CN103811081A - Method and device for preventing maloperation of safety protection system of nuclear power station - Google Patents
Method and device for preventing maloperation of safety protection system of nuclear power station Download PDFInfo
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- CN103811081A CN103811081A CN201210457594.XA CN201210457594A CN103811081A CN 103811081 A CN103811081 A CN 103811081A CN 201210457594 A CN201210457594 A CN 201210457594A CN 103811081 A CN103811081 A CN 103811081A
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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- 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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention is applicable to the technical field of mega-kilowatt class pressurized water reactor nuclear power stations, and provides a method and a device for preventing maloperation of a safety protection system of a nuclear power station. The method comprises the following steps of collecting a first time, wherein the first time is the time of duration of a high pressure difference signal of steam pressure between steam generator pipelines of the nuclear power station when an electric network has the instantaneous malfunction; acquiring a second time, wherein the second time is the time of maximal damp of a pressure transmitter in safety redundancy; setting the damping time of the pressure transmitter within the range from the first time to the second time; comparing the time of duration of the high pressure difference signal of the steam pressure between the steam generator pipelines of the nuclear power station with the damping time of the pressure transmitter when the high pressure difference signal of the steam pressure between the steam generator pipelines of the nuclear power station is generated, and controlling the safety protection system of the nuclear power station to act according to a comparison result. By adopting the method and the device, the problem of the maloperation of the safety protection system of the nuclear power station caused by the instantaneous malfunction of the electric network can be avoided.
Description
Technical field
The invention belongs to million kilowatt advanced pressurized water reactor nuclear power plant key technology area, relate in particular to a kind of method and apparatus that prevents the nuclear plant safety protection system malfunction that electrical network transient fault causes.
Background technology
The reactor of million kilowatt advanced pressurized water reactor nuclear power plant is ad hoc safety system (as safety injection system etc.).The function of this safety system is: in the time breaking in the carbonated drink loop of a loop generation dehydration fault or secondary circuit; according to system pressure drop situation; to the BAS of a loop moisturizing or injection high concentration, to complete the emergent refrigerating function of reactor core, guarantee nuclear plant safety.
The trigger pip of this safety system comprises the high signal of the pressure reduction of vapor pressure between steam generator jet chimney, because the high signal of the differential pressure of vapor pressure is one of factor of whether breaking of the carbonated drink loop for judging secondary circuit between steam generator jet chimney.Wherein between steam generator jet chimney, the high signal of the pressure reduction of vapor pressure refers to that the difference of the vapor pressure between the each jet chimney of steam generator is higher than the signal of predetermined threshold value.Because steam generator is to the various jet chimney length differences of steam turbine steam chest, therefore, in the time there is ringing in the operating mode of nuclear power station secondary loop, easily produce the high signal of pressure reduction of vapor pressure between steam generator jet chimney, and cause the safety injection system action of 1,000,000 grades of pressurized-water reactor nuclear power plants.
And in electrical network generation transient fault, during as three-phase or double earthfault, can cause near the load of the genset in trouble spot to occur fluctuation, and there is ringing in the operating mode that causes nuclear power station secondary loop, when serious, to produce the high signal of pressure reduction of vapor pressure between steam generator jet chimney, and cause the safety injection system action of 1,000,000 grades of pressurized-water reactor nuclear power plants.In the time of electrical network generation transient fault, also may produce the high signal of pressure reduction of vapor pressure between steam generator jet chimney, therefore, also may cause the safety injection system action of the reactor of pressurized-water reactor nuclear power plant, i.e. electrical network generation transient fault may cause the safety injection system malfunction of the reactor of pressurized-water reactor nuclear power plant.After safety injection system action due to the reactor of pressurized-water reactor nuclear power plant, equipment in pressurized-water reactor nuclear power plant and raw material are caused damage, therefore, how to avoid the malfunction of the safety injection system of the reactor of pressurized-water reactor nuclear power plant to become technical barrier anxious to be resolved.
Summary of the invention
The object of the embodiment of the present invention is to provide a kind of method that prevents the nuclear plant safety protection system malfunction that electrical network transient fault causes, and is intended to solve the problem of the nuclear plant safety protection system malfunction that prior art exists causes due to electrical network transient fault.
The embodiment of the present invention is achieved in that a kind of method that prevents the malfunction of nuclear plant safety protection system, and described method comprises:
Gather the very first time, the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure when the described very first time is electrical network generation transient fault;
Obtained for the second time, described the second time is the maximum damping time of safe margin internal pressure transmitter;
To be arranged on the very first time damping time of pressure unit in the scope of the second time;
In the time producing the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure; the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure and the damping time of pressure unit are compared, and according to the action of comparative result control nuclear plant safety protection system.
Another object of the embodiment of the present invention is to provide a kind of device that prevents the malfunction of nuclear plant safety protection system, and described device comprises:
Very first time collecting unit, for gathering the very first time, the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure when the described very first time is electrical network generation transient fault;
The second time acquisition unit, for obtaining for the second time, described the second time is the maximum damping time of safe margin internal pressure transmitter;
Damping time setting unit, for being arranged on the very first time damping time of pressure unit in the scope of the second time;
Peace note control module; for in the time producing the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure; the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure and the damping time of pressure unit are compared, and according to the action of comparative result control nuclear plant safety protection system.
In embodiments of the present invention; when being set to electrical network generation transient fault the damping time of pressure unit within the scope of the duration of the high signal of pressure reduction and the maximum damping time of safe margin internal pressure transmitter of nuclear power station steam generator pipeline enclosure vapor pressure, thereby avoid the problem of the nuclear plant safety protection system malfunction that electrical network generation transient fault causes.
Accompanying drawing explanation
Fig. 1 is the realization flow figure of the method that prevents the nuclear plant safety protection system malfunction that electrical network transient fault causes that provides of the embodiment of the present invention;
Fig. 2 is the realization flow figure of collection very first time of providing of the embodiment of the present invention;
Fig. 3 is the structured flowchart of the device that prevents the nuclear plant safety protection system malfunction that electrical network transient fault causes that provides of the embodiment of the present invention;
Fig. 4 is the structured flowchart of the very first time collecting unit in Fig. 4 of providing of the embodiment of the present invention.
Embodiment
In order to make object of the present invention, technical scheme and advantage clearer, below in conjunction with drawings and Examples, the present invention is further elaborated.Should be appreciated that specific embodiment described herein, only in order to explain the present invention, is not intended to limit the present invention.
In embodiments of the present invention; when being set to electrical network generation transient fault the damping time of pressure unit within the scope of the duration of the high signal of pressure reduction and the maximum damping time of safe margin internal pressure transmitter of nuclear power station steam generator pipeline enclosure vapor pressure; thereby can filter the high signal of pressure reduction of vapor pressure between the steam generator pipe measuring, thereby avoid the problem of the nuclear plant safety protection system malfunction causing due to electrical network transient fault.
For technical solutions according to the invention are described, describe below by specific embodiment.
The method of the nuclear plant safety protection system malfunction that electrical network transient fault that what Fig. 1 showed that the embodiment of the present invention provides prevent causes, details are as follows:
S101, gathers the very first time, the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure when this very first time is electrical network generation transient fault.
Wherein electrical network generation transient fault refers to the fault that the genset outlet voltage transient in nuclear power station generating plant declines.This electrical network generation transient fault includes but not limited to electrical network generation two-phase or three-phase ground fault or the electrical network fault etc. that is short-circuited.
The difference of the high signal indication nuclear power station steam generator of the pressure reduction pipeline enclosure vapor pressure of nuclear power station steam generator pipeline enclosure vapor pressure is higher than default threshold pressure differential.Illustrate as follows:
Steam generator in suppose core power station is provided with 3 main pipelines, 3 pressure units are all installed on each main pipeline, 007MP, 010MP and 013MP totally 3 pressure units are installed on a main pipeline as supposed, 008MP, 011MP and 014MP totally 3 pressure units are installed on No. two main pipelines, 009MP, 012MP and 015MP totally 3 pressure units are installed on No. three main pipelines.
Above-mentioned 9 pressure units in steam generator are divided into three groups, and one group is 007MP, 008MP and 009MP, and two groups is 010MP, 011MP and 012MP, and three groups is 013MP, 014MP and 015MP.Every group of pressure unit compared between two, obtain the comparative result of this group pressure unit, this comparative result is to judge according to this group pressure unit whether the high signal of pressure reduction of vapor pressure between steam generator pipe produces.Illustrate as follows:
For the pressure unit 007MP in a group, 008MP and 009M, the difference of the measured value of 007MP and 008MP and default threshold pressure differential are compared, can obtain whether producing the high signal of pressure reduction between a main pipeline and No. two main pipelines, in like manner, by the difference of the measured value of 007MP and 009MP and default threshold pressure differential are compared, can obtain whether producing the high signal of pressure reduction between a main pipeline and No. three main pipelines, by the difference of the measured value of 008MP and 009MP and default threshold pressure differential are compared, can obtain whether producing the high signal of pressure reduction between No. two main pipelines and No. three main pipelines.By above-mentioned relatively after, by 3 comparative results of getting 2 logic and obtain this group pressure unit, as when by above-mentioned relatively after, judge and at least produced two high signals of pressure reduction, as produced the high signal of pressure reduction between a main pipeline and No. two main pipelines, and between a main pipeline and No. three main pipelines, producing the high signal of pressure reduction, judging that the comparative result of this group pressure unit is as having produced the high signal of pressure reduction.For other two groups of pressure units, comparison principle is consistent, describes in detail no longer one by one at this.
Obtaining after the comparative result of each group of pressure unit, by the comparative result of these three groups of pressure units again according to the 3 high signals of pressure reduction of getting 2 logic and judge whether to produce vapor pressure between steam generator jet chimney.When having the comparative result of at least 2 group pressure units in 3 groups of pressure units for having produced the high signal of pressure reduction, judge the high signal of pressure reduction that has produced vapor pressure between steam generator jet chimney, otherwise judge the high signal of pressure reduction that does not produce vapor pressure between steam generator jet chimney.
The high signal of pressure reduction of this nuclear power station steam generator pipeline enclosure vapor pressure can be the high signal of pressure reduction of 1,000,000 grades of pressurized water reactor nuclear power station steam generator pipeline enclosure vapor pressures
The duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure refers to the lasting time of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure.The ultimate principle of duration of wherein obtaining the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure is as follows:
The pass of power and external interference power duration is: W=ft, and wherein W is power, and t is that external interference is insisted on the continuous time, and f is external interference power.Due to actual measurement to fault be once more serious fault, can be by the data of surveying in fault as reference data, f remains unchanged, the time that fault is lasting and power be varied to direct ratio estimation.Its detailed process as shown in Figure 3.
Refer to Fig. 2, the realization flow of the collection very first time providing for the embodiment of the present invention, as follows:
S301, the difference power of genset before and after detection failure.Wherein concrete detection method belongs to prior art, does not repeat them here.
S302, the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe before and after detection failure.
S303, obtains the maximum work rate variance of genset before and after fault under extreme case.
S304, according to the maximum work rate variance of genset before and after fault under the duration of the high signal of pressure reduction of vapor pressure between the difference power of genset before and after fault, fault front and back steam generator pipe and extreme case, according to the linear relationship between the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe and the difference power of steam turbine, duration of the high signal of pressure reduction of vapor pressure between steam generator pipe in nuclear power station when estimation electrical network generation transient fault.
Wherein, according to the linear relationship between the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe and the difference power of steam turbine, when estimation electrical network generation transient fault, in nuclear power station, between steam generator pipe, the duration of the high signal of pressure reduction of vapor pressure specifically comprises:
Adopt formula
duration of the high signal of pressure reduction of vapor pressure between steam generator pipe in nuclear power station when estimation electrical network generation transient fault;
Wherein T1 be estimation obtain electrical network generation transient fault time nuclear power station in duration (being also the very first time) of the high signal of pressure reduction of vapor pressure between steam generator pipe, Δ P1 is the difference power of genset before and after fault, Δ P2 is the maximum work rate variance of fault front and back genset under extreme case, and Ts is the duration of the high signal of pressure reduction of vapor pressure between the steam generator pipe of fault front and back.
In order to make the embodiment of the present invention more clear, below describe as an example of electrical network generation three-phase ground fault example:
Before and after assumed fault, actual measurement to the difference power of certain genset be 778 megawatts (MW), before and after fault actual measurement to steam generator pipe between duration of the high signal of pressure reduction of vapor pressure be 80 milliseconds (ms), under extreme case, the maximum work rate variance of genset is 993MW before and after fault, and when the electrical network generation transient fault that is estimated to, in nuclear power station, between steam generator pipe, the duration of the high signal of pressure reduction of vapor pressure is: (993 × 80)/778=0.1 second.
In another embodiment of the present invention, also can be by duration of the high signal of pressure reduction of vapor pressure between electrical network generation three-phase ground when barrier steam generator pipe in the multiple different genset of estimation, therefrom select the duration of a maximal value as the high signal of pressure reduction of vapor pressure between the final steam generator pipe detecting, therefrom select a maximal value as the very first time collecting, like this, can guarantee that the plurality of different genset all can not cause the malfunction of safety injection system.
For make to detect electrical network generation transient fault time steam generator pipe between duration of the high signal of pressure reduction of vapor pressure more accurate, in another embodiment of the present invention, the method also comprises the steps:
The duration of the high signal of pressure reduction of vapor pressure between steam generator pipe when different transient fault occurs detection of grid respectively.
Its testing process is described above, does not repeat them here.The duration of the high signal of pressure reduction of vapor pressure between steam generator pipe during as difference detection of grid generation double earthfault, the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe when electrical network generation three-phase ground fault, and electrical network duration of the high signal of pressure reduction of vapor pressure between steam generator pipe while being short-circuited fault.
Maximum duration for the high signal of pressure reduction of vapor pressure between steam generator pipe when the final electrical network detecting is short-circuited fault in the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe when different transient fault occurs electrical network, maximum very first time that conduct collects in the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe while there is different transient fault by electrical network, like this, no matter, can not cause the malfunction of safety injection system if there is which kind of transient fault in electrical network.
In order further to prevent the nonaction of the safety injection system that electrical network generation transient fault causes, in another embodiment of the present invention, the method also comprises the steps:
For detect electrical network generation transient fault time steam generator pipe between duration of the high signal of pressure reduction of vapor pressure increase default nargin, using increased after default nargin electrical network generation transient fault time steam generator pipe between duration of the high signal of pressure reduction of vapor pressure as the very first time collecting.Wherein default nargin can require arrange for the difference of security according to different nuclear power station, if default nargin can be 1/3 etc., but is not limited with this value.
In the present embodiment, the duration of the high signal of pressure reduction of the nuclear power station steam generator pipeline enclosure vapor pressure obtaining is in the manner described above generally 40 milliseconds to 80 milliseconds, and therefore, in the present embodiment, this very first time is generally 80 milliseconds.
S102, obtained for the second time, and this second time is the maximum damping time of safe margin internal pressure transmitter.Its detailed process is as follows:
During due to steam generator producer design steam generator; between steam generator pipe, the high guard signal designing requirement of the pressure reduction of vapor pressure measured value responds 63.2%(step response amplitude) time should be less than 0.4 second; suppose that its step response time parameter is T, 95%=1-e
-(T2/T), wherein T is certain value, as gets 1/2, can draw T2=1.2S.While responding 95% corresponding to measured value, should be less than 1.2S, therefore, be T2 the maximum damping time of the safe margin internal pressure transmitter getting, and the second time getting is 1.2S.
S103, will be arranged on the very first time damping time of pressure unit in the scope of the second time.
Wherein, avoid temporary disturbance signal setting for measuring the damping time of pressure unit.
In the present embodiment, be T the damping time of supposing pressure unit, and the very first time is T1, and the second time, while being T2, T damping time of pressure unit met following requirement:
T1<T<T2
In the present embodiment, because the scope of the very first time to the second time is 80 milliseconds to 1.2 seconds, therefore, can be arranged on to any one time value within the scope of 80 milliseconds to 1.2 seconds the damping time of pressure unit, but while being set to 1 second, can suppress the transient state pressure reduction that pressure unit individual character sensitive difference brings the damping time of pressure unit.
In another embodiment of the present invention, through overtesting and on-site verification, be set to 1.05 seconds the damping time of pressure unit, not only can avoid the malfunction of safety injection system, nor bring security risk can to the operation of nuclear power station.
Wherein be arranged on to the very first time damping time of pressure unit as follows to the detailed process in the scope of the second time:
Customization damping plate, is arranged on this damping plate in pressure unit;
To be arranged on the very first time damping time of pressure unit in the scope of the second time by this damping plate.
S104; in the time producing the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure; compare according to the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure and the damping time of pressure unit, and according to the action of comparative result control nuclear plant safety protection system.
In the present embodiment, in the time producing the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure, detect the time of the high signal existence of pressure reduction of this nuclear power station steam generator pipeline enclosure vapor pressure, the time that high pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure signal is existed and the damping time of pressure measurement transmitter compare, obtain comparative result, this comparative result comprises that the time of the high signal existence of the pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure is greater than, is equal to or less than the damping time of pressure measurement transmitter.
Wherein as follows according to the detailed process of the action of comparative result control nuclear plant safety protection system:
The time that the high signal of pressure reduction that is nuclear power station steam generator pipeline enclosure vapor pressure when comparative result exists, while being greater than or equal to the damping time of pressure measurement transmitter, starts nuclear plant safety protection system;
In the time that the time that the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure exists is less than the damping time of pressure measurement transmitter, do not start nuclear plant safety protection system.
In the present embodiment; the time that the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure exists when being set to the damping time of pressure measurement transmitter be greater than electrical network generation transient fault; like this; can filter out the high signal of pressure reduction of the nuclear power station steam generator pipeline enclosure vapor pressure producing due to electrical network generation transient fault, avoid the problem of the malfunction of the nuclear plant safety protection system causing because of electrical network generation transient fault.
Fig. 3 shows the structure of the device that prevents the malfunction of nuclear plant safety protection system that the embodiment of the present invention provides, and only shows for convenience of explanation the part relevant to the embodiment of the present invention.
This device can be for pressure unit, can be to run on the unit that software unit, hardware cell or software and hardware in pressure unit combine, also can be used as independently suspension member and be integrated in pressure unit or run in the application system of pressure unit.Wherein this device comprises:
Very first time collecting unit 1 is for gathering the very first time, the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure when the described very first time is electrical network generation transient fault.
Wherein electrical network generation transient fault refers to the fault that the genset outlet voltage transient in nuclear power station generating plant declines.This electrical network generation transient fault includes but not limited to electrical network generation two-phase or three-phase ground fault or the electrical network fault etc. that is short-circuited.
In the preferred embodiment of the present invention, refer to Fig. 4, this very first time collecting unit 1 specifically comprises:
The first difference power detection module 11 is for detection of the difference power of genset before and after fault;
Duration detection module 12 is for detection of the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe before and after fault;
The second difference power detection module 13 is for obtaining the maximum work rate variance of fault front and back genset under extreme case;
Duration estimation block 14 is for according to the maximum work rate variance of genset before and after fault under the duration of the high signal of pressure reduction of vapor pressure and extreme case between steam generator pipe before and after the difference power of genset before and after fault, fault, according to the linear relationship between the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe and the difference power of steam turbine, duration of the high signal of pressure reduction of vapor pressure between steam generator pipe in nuclear power station when estimation electrical network generation transient fault.
In the preferred embodiment of the present invention, this duration estimation block 14 is specifically for adopting formula
duration of the high signal of pressure reduction of vapor pressure between steam generator pipe in nuclear power station when estimation electrical network generation transient fault.
Wherein T1 be estimation obtain electrical network generation transient fault time nuclear power station in duration of the high signal of pressure reduction of vapor pressure between steam generator pipe, Δ P1 is the difference power of genset before and after fault, Δ P2 is the maximum work rate variance of fault front and back genset under extreme case, and Ts is the duration of the high signal of pressure reduction of vapor pressure between the steam generator pipe of fault front and back.
In the preferred embodiment of the present invention, this very first time collecting unit 1 is also for for multiple different genset, while estimating electrical network generation transient fault in each genset, the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe, therefrom selects a maximal value as the described very first time.
In the preferred embodiment of the present invention, this very first time collecting unit 1 is duration of the high signal of pressure reduction of vapor pressure between steam generator pipe when different transient fault occurs detection of grid respectively also; When there is different transient fault in electrical network between steam generator pipe in the duration of the high signal of pressure reduction of vapor pressure maximum one as the described very first time.
In the preferred embodiment of the present invention, this device also comprises very first time amending unit 5.When this very first time amending unit 5 is used to the electrical network generation transient fault detecting, between steam generator pipe, the duration of the high signal of pressure reduction of vapor pressure increases default nargin, using increased after default nargin electrical network generation transient fault time steam generator pipe between duration of the high signal of pressure reduction of vapor pressure as the very first time collecting.
In the present embodiment, the duration of the high signal of pressure reduction of the nuclear power station steam generator pipeline enclosure vapor pressure obtaining is in the manner described above generally 40 milliseconds to 80 milliseconds, and therefore, in the present embodiment, this very first time is generally 80 milliseconds.
The second time acquisition unit 2 is for obtaining for the second time, and described the second time is the maximum damping time of safe margin internal pressure transmitter.Its detailed process is as follows:
During due to steam generator producer design steam generator; between steam generator pipe, the high guard signal designing requirement of the pressure reduction of vapor pressure measured value responds 63.2%(step response amplitude) time should be less than 0.4 second; suppose that its step response time parameter is T, 95%=1-e
-(T2/T), wherein T is certain value, as gets 1/2, can draw T2=1.2S.While responding 95% corresponding to measured value, should be less than 1.2S, therefore, be T2 the maximum damping time of the safe margin internal pressure transmitter getting, and the second time getting is 1.2S.
Damping time, setting unit 3 was for being arranged on the very first time damping time of pressure unit in the scope of the second time.
In the present embodiment, because the scope of the very first time to the second time is 80 milliseconds to 1.2 seconds, therefore, can be arranged on to any one time value within the scope of 80 milliseconds to 1.2 seconds the damping time of pressure unit, as being set to 1 second or 1.05 seconds the damping time of pressure unit, so not only can avoid the malfunction of safety injection system, nor bring security risk can to the operation of nuclear power station.
Wherein be arranged on to the very first time damping time of pressure unit as follows to the detailed process in the scope of the second time:
Customization damping plate, is arranged on this damping plate in pressure unit;
To be arranged on the very first time damping time of pressure unit in the scope of the second time by this damping plate.
Peace note control module 4 is in the time producing the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure; the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure and the damping time of pressure unit are compared, and according to the action of comparative result control nuclear plant safety protection system.
It should be noted that said system, included unit is just divided according to function logic, but is not limited to above-mentioned division, as long as can realize corresponding function; In addition, the concrete title of each functional unit also, just for the ease of mutual differentiation, is not limited to protection scope of the present invention.
One of ordinary skill in the art will appreciate that, the all or part of step realizing in above-described embodiment method is can carry out the hardware that instruction is relevant by program to complete, described program can be being stored in a computer read/write memory medium, described storage medium.
In the present embodiment; when electrical network generation transient fault within the scope of the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure and the maximum damping time of safe margin internal pressure transmitter; thereby can filter the high signal of pressure reduction of vapor pressure between the steam generator pipe measuring, thereby avoid the problem of the nuclear plant safety protection system malfunction causing due to electrical network transient fault.
The foregoing is only preferred embodiment of the present invention, not in order to limit the present invention, all any modifications of doing within the spirit and principles in the present invention, be equal to and replace and improvement etc., within all should being included in protection scope of the present invention.
Claims (17)
1. a method that prevents the malfunction of nuclear plant safety protection system, is characterized in that, described method comprises:
Gather the very first time, the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure when the described very first time is electrical network generation transient fault;
Obtained for the second time, described the second time is the maximum damping time of safe margin internal pressure transmitter;
To be arranged on the very first time damping time of pressure unit in the scope of the second time;
In the time producing the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure; the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure and the damping time of pressure unit are compared, and according to the action of comparative result control nuclear plant safety protection system.
2. the method for claim 1, is characterized in that, described electrical network generation transient fault comprises electrical network generation two-phase or three-phase ground fault or the electrical network fault that is short-circuited.
3. the method for claim 1, is characterized in that, the described collection very first time specifically comprises:
The difference power of genset before and after detection failure;
The duration of the high signal of pressure reduction of vapor pressure between steam generator pipe before and after detection failure;
Obtain the maximum work rate variance of fault front and back genset under extreme case;
According to the maximum work rate variance of genset before and after fault under the duration of the high signal of pressure reduction of vapor pressure between the difference power of genset before and after fault, fault front and back steam generator pipe and extreme case, according to the linear relationship between the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe and the difference power of steam turbine, duration of the high signal of pressure reduction of vapor pressure between steam generator pipe in nuclear power station when estimation electrical network generation transient fault.
4. method as claimed in claim 3, it is characterized in that, according to the linear relationship between the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe and the difference power of steam turbine, when estimation electrical network generation transient fault, in nuclear power station, between steam generator pipe, the duration of the high signal of pressure reduction of vapor pressure specifically comprises:
Adopt formula
duration of the high signal of pressure reduction of vapor pressure between steam generator pipe in nuclear power station when estimation electrical network generation transient fault;
Wherein T1 be estimation obtain electrical network generation transient fault time nuclear power station in duration of the high signal of pressure reduction of vapor pressure between steam generator pipe, Δ P1 is the difference power of genset before and after fault, Δ P2 is the maximum work rate variance of fault front and back genset under extreme case, and Ts is the duration of the high signal of pressure reduction of vapor pressure between the steam generator pipe of fault front and back.
5. the method as described in claim 4 requirement, is characterized in that, the described collection very first time specifically comprises:
For multiple different genset, while estimating electrical network generation transient fault in each genset, the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe, therefrom selects a maximal value as the described very first time.
6. method as claimed in claim 4, is characterized in that, the described collection very first time specifically comprises:
The duration of the high signal of pressure reduction of vapor pressure between steam generator pipe when different transient fault occurs detection of grid respectively;
When there is different transient fault in electrical network between steam generator pipe in the duration of the high signal of pressure reduction of vapor pressure maximum one as the described very first time.
7. the method as described in claim 3 to 6 any one, is characterized in that, described method also comprises:
For detect electrical network generation transient fault time steam generator pipe between duration of the high signal of pressure reduction of vapor pressure increase default nargin, using increased after default nargin electrical network generation transient fault time steam generator pipe between duration of the high signal of pressure reduction of vapor pressure as the very first time collecting.
8. the method as described in claim 1 to 6 any one, is characterized in that, the scope of the described very first time to the second time is 80 milliseconds to 1.2 seconds.
9. the method as described in claim 1 to 6 any one, is characterized in that, is set to 1 second or 1.05 seconds the damping time of pressure unit.
10. the method as described in claim 1 to 6 any one, is characterized in that, is arranged on the very first time the described damping time by pressure unit specifically to comprise in the scope of the second time:
Customization damping plate, is arranged on described damping plate in pressure unit;
To be arranged on the very first time damping time of pressure unit in the scope of the second time by described damping plate.
11. 1 kinds prevent the device of nuclear plant safety protection system malfunction, it is characterized in that, described device comprises:
Very first time collecting unit, for gathering the very first time, the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure when the described very first time is electrical network generation transient fault;
The second time acquisition unit, for obtaining for the second time, described the second time is the maximum damping time of safe margin internal pressure transmitter;
Damping time setting unit, for being arranged on the very first time damping time of pressure unit in the scope of the second time;
Peace note control module; for in the time producing the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure; the duration of the high signal of pressure reduction of nuclear power station steam generator pipeline enclosure vapor pressure and the damping time of pressure unit are compared, and according to the action of comparative result control nuclear plant safety protection system.
12. devices as claimed in claim 11, is characterized in that, described electrical network generation transient fault comprises electrical network generation two-phase or three-phase ground fault or the electrical network fault that is short-circuited.
13. devices as claimed in claim 11, is characterized in that, described very first time collecting unit specifically comprises:
The first difference power detection module, for detection of the difference power of genset before and after fault;
Duration detection module, for detection of the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe before and after fault;
The second difference power detection module, for obtaining the maximum work rate variance of fault front and back genset under extreme case;
Duration estimation block, be used for according to the maximum work rate variance of genset before and after fault under the duration of the high signal of pressure reduction of vapor pressure between the difference power of genset before and after fault, fault front and back steam generator pipe and extreme case, according to the linear relationship between the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe and the difference power of steam turbine, duration of the high signal of pressure reduction of vapor pressure between steam generator pipe in nuclear power station when estimation electrical network generation transient fault.
14. devices as claimed in claim 13, is characterized in that, described duration estimation block is specifically for adopting formula
duration of the high signal of pressure reduction of vapor pressure between steam generator pipe in nuclear power station when estimation electrical network generation transient fault;
Wherein T1 be estimation obtain electrical network generation transient fault time nuclear power station in duration of the high signal of pressure reduction of vapor pressure between steam generator pipe, Δ P1 is the difference power of genset before and after fault, Δ P2 is the maximum work rate variance of fault front and back genset under extreme case, and Ts is the duration of the high signal of pressure reduction of vapor pressure between the steam generator pipe of fault front and back.
15. as claim 14 require as described in device, it is characterized in that, described very first time collecting unit is also for for multiple different genset, while estimating electrical network generation transient fault in each genset, the duration of the high signal of pressure reduction of vapor pressure between steam generator pipe, therefrom selects a maximal value as the described very first time.
16. devices as claimed in claim 14, is characterized in that, described very first time collecting unit is duration of the high signal of pressure reduction of vapor pressure between steam generator pipe when different transient fault occurs detection of grid respectively also; When there is different transient fault in electrical network between steam generator pipe in the duration of the high signal of pressure reduction of vapor pressure maximum one as the described very first time.
17. devices as described in claim 13 to 16 any one, is characterized in that, described device also comprises:
Very first time amending unit, while being used to the electrical network generation transient fault detecting, between steam generator pipe, the duration of the high signal of pressure reduction of vapor pressure increases default nargin, using increased after default nargin electrical network generation transient fault time steam generator pipe between duration of the high signal of pressure reduction of vapor pressure as the very first time collecting.
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| CN104282350A (en) * | 2014-08-05 | 2015-01-14 | 中国核电工程有限公司 | Control method for reducing false alarm of nuclear power station charging pump |
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| CN111282336B (en) * | 2020-02-26 | 2022-01-11 | 中广核研究院有限公司 | Control method and system for drum-shaped filter screen in circulating water filtering system of nuclear power station |
| CN111397679A (en) * | 2020-04-01 | 2020-07-10 | 江苏核电有限公司 | Main steam flow measuring device of nuclear power plant and measuring method thereof |
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Address after: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor Applicant after: China General Nuclear Power Corporation Applicant after: Dayawan Nuclear Power Running Management Co., Ltd. Address before: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor Applicant before: China Guangdong Nuclear Power Group Co., Ltd. Applicant before: Dayawan Nuclear Power Running Management Co., Ltd. |
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