CN102324258A - Method and system for preventing error drive of ATWT (Anticipated Transients without Trip) equipment cabinet - Google Patents

Method and system for preventing error drive of ATWT (Anticipated Transients without Trip) equipment cabinet Download PDF

Info

Publication number
CN102324258A
CN102324258A CN201110164273A CN201110164273A CN102324258A CN 102324258 A CN102324258 A CN 102324258A CN 201110164273 A CN201110164273 A CN 201110164273A CN 201110164273 A CN201110164273 A CN 201110164273A CN 102324258 A CN102324258 A CN 102324258A
Authority
CN
China
Prior art keywords
signal
atwt
rack
circuit
power supply
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.)
Granted
Application number
CN201110164273A
Other languages
Chinese (zh)
Other versions
CN102324258B (en
Inventor
王巧燕
田亚杰
江辉
张龙强
李恒
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
Original Assignee
China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by China General Nuclear Power Corp, China Nuclear Power Engineering Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN201110164273.6A priority Critical patent/CN102324258B/en
Publication of CN102324258A publication Critical patent/CN102324258A/en
Application granted granted Critical
Publication of CN102324258B publication Critical patent/CN102324258B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Abstract

The invention discloses a method and system for preventing error drive of an ATWT (Anticipated Transients without Trip) equipment cabinet, wherein the method comprises the following steps of: collecting a main feedwater flow signal and a nuclear instrument signal; collecting a power loss signal of a reactor protection equipment cabinet; outputting a first signal after the power loss signal and the main feedwater flow signal are subjected to a first logic AND treatment; and outputting a second signal after the first signal and the nuclear instrument signal are subjected to a second logic AND treatment, wherein the second signal is used for determining whether ATMT happens or not. Through the collection of the power loss signal of the reactor protection equipment cabinet and the corresponding logic treatment of the signals, the error protection of the ATWT is effectively inhibited.

Description

A kind of nuclear power station ATWT rack mistake method of driving and system of preventing
Technical field
The present invention relates to the nuclear power technology field, relate in particular to a kind of nuclear power station ATWT rack mistake method of driving and system of preventing.
Background technology
Reactor protection system mainly is emergency shut-down to the salvo of accident conditions, when the emergency shut-down protection then starts ATWT (tripping of Anticipated Transients without Trip trip protection system) rack when breaking down.Reach emergency shut-down protection threshold value like the nuclear power station parameter but do not produce the emergency shut-down guard signal, though or produced the scram signal scram breaker and do not broken off, and ATWT then takes place in directly emergency shut-down.
The ATWT rack has adopted protection logic as shown in Figure 1; When range nuclear power is greater than 30%Pn in the middle of the nuclear power station; If main feedwater flow is lower than 6%NF; Then start the ATWT protection, promptly take shutdown, shutdown, startup auxiliary feedwater and the 3rd group of action such as bleed valve of locking GCT (Steam Turbine Bypass System).
ATWT protects as one of diversified important means of reactor protection; In order to prevent the digitizing common mode failure; Adopt mimic channel to realize the ATWT function, this function realizes in DAC (variation drives rack), generally also can DAC variation rack be called the ATWT rack.
Prior art scheme such as Fig. 2, main feedwater flow signal deliver to the ATWT rack after being gathered, distribute, isolated by RPC (reactor protection rack), and signal type is 0-10V, and the signal of RPN (nuclear instrument) (comprising test and fault-signal) is directly gathered from the RPN rack.Main feedwater flow signal is done three and is got two logics, do with the RPN signal " with " logic, produce the ATWT signal at last, trigger corresponding protection action.That anticipates shown in Fig. 2 realizes with a door or a hard logic module that in fact all adopts analog component to be barricaded as.
Because main feedwater flow sensor is by the power supply of RPC rack, when RPC rack dead electricity took place, the flow signal that is sent to the ATWT rack became 0V; And at power plant's normal operation period; Nuclear power must be greater than 30%FP, and this will cause mistake to drive the ATWT protection, produces serious consequences such as spurious shutdown, mistakenly stop machine; Reduce the available rate of power plant, caused the tremendous economic loss to power plant simultaneously.
Summary of the invention
The technical matters that the present invention will solve is to prior art the defective that ATWT protection mistake drives to take place easily, and a kind of nuclear power station trip protection system tripping ATWT rack mistake method of driving and system of preventing is provided.
The technical solution adopted for the present invention to solve the technical problems is:
A kind of nuclear power station ATWT rack mistake method of driving that prevents is provided, comprises step: gather main feedwater flow signal and nuclear instrument signal, also comprise step:
Gather the power supply dead electricity signal of reactor protection rack;
With said power supply dead electricity signal and said main feedwater flow signal through with logical process after output first signal;
With said first signal and said nuclear instrument signal through with logical process after export secondary signal, and characterize according to said secondary signal whether ATWT takes place, and trigger the ATWT protection.
The nuclear power station ATWT rack that prevents of the present invention misses in the method for driving, and said power supply dead electricity signal is 0 o'clock, and the power supply of expression reactor protection rack is normal; Said main feedwater flow signal is 1 o'clock, and range nuclear power is greater than 30%Pn in the middle of the expression nuclear power station; Said main feedwater flow signal is 1 o'clock, representes that main feedwater flow is lower than 6%NF; At said power supply dead electricity signal is 1 o'clock, and said main feedwater flow signal and said nuclear instrument signal be at 1 o'clock, and this moment, said first signal and said secondary signal were 1, and said logic determines produces the ATWT signal, and the ATWT protection takes place the ATWT rack simultaneously.
Of the present inventionly prevent that power supply dead electricity signal described in the nuclear power station ATWT rack mistake method of driving from being the dead electricity signal of primary power or standby power supply in the said reactor protection rack.
Main feedwater flow signal described in the nuclear power station ATWT rack method of driving of the present invention is that three steam generator flow low signals are got the signal of two logics output through three.
Gathering the nuclear instrument signal described in the nuclear power station ATWT rack method of driving of the present invention is specially: range, test pattern and the fault-signal that will examine in instrument system one passage are exported a channel signal through OR circuit; Simultaneously, range, test pattern and fault-signal in nuclear instrument system two passages are also exported two channel signals through OR circuit; A said channel signal and two channel signals are exported said nuclear instrument signal through AND circuit again.
Another technical scheme that technical solution problem of the present invention adopts is:
A kind of nuclear power station ATWT rack mistake method of driving that prevents is provided; Comprise reactor protection rack, main feedwater flow signal acquisition module, nuclear instrument signal acquisition module and ATWT rack; Said reactor protection rack comprises primary power and standby power supply; This system also comprises: power supply dead electricity signal acquisition module is used to gather the power supply dead electricity signal of said reactor protection rack; Said ATWT rack comprises the first logical and circuit, the second logical and circuit and ATWT driver module;
The said first logical and circuit, the main feedwater flow signal that is used for said power supply dead electricity signal and said main feedwater flow signal acquisition module are gathered is handled back output first signal through AND circuit;
The said second logical and circuit; The nuclear instrument signal that is used for said first signal and said nuclear instrument signal acquisition module are gathered is handled back output secondary signal through AND circuit, and said secondary signal is used to control said ATWT driver module whether ATWT takes place.
In the system that nuclear power station ATWT rack of the present invention drives; Said power supply dead electricity signal acquisition module comprises first relay that is connected with said primary power and second relay that is connected with said standby power supply, two contact parallel connections of said first relay and said second relay;
Said ATWT rack comprises the 3rd relay, and the coiler part of said the 3rd relay is connected with parallel connection place of said first relay and said second relay, and the contact of said the 3rd relay is connected with the said first logical and circuit.
Of the present invention preventing in the nuclear power station ATWT rack mistake method of driving; Main feedwater flow signal acquisition module comprises three flow sensors; The flow that is used for three steam generators of detection reaction heap protection cabinet four-way rack; In twos through obtaining three signals behind the AND circuit, these three signals are again through obtaining said main feedwater flow signal behind the OR circuit with detected three steam generator flow low signals for said three flow sensors.
Of the present invention preventing examined the instrument signal acquisition module and comprised a channel signal processing unit, two channel signal processing units and the 3rd logical and circuit in the nuclear power station ATWT rack mistake method of driving, wherein:
A said channel signal processing unit is used for range signal, test mode signal and the fault-signal of nuclear instrument system one passage are passed through to export a channel signal behind the OR circuit;
Said two channel signal processing units are used for range signal, test mode signal and the fault-signal of nuclear instrument system two passages are passed through to export two channel signals behind the OR circuit;
Said the 3rd logical and circuit is used for a said channel signal and said two channel signals are passed through to export said nuclear instrument signal behind the AND circuit.
The beneficial effect that the present invention produces is: the power supply dead electricity signal of gathering the reactor protection rack through power supply dead electricity signal acquisition module; The main feedwater flow signal of being gathered, nuclear instrument signal and power supply dead electricity signal are passed through the first logical and circuit and the second logical and processing of circuit; Utilize the signal controlling of second logical and circuit output whether ATWT takes place, thereby the misoperation of ATWT is effectively suppressed.
Description of drawings
To combine accompanying drawing and embodiment that the present invention is described further below, in the accompanying drawing:
Fig. 1 is an ATWT protection logic realization synoptic diagram;
Fig. 2 is the logic realization synoptic diagram of ATWT in the prior art;
Fig. 3 is the system architecture synoptic diagram that preferred embodiment nuclear power station ATWT rack of the present invention drives;
Fig. 4 is the system power supply dead electricity signal acquisition module of preferred embodiment nuclear power station ATWT rack driving of the present invention and the part-structure synoptic diagram of ATWT driver module;
Fig. 5 is that the system logic that preferred embodiment nuclear power station ATWT rack of the present invention drives realizes synoptic diagram;
Fig. 6 is a nuclear power station ATWT rack method of driving process flow diagram of the present invention.
Embodiment
In order to make the object of the invention, technical scheme and advantage clearer,, the present invention is further elaborated below in conjunction with accompanying drawing and embodiment.Should be appreciated that specific embodiment described herein only in order to explanation the present invention, and be not used in qualification the present invention.
As shown in Figure 3; The system that preferred embodiment nuclear power station ATWT rack of the present invention drives comprises main feedwater flow signal acquisition module 10, power supply dead electricity signal acquisition module 20, nuclear instrument signal acquisition module 30 and ATWT rack 40; Power supply dead electricity signal acquisition module 20 is used to gather the power supply dead electricity signal of reactor protection rack (being the RPC rack), and power supply dead electricity signal can be the dead electricity signal of primary power or standby power supply in the RPC rack; Power supply dead electricity signal is 1 o'clock, and the power supply of expression RPC rack is normal, and power supply dead electricity signal is to represent that the power supply of RPC rack was undesired at 0 o'clock; ATWT rack 40 comprises the first logical and circuit 41, second logical circuit 42 and ATWT driver module 43; The first logical and circuit 41; The main feedwater flow signal that is used for power supply dead electricity signal and main feedwater flow signal acquisition module 10 are gathered is handled back output first signal through AND circuit; Main feedwater flow signal is 1 o'clock in the preferred embodiment of the present invention, representes that main feedwater flow is lower than 6%NF; The second logical and circuit 42; Be used for the nuclear instrument signal that first signal and nuclear instrument signal acquisition module 30 are gathered is handled back output secondary signal through AND circuit; Preferred embodiment center instrument signal of the present invention is 1 o'clock; Range nuclear power is greater than 30%Pn in the middle of the expression nuclear power station, and whether secondary signal control ATWT driver module 43 ATWT takes place.At power supply dead electricity signal is 1 o'clock, and main feedwater flow signal is at 1 o'clock with the nuclear instrument signal, and this moment, first signal and secondary signal also were 1, then produced the ATWT signal, and the ATWT rack ATWT takes place is protected simultaneously.
Further, as shown in Figure 4, power supply dead electricity signal acquisition module 20 is arranged among the RPC (the reactor protection cabinet is generally reactor protection cabinet four-way rack), and RPC is by primary power 21 or standby power supply 22 power supplies.Power supply dead electricity signal acquisition module 20 comprises first relay 23 that is connected with primary power 21 and second relay 23 that is connected with standby power supply 22; Primary power 21 is respectively the coil power supply in first relay 23 and second relay 24 with standby power supply 22; Two contact parallel connections of first relay 23 and second relay 24, output dry contact signal.
ATWT rack 40 comprises that the coiler part of the 3rd relay 44, the three relays 44 is connected with parallel connection place of first relay 23 and second relay 24, and the contact of the 3rd relay 44 is connected with first logical circuit 41.Promptly the contact signal at first relay 23 and second relay, 24 parallel connection places is controlled the current switching of the 3rd relay 44 coils, and the 3rd relay 44 coils are by the DC power supply of 48V, and the 3rd relay 44 coil contact switchs are by the DC-voltage supply of 24V.The contact out-put supply dead electricity signal of the 3rd relay 44, power supply dead electricity signal through the logical process of the first logical and circuit 42 after control ATWT driver module 43 whether ATWT takes place.
Preferred embodiment of the present invention prevents that the concrete internal logic of the system that nuclear power station ATWT rack mistake drives is as shown in Figure 5; The signal that main feedwater flow control signal acquisition module 10 is gathered is mainly among the RPC (reactor protection cabinet four-way rack); Feedwater flow control system among the RPC comprises feedwater flow sensor 049,050 and 051; Come the flow of three steam generators in the detection reaction heap protection cabinet four-way rack through the feedwater flow sensor; Three steam generator flow low signals are in twos through obtaining three signals behind the AND circuit; These three signals obtain final main feedwater flow signal through OR circuit again, and main feedwater flow signal is 1 o'clock, represent that main feedwater flow is lower than 6%NF.Obtain RPC output signal, i.e. first signal through an AND circuit again from the power supply dead electricity signal of RPC collection and final main feedwater flow signal.
Nuclear instrument signal acquisition module 30 comprises a channel signal processing unit, two channel signal processing units and the 3rd logical and circuit; Wherein, One channel signal processing unit is used for range, test pattern and the fault-signal of nuclear instrument system one passage are passed through to export a channel signal behind the OR circuit; Two channel signal processing units are used for range, test pattern and the fault-signal of nuclear instrument system two passages are passed through to export two channel signals behind the OR circuit; The 3rd logical and circuit is used for a channel signal and two channel signals are examined instrument signal (RPN signal) through output behind the AND circuit, and the RPN signal is 1 o'clock, and range nuclear power is greater than 30%FP in the middle of the expression nuclear power station.RPN signal and RPC output signal (i.e. first signal) are again through an AND circuit, and utilizing the signal of this AND circuit output is secondary signal, control ATWT driver module.
The hard logic module that all logical devices in the logical diagram as shown in Figure 5 all adopt analog component to be barricaded as realizes.ATWT be electronic work, when the RPC power supply just often, power supply dead electricity signal is a high level 1; When RPC rack dead electricity, power supply dead electricity signal is a low level 0, and RPC output signal must be low level 0, thereby the misoperation of ATWT is effectively suppressed.
The present invention gathers the power supply dead electricity signal of RPC rack through power supply dead electricity signal acquisition module 20; The main feedwater flow signal of being gathered, nuclear instrument signal and power supply dead electricity signal are handled through first logical circuit 41 and second logical circuit 42; Utilize the signal of second logical circuit, 42 outputs to drive ATWT driver module 43, thereby the misoperation of ATWT is effectively suppressed.
The present invention also provides and prevented nuclear power station ATWT rack mistake method of driving, and is as shown in Figure 6, comprises step:
S1, the main feedwater flow signal of collection and nuclear instrument signal.Main feedwater flow signal is that three steam generator flow low signals are got the signal of two logics output through three; The feedwater flow control system that is specially among the RPC IVP comprises feedwater flow sensor 049,050 and 051; Come the flow of three steam generators among the detection reaction heap protection cabinet RPC through the feedwater flow sensor; Three steam generator flow low signals in twos with after obtain three signals, these three signals again through or door obtain final main feedwater flow signal.From RPN IP and RPN IIP, gather the nuclear instrument signal; With range signal, test mode signal and fault-signal among the RPN IP (nuclear instrument system one passage) through one or door output RPN IP signal; Likewise; Range signal, test mode signal and fault-signal among the RPN IIP (nuclear instrument system two passages) also through one or door output RPN IIP signal, are exported a RPN signal through one with door with RPN IP signal and RPN IIP signal at last again, promptly examine instrument signal.
S2, from RPC, gather the power supply dead electricity signal of RPC rack; Power supply dead electricity signal is the dead electricity signal of primary power or standby power supply in the RPC rack, when power supply dead electricity signal is high level 1, shows that the power supply of RPC rack is normal; When power supply dead electricity signal is low level 0, show that the power supply of RPC rack is undesired.ATWT be electronic work, when RPC rack power supply just often, power supply dead electricity signal is a high level 1; When RPC rack dead electricity, power supply dead electricity signal is a low level 0, and RPC rack output signal must be low level 0, thereby the misoperation of ATWT is effectively suppressed.
S3, power supply dead electricity signal and main feedwater flow signal are handled back output first signal through first logical and;
S4, in the ATWT rack, first signal and nuclear instrument signal are handled back output secondary signal through second logical and, secondary signal is used to control the ATWT rack whether ATWT takes place.When supplying power just often; Be that power supply dead electricity signal is 1; And main feedwater flow signal is at 1 o'clock with the nuclear instrument signal, and this moment, first signal and secondary signal were 1, and ATWT then takes place; ATWT protection action promptly takes place, and comprises shutdown, shutdown, startup auxiliary feedwater and the 3rd group of GCT bleed valve of locking etc.
Further, preferred embodiment of the present invention prevents that the concrete steps of gathering power supply dead electricity signal are in the nuclear power station ATWT rack mistake method of driving:
First relay in the RPC rack is connected with primary power; Second relay in the RPC rack is connected with standby power supply; Two contact parallel connections of first relay and second relay; Primary power and standby power supply are respectively the coil power supply in first relay and second relay, two contact parallel connections of first relay and second relay, output dry contact signal.The contact signal at parallel connection place is the current switching that the dry contact signal is used for controlling the 3rd relay coil in the diversified rack, and the signal of the output of the 3rd relay contact is a power supply dead electricity signal.
Should be understood that, concerning those of ordinary skills, can improve or conversion, and all these improvement and conversion all should belong to the protection domain of accompanying claims of the present invention according to above-mentioned explanation.

Claims (10)

1. one kind prevents nuclear power station trip protection system tripping ATWT rack mistake method of driving, comprises step: gather main feedwater flow signal and nuclear instrument signal, it is characterized in that, also comprise step:
Gather the power supply dead electricity signal of reactor protection rack;
With said power supply dead electricity signal and said main feedwater flow signal through with logical process after output first signal;
With said first signal and said nuclear instrument signal through with logical process after export secondary signal, and confirm whether to take place ATWT according to said secondary signal.
2. the nuclear power station trip protection system tripping ATWT rack mistake method of driving that prevents according to claim 1 is characterized in that said power supply dead electricity signal is at 1 o'clock, and the power supply of expression RPC rack is normal; Said main feedwater flow signal is 1 o'clock, and range nuclear power is greater than 30%Pn in the middle of the expression nuclear power station; Said main feedwater flow signal is 1 o'clock, representes that main feedwater flow is lower than 6%NF; At said power supply dead electricity signal is 1 o'clock, and said main feedwater flow signal and said nuclear instrument signal be at 1 o'clock, and this moment, said first signal and said secondary signal were 1, produced the ATWT signal, and the ATWT protection takes place the ATWT rack.
3. the nuclear power station trip protection system tripping ATWT rack mistake method of driving that prevents according to claim 2 is characterized in that, said power supply dead electricity signal is the dead electricity signal of primary power or standby power supply in the said reactor protection rack.
4. the nuclear power station trip protection system tripping ATWT rack of stating according to claim 3 that prevents misses method of driving, it is characterized in that, said main feedwater flow signal is that three steam generator flow low signals are got the signal of two logics output through three.
5. the nuclear power station trip protection system tripping ATWT rack of stating according to claim 4 that prevents misses method of driving; It is characterized in that said collection nuclear instrument signal is specially: range, test pattern and the fault-signal that will examine in instrument system one passage are exported a channel signal through OR circuit; Simultaneously, range, test pattern and fault-signal in nuclear instrument system two passages are also exported two channel signals through OR circuit; A said channel signal and two channel signals are exported said nuclear instrument signal through AND circuit again.
6. one kind prevents the nuclear power station trip protection system tripping ATWT rack system of driving by mistake; Comprise reactor protection rack, main feedwater flow signal acquisition module (10), nuclear instrument signal acquisition module (30) and ATWT rack (40); Said reactor protection rack comprises primary power (21) and standby power supply (22); It is characterized in that this system also comprises: power supply dead electricity signal acquisition module (20) is used to gather the power supply dead electricity signal of said reactor protection rack; Said ATWT rack (40) comprises the first logical and circuit (41), the second logical and circuit (42) and ATWT driver module (43);
The said first logical and circuit (41), the main feedwater flow signal that is used for said power supply dead electricity signal and said main feedwater flow signal acquisition module (10) are gathered is handled back output first signal through AND circuit;
The said second logical and circuit (42); The nuclear instrument signal that is used for said first signal and said nuclear instrument signal acquisition module (30) are gathered is handled back output secondary signal through AND circuit, and said secondary signal is used to control said ATWT driver module whether ATWT (43) takes place.
7. the system that prevents that nuclear power station trip protection system tripping ATWT rack mistake from driving according to claim 6 is characterized in that, is 1 o'clock at said power supply dead electricity signal, and ATWT takes place the emergency shut-down of said ATWT rack.
8. the system that prevents that nuclear power station trip protection system tripping ATWT rack mistake from driving according to claim 7; It is characterized in that; Said power supply dead electricity signal acquisition module (20) comprises first relay (23) that is connected with said primary power (21) and second relay (24) that is connected with said standby power supply (22), two contact parallel connections of said first relay (23) and said second relay (24);
Said ATWT rack (40) comprises the 3rd relay (44); The coiler part of said the 3rd relay (44) is connected with parallel connection place of said first relay (23) with said second relay (24), and the contact of said the 3rd relay (44) is connected with the said first logical and circuit (41).
9. the system that prevents that nuclear power station trip protection system tripping ATWT rack mistake from driving according to claim 8; It is characterized in that; Main feedwater flow signal acquisition module (10) comprises three flow sensors (049,050 and 051); The flow that is used for three steam generators of detection reaction heap protection cabinet four-way rack; In twos through obtaining three signals behind the AND circuit, these three signals are again through obtaining said main feedwater flow signal behind the OR circuit with detected three steam generator flow low signals for said three flow sensors (049,050 and 051).
10. the system that prevents that nuclear power station trip protection system tripping ATWT rack mistake from driving according to claim 9; It is characterized in that; Nuclear instrument signal acquisition module comprises a channel signal processing unit, two channel signal processing units and the 3rd logical and circuit, wherein:
A said channel signal processing unit is used for range signal, test mode signal and the fault-signal of nuclear instrument system one passage are passed through to export a channel signal behind the OR circuit;
Said two channel signal processing units are used for range signal, test mode signal and the fault-signal of nuclear instrument system two passages are passed through to export two channel signals behind the OR circuit;
Said the 3rd logical and circuit is used for a said channel signal and said two channel signals are passed through to export said nuclear instrument signal behind the AND circuit.
CN201110164273.6A 2011-06-17 2011-06-17 Method and system for preventing error drive of ATWT (Anticipated Transients without Trip) equipment cabinet Active CN102324258B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201110164273.6A CN102324258B (en) 2011-06-17 2011-06-17 Method and system for preventing error drive of ATWT (Anticipated Transients without Trip) equipment cabinet

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201110164273.6A CN102324258B (en) 2011-06-17 2011-06-17 Method and system for preventing error drive of ATWT (Anticipated Transients without Trip) equipment cabinet

Publications (2)

Publication Number Publication Date
CN102324258A true CN102324258A (en) 2012-01-18
CN102324258B CN102324258B (en) 2014-06-04

Family

ID=45451983

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201110164273.6A Active CN102324258B (en) 2011-06-17 2011-06-17 Method and system for preventing error drive of ATWT (Anticipated Transients without Trip) equipment cabinet

Country Status (1)

Country Link
CN (1) CN102324258B (en)

Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103400623A (en) * 2013-07-30 2013-11-20 中广核工程有限公司 Protection method and system for digitalized instrument control diversity of nuclear power station
CN103499958A (en) * 2013-09-30 2014-01-08 中国神华能源股份有限公司 Method and device for controlling MFT (Main Fuel Trip)
CN103700414A (en) * 2013-12-10 2014-04-02 中广核工程有限公司 Diversity driving system and method for nuclear power plant
CN103985421A (en) * 2014-05-06 2014-08-13 中科华核电技术研究院有限公司 Method for improving security of nuclear power unit during failure of emergency shut-down of reactor
CN104332188A (en) * 2013-07-22 2015-02-04 中国核动力研究设计院 Method for alleviating primary loop overpressure during normal feedwater fail-ATWS (Anticipated Transients Without Scram) accident
CN104348132A (en) * 2013-08-09 2015-02-11 中核核电运行管理有限公司 External power supply interlocking controller of reactor protection system
CN104348133A (en) * 2013-08-09 2015-02-11 中核核电运行管理有限公司 Internal power supply interlocking controller of reactor protection system
CN108022662A (en) * 2016-11-03 2018-05-11 斗山重工业株式会社 Nuclear plant digital protects system
CN108242271A (en) * 2016-12-27 2018-07-03 中广核研究院有限公司 A kind of reactor virtual protection control device and its corresponding protection system
CN111292862A (en) * 2020-03-27 2020-06-16 江苏核电有限公司 Emergency reactor shutdown method based on signal state of safety important instrument of nuclear power plant
CN111681792A (en) * 2020-05-14 2020-09-18 岭东核电有限公司 ATWT control device and nuclear power equipment

Citations (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0202052A2 (en) * 1985-05-09 1986-11-20 Westinghouse Electric Corporation Auxiliary reactor protection system and method
US4697093A (en) * 1985-01-23 1987-09-29 Westinghouse Electric Corp. Testable, fault-tolerant power interface circuit for controlling plant process equipment
US4717532A (en) * 1985-06-26 1988-01-05 Westinghouse Electric Corp. Pressure control system for a pressurized water nuclear reactor plant
US5139735A (en) * 1990-07-10 1992-08-18 General Electric Company Reactivity control system
US5586156A (en) * 1995-07-14 1996-12-17 General Electric Company Reactor protection system with automatic self-testing and diagnostic
WO1997004463A1 (en) * 1995-07-14 1997-02-06 General Electric Company Reactor protection system
CN1626007A (en) * 2003-12-12 2005-06-15 乐金电子(天津)电器有限公司 Device for displaying powerdown in electric cooker and method
CN101106267A (en) * 2007-06-11 2008-01-16 上海外高桥第三发电有限责任公司 Unit thermal control intelligent protection system
CN102157208A (en) * 2010-11-12 2011-08-17 中广核工程有限公司 Nuclear power plant reactor protection system

Patent Citations (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4697093A (en) * 1985-01-23 1987-09-29 Westinghouse Electric Corp. Testable, fault-tolerant power interface circuit for controlling plant process equipment
EP0202052A2 (en) * 1985-05-09 1986-11-20 Westinghouse Electric Corporation Auxiliary reactor protection system and method
US4752869A (en) * 1985-05-09 1988-06-21 Westinghouse Electric Corp. Auxiliary reactor protection system
US4717532A (en) * 1985-06-26 1988-01-05 Westinghouse Electric Corp. Pressure control system for a pressurized water nuclear reactor plant
US5139735A (en) * 1990-07-10 1992-08-18 General Electric Company Reactivity control system
US5586156A (en) * 1995-07-14 1996-12-17 General Electric Company Reactor protection system with automatic self-testing and diagnostic
WO1997004463A1 (en) * 1995-07-14 1997-02-06 General Electric Company Reactor protection system
CN1626007A (en) * 2003-12-12 2005-06-15 乐金电子(天津)电器有限公司 Device for displaying powerdown in electric cooker and method
CN101106267A (en) * 2007-06-11 2008-01-16 上海外高桥第三发电有限责任公司 Unit thermal control intelligent protection system
CN102157208A (en) * 2010-11-12 2011-08-17 中广核工程有限公司 Nuclear power plant reactor protection system

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
曹建亭: "采用DCS实现核电站多样性保护控制分析", 《现代电力》, vol. 24, no. 06, 10 December 2007 (2007-12-10) *
郭城: "大亚湾及岭澳核电站ATWT保护失电风险", 《核动力工程》, vol. 31, no. 04, 31 August 2010 (2010-08-31) *

Cited By (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104332188A (en) * 2013-07-22 2015-02-04 中国核动力研究设计院 Method for alleviating primary loop overpressure during normal feedwater fail-ATWS (Anticipated Transients Without Scram) accident
CN103400623A (en) * 2013-07-30 2013-11-20 中广核工程有限公司 Protection method and system for digitalized instrument control diversity of nuclear power station
CN104348133B (en) * 2013-08-09 2017-07-18 中核核电运行管理有限公司 Reactor protection system internal electric source interlocking controller
CN104348132B (en) * 2013-08-09 2017-07-18 中核核电运行管理有限公司 Reactor protection system external power source interlocking controller
CN104348132A (en) * 2013-08-09 2015-02-11 中核核电运行管理有限公司 External power supply interlocking controller of reactor protection system
CN104348133A (en) * 2013-08-09 2015-02-11 中核核电运行管理有限公司 Internal power supply interlocking controller of reactor protection system
CN103499958A (en) * 2013-09-30 2014-01-08 中国神华能源股份有限公司 Method and device for controlling MFT (Main Fuel Trip)
CN103700414B (en) * 2013-12-10 2017-02-22 中广核工程有限公司 Diversity driving system and method for nuclear power plant
CN103700414A (en) * 2013-12-10 2014-04-02 中广核工程有限公司 Diversity driving system and method for nuclear power plant
CN103985421B (en) * 2014-05-06 2016-09-28 中广核研究院有限公司 The method that reactor fails to improve nuclear power generating sets safety during emergency shut-down
CN103985421A (en) * 2014-05-06 2014-08-13 中科华核电技术研究院有限公司 Method for improving security of nuclear power unit during failure of emergency shut-down of reactor
CN108022662A (en) * 2016-11-03 2018-05-11 斗山重工业株式会社 Nuclear plant digital protects system
CN108022662B (en) * 2016-11-03 2021-06-29 斗山重工业株式会社 Digital protection system of nuclear power station
CN108242271A (en) * 2016-12-27 2018-07-03 中广核研究院有限公司 A kind of reactor virtual protection control device and its corresponding protection system
CN111292862A (en) * 2020-03-27 2020-06-16 江苏核电有限公司 Emergency reactor shutdown method based on signal state of safety important instrument of nuclear power plant
CN111292862B (en) * 2020-03-27 2021-12-17 江苏核电有限公司 Emergency reactor shutdown method based on signal state of safety important instrument of nuclear power plant
CN111681792A (en) * 2020-05-14 2020-09-18 岭东核电有限公司 ATWT control device and nuclear power equipment

Also Published As

Publication number Publication date
CN102324258B (en) 2014-06-04

Similar Documents

Publication Publication Date Title
CN102324258B (en) Method and system for preventing error drive of ATWT (Anticipated Transients without Trip) equipment cabinet
US20120283890A1 (en) Control Apparatus for Micro-grid Connect/Disconnect from Grid
CN102157208B (en) Nuclear power plant reactor protection system
CN104158394A (en) Auto-starting control method for photovoltaic inverter
US10541059B2 (en) Digital protection system for nuclear power plant
CN102426863A (en) Signal transmission system and method of reactor in nuclear station
CN111431147B (en) Fault switching system and method for valve control system protection device of flexible direct current converter valve
CN102298980A (en) Protection exit method for million-kilowatt digital nuclear power plant reactor
US9620252B2 (en) Island mode for nuclear power plant
EP2589758B1 (en) Fault tolerant turbine speed control system
US20150333504A1 (en) Protection Device for DC Collection Systems
CN103700411A (en) Method and system for dealing with loss of coolant accident (LOCA) of nuclear power station
CN111681792B (en) ATWT control device and nuclear power equipment
EP2602794B1 (en) Control system for nuclear power plant
US8090073B2 (en) Nuclear power plant, method of replacement in the same and method of operating the same
KR101681978B1 (en) Reactor Protection System Having Different Kind of Control Apparatus
CN104332186A (en) Reactor safe shutdown method
CN113658733B (en) Control system device of nuclear turbine and control method thereof
CN104348133B (en) Reactor protection system internal electric source interlocking controller
CN108063546B (en) Low-voltage ride through power supply control system of frequency converter
CN102003373A (en) Joint inspection device of drainage pump and pump station generating set under high-speed rail and in tunnel
CN105470990B (en) High-power direct drive permanent magnetic wind generator system low-voltage crossing control system and control method
CN203813429U (en) Signal lightning arrester being capable of on-line detection
CN107947736B (en) Photovoltaic power generation elastic control device and control method thereof
CN201763396U (en) Apparatus for combined tour inspection on draining pumps below high-speed rail and of tunnel and generating set of pumping station

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant
CP01 Change in the name or title of a patent holder

Address after: 518023 No. 69 Shennan Middle Road, Shenzhen, Guangdong, Futian District

Co-patentee after: CHINA GENERAL NUCLEAR POWER Corp.

Patentee after: CHINA NUCLEAR POWER ENGINEERING Co.,Ltd.

Address before: 518023 No. 69 Shennan Middle Road, Shenzhen, Guangdong, Futian District

Co-patentee before: CHINA GUANGDONG NUCLEAR POWER GROUP Co.,Ltd.

Patentee before: CHINA NUCLEAR POWER ENGINEERING Co.,Ltd.

CP01 Change in the name or title of a patent holder