical state.This process that emergency shut-down is realized by control rod is: reactor protection system is patrolled
Operation is collected, reactor emergency shut-down driving signal is generated, emergency shut-down driving signal makes shutdown breaker coil power loss, and shutdown is disconnected
Road device is opened, stick power loss, and control rod falls, reactor shutdown.There are control rods to be unable to underthrust for this emergency shut-down method
Reactor is caused to be unable to the Potential feasibility of emergency shut-down.
There is enterprise to propose the diagnostic method of some shutdowns at present, such as patent document CN102881340B, it is of the invention
Purpose is by parameters such as monitoring pile neutron fluences, and confirmation control rod is not able to achieve emergency shutdown；In another example patent document
CN104332200A is related to the step-out monitoring of control rod, judges whether control rod operates other step-out alarms, judges control rod position
It sets and whether change in location, operation is carried out according to position record value and determines whether to alarm.
In the implementation of the present invention, at least there are the following problems for inventor's discovery prior art:
Patent document CN102881340B is directed to vertical core structure, is not suitable for other core structures.According to its monitoring
The immediate cause that parameter cannot intuitively judge that reactor fails shutdown is mechanical card rod or since Signal Fail causes.
Patent document CN104332200A is related to the step-out monitoring of control rod, passes through each control in monitoring control rod group
Given stick position when the measuring stick position of stick changes, then mean value and extreme value are calculated, it then calculates and deviates, if deviation is super
Threshold value just triggers step-out alarm out.Whether main purpose is to monitor control rod step-out, rather than judge reactor core due to control rod
Card rod fails shutdown.
To sum up, it can decide whether to fail emergency shut-down due to mechanical card rod there has been no dependent diagnostic method at present.
Summary of the invention
The problem to be solved in the present invention is to provide a kind of diagnostic method of reactor shutdown failure, with judge whether due to
Mechanical card rod and fail emergency shut-down.
In order to solve the above-mentioned technical problem, the embodiment of the present invention provides a kind of diagnostic method of reactor shutdown failure, should
Method includes the following steps:
S1 heap plug level monitoring system carries out the monitoring of nuclear power station shutdown state, receives the starting shutdown letter that nuclear power station unit station issues
Number；
S2 heap plug level monitoring system receives and detects control rod position according to the starting shutdown signal, according to the control detected
The comparison result of stick position processed and predeterminated position threshold value determines whether shutdown success, and generates shutdown state signal；
S3 determines whether that issuing the anticipated transient for failing emergency shut-down believes according to the starting shutdown signal and shutdown state signal
Number；
S4 is received and is entered subsequent accident mitigation according to the anticipated transient signal for failing emergency shut-down, slow according to default accident
Solution strategy carries out accident mitigation.
Wherein, it includes: to detect the number of nuclear power plant's unit allocation stick underthrust and every that control rod position is detected in the S2
The position of the control rod of one underthrust.
Wherein, determine whether to stop according to the comparison result of the control rod position and predeterminated position threshold value that detect in the S2
If the number and location that heap successfully includes: control rod underthrust do not reach design of nuclear power plant requirement, then it is assumed that shutdown failure is simultaneously
Generate shutdown failure signal；If the number and location of control rod underthrust reach design of nuclear power plant requirement, then it is assumed that shutdown success
And generate shutdown pass signal.
Wherein, the S3 is specifically included:
If receiving the starting shutdown signal and the shutdown failure signal, the anticipated transient for failing emergency shut-down is issued
Signal；
If receiving the starting shutdown signal and the shutdown pass signal, the expection wink for failing emergency shut-down is not issued
State signal.
Wherein, the S4 includes the anticipated transient signal for failing emergency shut-down described in reception, fails promptly to stop according to described
The anticipated transient signal of heap or the anticipated transient signal for failing emergency shut-down combine the control of other signals to stop reactor
The main pump of primary Ioops.
Wherein, the S4 includes the anticipated transient signal for failing emergency shut-down described in reception, fails promptly to stop according to described
The anticipated transient signal of heap or the anticipated transient signal for failing emergency shut-down combine other signals control starting waste heat row
System out.
Wherein, the S4 includes receiving and injecting dense boron to reactor core according to the anticipated transient signal for failing emergency shut-down
Acid solution.
Wherein, the S4 includes receiving and being controlled according to the anticipated transient signal for failing emergency shut-down and other signals
Control close portion divides separation valve door.
Wherein, control close portion divides other signals of separation valve door to be the excessive signal of secondary circuit steam flow.
The embodiment of the present invention has the advantages that
The embodiment of the present invention judges that nuclear power station enters mechanical card rod and fails tightly with nuclear power station design parameter by the monitoring of heap core rod position
The anticipated transient accident of emergency stop heap, accurate information needed for obtaining accident mitigation (management).To start reply in the shortest time
Measure and contingency plan, to greatest extent reduce accident risk provide safeguard, thus further enhance nuclear power station safety and can
By property.After the embodiment of the present invention is implemented, the problem of can accidentally being driven to avoid existing nuclear power station trip protection system ATWT cabinet, and
The embodiment of the present invention is simple and practical, and operation and feasibility are strong, can be improved the safety of nuclear power station, reliability and economy.
Detailed description of the invention
In order to more clearly explain the embodiment of the invention or the technical proposal in the existing technology, to embodiment or will show below
There is attached drawing needed in technical description to be briefly described, it should be apparent that, the accompanying drawings in the following description is only this
Some embodiments of invention for those of ordinary skill in the art without creative efforts, can be with
It obtains other drawings based on these drawings.
Fig. 1 is a kind of diagnostic method flow chart of reactor shutdown failure in the embodiment of the present invention.
Fig. 2 is that ATWS signal flow graph is issued in the embodiment of the present invention.
Specific embodiment
Following will be combined with the drawings in the embodiments of the present invention, and technical solution in the embodiment of the present invention carries out clear, complete
Site preparation description, it is clear that described embodiments are only a part of the embodiments of the present invention, instead of all the embodiments.It is based on
Embodiment in the present invention, it is obtained by those of ordinary skill in the art without making creative efforts every other
Embodiment shall fall within the protection scope of the present invention.
As shown in Figure 1, the embodiment of the present invention provides a kind of diagnostic method of reactor shutdown failure, include the following steps:
S1 heap plug level monitoring system carries out the monitoring of nuclear power station shutdown state, receives the starting shutdown letter that nuclear power station unit station issues
Number；
S2 heap plug level monitoring system receives and detects control rod position according to the starting shutdown signal, according to the control detected
The comparison result of stick position processed and predeterminated position threshold value determines whether shutdown success, and generates shutdown state signal；
S3 determines whether that issuing the anticipated transient for failing emergency shut-down believes according to the starting shutdown signal and shutdown state signal
Number namely ATWS signal (ATWS, Anticipated transient without scram)；
S4 is received and is entered subsequent accident mitigation according to the anticipated transient signal for failing emergency shut-down, slow according to default accident
Solution strategy carries out accident mitigation.
Specifically, detection control rod position described in step S2 includes: the number for detecting nuclear power plant's unit allocation stick underthrust
The position of mesh and the control rod of each underthrust；
As shown in Fig. 2, being determined described in step S2 according to the comparison result of the control rod position and predeterminated position threshold value that detect
Whether shutdown successfully includes:
If the number and location of control rod underthrust do not reach design of nuclear power plant requirement, then it is assumed that shutdown fails and generates shutdown
Failure signal；For example, control rod does not entirely fall in reactor core or without being inserted into reactor core bottom down completely.
If the number and location of control rod underthrust reach design of nuclear power plant requirement, then it is assumed that shutdown succeeds and generates shutdown
Pass signal.
It should be noted that control rod is inserted to reactor core bottom under needing, therefore passes through the control rod of detection underthrust in shutdown
Quantity and underthrust after control rod position, and combine nuclear power plant in shutdown to the action request of control rod, can be quick
Whether in place control rod is judged, it is possible thereby to determine that shutdown failure whether because of control rod clamping stagnation, is not inserted to design of nuclear power plant down
Position and cause.
It is described to determine whether that sending fails promptly according to the starting shutdown signal and shutdown state signal in the present embodiment
The anticipated transient signal of shutdown includes:
If receiving the starting shutdown signal and the shutdown failure signal, the anticipated transient for failing emergency shut-down is issued
Signal；It should be noted that only receiving the starting shutdown signal and the shutdown failure signal simultaneously, it can just issue and fail
The anticipated transient signal of emergency shut-down.
If receiving the starting shutdown signal and the shutdown pass signal, does not issue and fail the pre- of emergency shut-down
Phase transient signal.
Specifically, being detected simultaneously by nuclear power plant's unit allocation stick when monitoring nuclear power plant's unit sending shutdown signal and inserting
The number and location entered judge the shutdown state of nuclear power plant according to the final position of control rod, if control rod underthrust
Number and location do not reach design of nuclear power plant requirement, it is believed that shutdown failure, issue ATWS signal, it is on the contrary then think shutdown at
Function does not need shutdown, does not issue ATWS signal.
In the present embodiment, it includes stopping reactor-loop that the basis, which presets accident mitigation strategy and carries out accident mitigation,
Main pump, when secondary circuit steam flow is excessive, close portion divides separation valve door, injects concentrated boric acid solution to reactor core, starting Residual heat removal
System.
Specifically, the default accident mitigation strategy of the present embodiment includes:
1) fail the anticipated transient signal or the anticipated transient signal node for failing emergency shut-down of emergency shut-down according to
The main pump that other signals (e.g. steam generator water level signal) cut off reactor-loop is closed, primary Ioops lean on Natural Circulation band
Heat.
2) the anticipated transient signal and the control control of secondary circuit status signal for failing emergency shut-down according to close part
The coolant loading amount of separation valve door guarantee secondary circuit.
3) the anticipated transient signal enabling emergency boronation system for failing emergency shut-down according to, injects dense boric acid to reactor core
Solution controls the reactivity of reactor core.
4) fail the anticipated transient signal or the anticipated transient letter for failing emergency shut-down of emergency shut-down according to
Number combine other signals (such as primary Ioops water level signal or steam generator water level signal) start (passive/active) waste heat
Discharge system helps to take away the heat of reactor.
Wherein, ATWS signal can individually enter accident mitigation (such as default accident mitigation strategy 3), but certain alleviations
Measure also needs to be determined according to the state of the other systems of nuclear power plant.Such as above-mentioned close portion sub-valve guarantees secondary circuit coolant
Loading amount needs ATWS Signal averaging secondary circuit steam flow excessive or other can characterize the signal of secondary circuit state to execute,
That is while receiving ATWS signal and when secondary circuit steam flow is excessive or other can characterize the signal of secondary circuit state
Default accident mitigation strategy 2 can just be executed), thus execute certain accident mitigation measures be need to consider ATWS Signal averaging its
Its signal.Other signals, for example, secondary circuit steam flow it is excessive etc. can be nuclear power plant system state signal.
By the description of the above content it is found that the embodiment of the present invention is sentenced by the monitoring of heap core rod position with nuclear power station design parameter
Disconnected nuclear power station enters the anticipated transient accident that mechanical card rod fails emergency shut-down, accurate letter needed for obtaining accident mitigation (management)
Breath.To start counter-measure and contingency plan in the shortest time, accident risk is reduced to greatest extent and is provided safeguard, thus into one
The safety and reliability of step enhancing nuclear power station.It, can be to avoid existing nuclear power station Reactor trip system after the embodiment of the present invention is implemented
The problem of ATWT cabinet of uniting accidentally drives, and the embodiment of the present invention is simple and practical, operation and feasibility are strong, can be improved nuclear power station
Safety, reliability and economy.
The above described is only a preferred embodiment of the present invention, being not intended to limit the present invention in any form.Though
So the present invention has been disclosed as a preferred embodiment, and however, it is not intended to limit the invention.It is any to be familiar with those skilled in the art
Member, without departing from the scope of the technical proposal of the invention, all using the methods and technical content of the disclosure above to the present invention
Technical solution makes many possible changes and modifications or equivalent example modified to equivalent change.Therefore, it is all without departing from
The content of technical solution of the present invention, according to the technical essence of the invention any simple modification made to the above embodiment, equivalent
Variation and modification, all of which are still within the scope of protection of the technical scheme of the invention.
Claims (9)
1. a kind of diagnostic method of reactor shutdown failure, which comprises the steps of:
S1 heap plug level monitoring system carries out the monitoring of nuclear power station shutdown state, receives the starting shutdown letter that nuclear power station unit station issues
Number；
S2 heap plug level monitoring system receives and detects control rod position according to the starting shutdown signal, according to the control detected
The comparison result of stick position processed and predeterminated position threshold value determines whether shutdown success, and generates shutdown state signal；
S3 determines whether that issuing the anticipated transient for failing emergency shut-down believes according to the starting shutdown signal and shutdown state signal
Number；
S4 is received and is entered subsequent accident mitigation according to the anticipated transient signal for failing emergency shut-down, slow according to default accident
Solution strategy carries out accident mitigation.
2. the diagnostic method of reactor shutdown failure according to claim 1, which is characterized in that
It includes: the control for detecting the number and each underthrust of nuclear power plant's unit allocation stick underthrust that control rod position is detected in the S2
The position of stick processed.
3. the diagnostic method of reactor shutdown failure according to claim 2, which is characterized in that according to detection in the S2
If to control rod position and the comparison result of predeterminated position threshold value determine whether shutdown successfully and include: the number of control rod underthrust
Mesh and position do not reach design of nuclear power plant requirement, then it is assumed that shutdown fails and generates shutdown failure signal；If under control rod
Slotting number and location reach design of nuclear power plant requirement, then it is assumed that shutdown succeeds and generates shutdown pass signal.
4. the diagnostic method of reactor shutdown failure according to claim 3, which is characterized in that the S3 is specifically included:
If receiving the starting shutdown signal and the shutdown failure signal, the anticipated transient for failing emergency shut-down is issued
Signal；
If receiving the starting shutdown signal and the shutdown pass signal, the expection wink for failing emergency shut-down is not issued
State signal.
5. the diagnostic method of reactor shutdown failure according to claim 4, which is characterized in that the S4 includes receiving institute
State the anticipated transient signal for failing emergency shut-down, according to the anticipated transient signal for failing emergency shut-down or it is described fail it is tight
The anticipated transient signal of emergency stop heap combines the main pump of other signals control stopping reactor-loop.
6. the diagnostic method of reactor shutdown failure according to claim 5, which is characterized in that the S4 includes receiving institute
State the anticipated transient signal for failing emergency shut-down, according to the anticipated transient signal for failing emergency shut-down or it is described fail it is tight
The anticipated transient signal of emergency stop heap combines other signals control starting residual heat removal system.
7. the diagnostic method of reactor shutdown failure according to claim 5, which is characterized in that the S4 includes receiving simultaneously
Concentrated boric acid solution is injected to reactor core according to the anticipated transient signal for failing emergency shut-down.
8. the diagnostic method of reactor shutdown failure according to claim 5, which is characterized in that the S4 includes receiving simultaneously
Divide separation valve door according to the anticipated transient signal for failing emergency shut-down and secondary circuit status signal control control close portion.
9. the diagnostic method of reactor shutdown failure according to claim 8, which is characterized in that the secondary circuit state is
The excessive signal of secondary circuit steam flow.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811421509.8A CN109686465A (en) | 2018-11-27 | 2018-11-27 | A kind of diagnostic method of reactor shutdown failure |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811421509.8A CN109686465A (en) | 2018-11-27 | 2018-11-27 | A kind of diagnostic method of reactor shutdown failure |
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| Publication Number | Publication Date |
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| CN109686465A true CN109686465A (en) | 2019-04-26 |
Family
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| Application Number | Title | Priority Date | Filing Date |
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| CN201811421509.8A Pending CN109686465A (en) | 2018-11-27 | 2018-11-27 | A kind of diagnostic method of reactor shutdown failure |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111540485A (en) * | 2020-05-18 | 2020-08-14 | 中国核动力研究设计院 | Protection system for dealing with ATWS (automatic water supply) accident of nuclear power plant caused by loss of normal water supply |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101840737A (en) * | 2009-09-02 | 2010-09-22 | 中广核工程有限公司 | Digital rod position control system and method |
| CN102881340A (en) * | 2012-09-27 | 2013-01-16 | 中国核电工程有限公司 | Emergency shut-down system and method combining activeness and passiveness |
-
2018
- 2018-11-27 CN CN201811421509.8A patent/CN109686465A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101840737A (en) * | 2009-09-02 | 2010-09-22 | 中广核工程有限公司 | Digital rod position control system and method |
| CN102881340A (en) * | 2012-09-27 | 2013-01-16 | 中国核电工程有限公司 | Emergency shut-down system and method combining activeness and passiveness |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111540485A (en) * | 2020-05-18 | 2020-08-14 | 中国核动力研究设计院 | Protection system for dealing with ATWS (automatic water supply) accident of nuclear power plant caused by loss of normal water supply |
| CN111540485B (en) * | 2020-05-18 | 2022-02-01 | 中国核动力研究设计院 | Protection system for dealing with ATWS (automatic water supply) accident of nuclear power plant caused by loss of normal water supply |
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