CN104299661B - Transient test control method and system used in debugging and starting process of nuclear power station - Google Patents
Transient test control method and system used in debugging and starting process of nuclear power station Download PDFInfo
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- CN104299661B CN104299661B CN201410535939.8A CN201410535939A CN104299661B CN 104299661 B CN104299661 B CN 104299661B CN 201410535939 A CN201410535939 A CN 201410535939A CN 104299661 B CN104299661 B CN 104299661B
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- 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
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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
- 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
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Abstract
The invention discloses a transient test control method and system used in a debugging and starting process of a nuclear power station, which are used for solving the technical problems in the prior art that the program is complicated, guiding points and operation sheets are excessive and the execution efficiency is low when SOP (State Occurrence Procedure) of a unit of the nuclear power station is used for processing a single nuclear power accident, so that the whole accident processing efficiency in a transient testing process of the nuclear power station is low; the decreasing speed of temperatures and pressure of a primary circuit is high under the special conditions without reactor core residual heat and the like during the debugging and starting process, the SOP cannot control in time, and the requirements on the control of the unit in a testing process cannot be completely met. The method comprises the following steps: starting the SOP of the unit of the nuclear power station and a transient test control regulation; carrying out accident detection on the unit of the nuclear power station through the transient test control regulation to obtain detection information; and determining an accident type of the unit of the nuclear power station based on the detection information, determining an accident processing policy based on the accident type, and intercepting a circulating execution manner of the SOP based on the processing policy, so as to carry out intervene control on the unit of the nuclear power station.
Description
Technical field
The present invention relates to the transient test control in technical field of nuclear power, more particularly to a kind of nuclear power station debugging start-up course
Method and system.
Background technology
Pressurized-water reactor nuclear power plant is mainly made up of the part such as pressurized water reactor, primary Ioops system and secondary coolant circuit system, primary Ioops
System one is connected to reactor core, and other end is connected to steam generator, wherein, steam generator is connected with secondary coolant circuit system.
During nuclear power station generates electricity, pressurized water reactor carries out nuclear fission reaction by the reactor core that low-enrichment uranium is constituted, and discharges big
The heat energy of amount;Cooling water (hereinafter referred to as primary Ioops water) in primary Ioops system flows through reactor core, takes the heat energy of reactor core out of out-pile,
And flow to steam generator;Hoarding in a vapor generator has light water (hereinafter referred to as secondary circuit water), by heat transfer process one
The heat transfer of Loop Water produces Steam Actuation steam turbine generator and generates electricity after being heated to secondary circuit water, secondary circuit water.
Because the security requirement generated electricity to nuclear power station is very high, before the formal business's fortune of nuclear power station, need to nuclear power station
Each composition system carry out single system debugging, including:Cold examination, heat examination, charging, red switch is grid-connected, a series of debugging such as generating,
So that it is guaranteed that unit being capable of safe and reliable operation.Wherein heat examination is the most key link to before reactor reaction cartridge material.
Great transient test during heat examination is specifically included:COC tests, BAS tests and peace note test;Wherein, COC tests
(I&C Power Outage Tests) is the test of nuclear power plant instrument control instrument dead electricity, is distinctive large-scale joint debugging in nuclear power station debugging
Test, the test objective is to verify safely controllable property of the nuclear power generating sets under power conditions out of hand, the instrument control instrument of nuclear power station
Table electric power system includes, to unit normally run 48V DC sources LCA that necessary instrument control instrument station-service equipment powers or
LCB, 110V DC source LBA etc.;BAS power supply switching tests (Electrical Power Supply Change Over
Tests it is) nuclear power station electrical source of power switching tests, mainly verifies that the switching of service power is suitable under the various operating modes of dead electricity
The correctness of sequence, wherein, electrical source of power is mainly power-equipment (the such as main pump, auxiliary feed water pump) power supply of nuclear power station;Safety
Injection (referred to as peace note) system is when the pipeline of reactor coolant loop or main steam system occurs break accident, there is provided heap
The emergent cooling of core, under reactor coolant loop rupture event, can prevent fuel sheath failure and ensure the geometric form of reactor core
Shape and integrity, when steam pipe line ruptures, inject high concentration boron water, and compensation causes reaction due to uncontrollably producing steam
Reactor coolant is supercool and causes volume change and the increase of reactivity, and it is during nuclear power generating sets joint debugging to pacify note test
Large-scale special project test, peace note test objective is in order to the correctness of each system auto-action, reactor jump heap after checking peace to note
Triggering, phase security shell are isolated the triggering of CIA (Containment Isolation Phase A) signal and are moved automatically accordingly
Make, and the peace beam amount adjusted during cold examination of uncapping to nuclear power generating sets is verified and come into force.
However, the great transient test during heat examination is along with the great virtual protection action of each system under test (SUT), unit
State also can be varied widely therewith, if not now being controlled set state, nuclear power generating sets equipment can be caused to damage,
Such as primary Ioops system pressure is too high causes pressurizer safety valve to be opened, and needs to be controlled by a series of technological means and surely
Determine set state, so as to during heat examination, reduce empirical risk, and can enter in the appropriate control device of links
And the serious consequence such as cause device damage, unit out of control is alleviated or avoided.
From the ridge Australia second phase, there is accident in unit or carry out in unit failure test process, prior art master
Unit, i.e. adoption status are controlled according to malfunction protocol be oriented to accident treatment program SOP (State Occurrence
Procedure), six status function parameters (subcriticality of reactor, primary Ioops water loading amount, primary Ioops pressure and temperature are selected
Degree, the integrity of the water loading amount, the integrity of steam generator and containment of steam generator) come determine Nuclear Power Accident process
Strategy.In actual moving process, although the accident kind of nuclear power station has a lot, but the physical state of nuclear power station be it is limited,
The information that nuclear power operator can be obtained by SOP in master control room, determines the physical state of reactor core;Under accident conditions, can be with
By the situation for reflecting six status function parameters of unit, the peace for choosing appropriate strategy to control unit to ensure reactor core
Entirely.For the accident for occurring, SOP constantly can sentence during detection process to above-mentioned six status function parameters
It is disconnected, and result is fed back to into operator, operator carries out accident orientation further according to the data of feedback, and corrects accident treatment plan
Slightly;It can be seen that, it is that one is big that SOP can process superposition accident (such as primary Ioops cut, while losing the Nuclear Power Accident of external power)
Advantage.
But, due to heat examination in great test belong to specific single incident, that is to say, that transient test one during heat examination
As do not result in nuclear steam supply system NSSS (Nuclear Steam Supply System) six status functions (reaction
The subcriticality of heap, primary Ioops water loading amount, primary Ioops pressure and temperature, the water loading amount of steam generator, steam generator it is complete
The integrity of whole property and containment) degrade, now stably unit be concentrated mainly on steam generator (SG) water lev el control, one time
In road temperature and Stress control and primary Ioops water content.It can be seen that, for single Nuclear Power Accident (such as losing external power) situation,
SOP repeatedly judges six status functions that the processing routine that can cause the accident is complicated simultaneously, and guiding point is more, and (i.e. SOP feeds back
It is many to the accident information of operator so that the accident probability pointed by accident information is more), operation is single more (i.e. for determination
The operation task that accident probability is carried out is more) so that it is low for the reduction of single accident treatment, loaded down with trivial details, execution efficiency, ultimately cause
Accident treatment efficiency is low;In addition, distinctive without residual heat of nuclear core situation during starting for debugging, primary Ioops temperature and pressure declines
Comparatively fast, SOP can not be controlled in time, it is impossible to the needs of complete adequacy test, in some instances it may even be possible to cause unit allocation difficulty to increase.
That is, station guide accident treatment code SOP that there is nuclear power station unit station in prior art is processing single
Program is complicated during Nuclear Power Accident, guiding point is more, the single many, execution efficiency of operation is low, and causes during nuclear power station transient test
The low technical problem of overall accident treatment efficiency, also exist debugging start during it is distinctive without residual heat of nuclear core situations such as, primary Ioops
Temperature and pressure declines comparatively fast, and SOP can not be controlled in time, it is impossible to fully meet in process of the test to the needs of unit allocation
Technical problem.
The content of the invention
The embodiment of the present application debugs transient test control method and system in start-up course by a kind of nuclear power station of offer,
Solve station guide accident treatment code SOP of nuclear power station unit station in the prior art program when single Nuclear Power Accident is processed to answer
Miscellaneous, guiding point is more, the single many, execution efficiency of operation is low, and causes the overall accident treatment efficiency during nuclear power station transient test
Low technical problem, and for debugging start during it is distinctive without residual heat of nuclear core situations such as, primary Ioops temperature and pressure decline
Comparatively fast, SOP can not be controlled in time, it is impossible to fully meet the technical problem of the needs in process of the test to unit allocation, real
Show and by the transient test control procedure the single accident occurred in heat examination transient test has efficiently been judged and done
In advance, when needed, the transient test control procedure interrupts the round-robin implementation of SOP, and the nuclear power station unit station is carried out
Intervene control, meet the treatment principle of SOP, compensate for deficiencies of the SOP in single accident treatment, the transient test control rule
Both journey and SOP are combined can more fully carry out unit failure process, and with strong points, program is held when set state is controlled
Row is succinct, smoothly and can be efficiently completed transient test.
On the one hand, the embodiment of the present application provides the transient test control method that a kind of nuclear power station is debugged in start-up course,
Methods described comprises the steps:
S1, when nuclear power station transient test starts, start nuclear power station unit station station guide accident treatment code, while opening
Move the transient test control procedure of the nuclear power station unit station;
S2, accident detection is carried out to the nuclear power station unit station by the transient test control procedure, obtain detection information;
S3, the accident pattern that the nuclear power station unit station is determined based on the detection information, and it is true based on the accident pattern
The process strategy of the fixed accident, and held based on the tactful circulation for interrupting the station guide accident treatment code of the process
Line mode, and intervention control is carried out to the nuclear power station unit station.
Optionally, when the power supply of the nuclear power station unit station is switched to accessory power supply by the front simulation in step S1 from main power source
Power switching operations when, step S3 is specifically included:
Based on the detection information determine power supply that the accident pattern of the nuclear power station unit station is the nuclear power station unit station from
Main power source is switched to the single accident of the first kind that accessory power supply causes the nuclear power station unit station primary Ioops main pump dead electricity to be stopped transport;
Based on the single accident of the first kind, the round-robin implementation of the station guide accident treatment code is interrupted, and
The standard-sized sheet signal of the auxiliary feedwater control valve of the nuclear power station unit station that resetted by control, and adjust the auxiliary feedwater control
The aperture of valve is to default aperture, while the Steam Turbine Bypass System for controlling the nuclear power station unit station stops outwards discharge steam, comes real
The temperature and pressure for now controlling the primary Ioops system of the nuclear power station is maintained at the temperature and pressure of the nuclear power station standard hot shutdown
In the range of power;
Resetted the enabling signal of the auxiliary feedwater system of the nuclear power station unit station by control, and by the auxiliary feedwater system
The feedwater flow that unite carries out auxiliary feedwater to the steam generator of the nuclear power generating sets is adjusted to minimum preset flow, while control
The blowdown flow rate of the steam generator blowdown system of the nuclear power generating sets is reduced to default blowdown flow rate to realize that controlling the steam sends out
The water level of raw device is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator adjusts water level in the SG, can
Ensure the nuclear power generating sets stable operation.
Optionally, when the power supply of the nuclear power station unit station is switched to accessory power supply by the front simulation in step S1 from main power source
Power switching operations when, step S3 also includes:
Determine that the accident pattern of the nuclear power station unit station is powered from master for the nuclear power station unit station based on the detection information
Power supply is switched to the Equations of The Second Kind list that accessory power supply causes the nuclear power station unit station primary Ioops main pump dead electricity to be powered again after stopping transport
One accident;
Based on the single accident of the Equations of The Second Kind, the round-robin implementation of the station guide accident treatment code is interrupted, and
It is default to first by adjusting the setting value of pressure of Steam Turbine Bypass System of the nuclear power station unit station before the main pump is started
Pressure value, and control the valve of the Steam Turbine Bypass System and be closed, and by the manostat of the nuclear power station unit station
Shower valve be set to automatic control mode to realize that the temperature and pressure for controlling the primary Ioops system of the nuclear power station is maintained at
In the range of the temperature and pressure of the nuclear power station standard hot shutdown;
The steam generator of the auxiliary feedwater system of the nuclear power station unit station to the nuclear power station unit station is adjusted by control
The aperture of the auxiliary feedwater control valve of auxiliary feedwater is carried out, the steam generator is obtained by the auxiliary feedwater control valve
The confluent for arriving realizes that the water level for controlling the steam generator is maintained at SG with the displacement balance of the steam generator
Adjust water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that the nuclear power generating sets are steady
Fixed operation;
After the main pump is started, by controlling the Steam Turbine Bypass System in automatic operation mode control is realized
The temperature and pressure for making the primary Ioops system is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown.
Optionally, the instrument control instrument power supply in nuclear power station unit station described in the front simulation in step S1 is for the unit
When the dead electricity of 48V DC sources is operated, step S3 is specifically included:
Determine that the accident pattern of the nuclear power station unit station is the nuclear power station unit station for described based on the detection information
The 48V DC source dead electricity of instrument control instrument power supply causes the pneumatic operated valve of the auxiliary feedwater system of the nuclear power generating sets in unit
The single accident of the 3rd class opened;
Based on the single accident of the 3rd class, the round-robin implementation of the station guide accident treatment code is interrupted, and
Stoppage in transit state is in by controlling the auxiliary feed water pump of the auxiliary feedwater system, and controls the auxiliary feedwater system to institute
Stating the steam generator of nuclear power generating sets carries out the aperture of auxiliary feedwater control valve of auxiliary feedwater, passes through the steam generator
The confluent that the auxiliary feedwater control valve gets is realized controlling the steaming with the displacement balance of the steam generator
The water level of vapour generator is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator adjusts water level in the SG,
Ensure that the nuclear power generating sets stable operation;
By the aperture for controlling to adjust the auxiliary feedwater control valve, so that the water level of the steam generator is maintained at institute
State SG to adjust water level, or realize controlling institute by controlling the auxiliary feed water pump of the auxiliary feedwater system in stoppage in transit state
The temperature and pressure for stating the primary Ioops system of nuclear power station unit station is maintained at the temperature and pressure model of the nuclear power station standard hot shutdown
In enclosing;
The manostat is isolated by the letdown line of the manostat of the control isolation primary Ioops system, and control
On fill pipeline and adjust water level realizing that the water level for controlling the manostat is maintained at voltage stabilizing;Wherein, when the water level of the manostat
When water level is adjusted in the voltage stabilizing, the nuclear power generating sets stable operation is ensure that.
Optionally, when the front simulation in step S1 triggers the operation of the peace note signal of the nuclear power station unit station, step S3
Also include:
The peace note letter that the accident pattern of the nuclear power station unit station is the nuclear power station unit station is determined based on the detection information
Number being triggered causes the safety injection system of the nuclear power station unit station to carry out Safety Injection to the primary Ioops system of the nuclear power station unit station
The single accident of the 4th class;
Based on the single accident of the 4th class, the round-robin implementation of the station guide accident treatment code is interrupted, and
It is closed by controlling the Steam Turbine Bypass System of the nuclear power station unit station, and the temperature in the primary Ioops system rises
During to preset temperature, the setting value of pressure of the Steam Turbine Bypass System is adjusted to into the second preset pressure value to realize controlling institute
The temperature and pressure for stating primary Ioops system is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;
After the nuclear power station unit station persistently carries out Safety Injection operation preset duration, the control isolation nuclear power station unit station
Boron injection tank be maintained at required value water level the water level of realizing the manostat for controlling the nuclear power station unit station;Wherein, when described
The water level of manostat ensure that the nuclear power generating sets stable operation in the required value water level;
The steam generator of the auxiliary feedwater system of the nuclear power station unit station to the nuclear power station unit station is adjusted by control
The aperture of the auxiliary feedwater control valve of auxiliary feedwater is carried out, the steam generator is obtained by the auxiliary feedwater control valve
The confluent for arriving realizes that the water level for controlling the steam generator is maintained at SG with the displacement balance of the steam generator
Adjust water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that the nuclear power generating sets are steady
Fixed operation.
On the other hand, the embodiment of the present application additionally provides the transient test control system in a kind of nuclear power station debugging start-up course
System, the system includes:
Process code start unit, for when nuclear power station transient test starts, starting the station guide of nuclear power station unit station
Accident treatment code, while starting the transient test control procedure of the nuclear power station unit station;
Detection information acquisition unit, for carrying out accident to the nuclear power station unit station by the transient test control procedure
Detection, obtains detection information;
Unit failure processing unit, for determining the accident pattern of the nuclear power station unit station based on the detection information, and
The process strategy of the accident is determined based on the accident pattern, and the station guide thing is interrupted based on the process strategy
Therefore the round-robin implementation of code is processed, and intervention control is carried out to the nuclear power station unit station.
Optionally, when nuclear power station transient test starts, and simulate the power supply of the nuclear power station unit station from main power source switching
To accessory power supply power switching operations when, the unit failure processing unit is specifically included:
First accident pattern determining module, for determining the accident pattern of the nuclear power station unit station based on the detection information
Power supply for the nuclear power station unit station is switched to accessory power supply and causes the nuclear power station unit station primary Ioops main pump dead electricity from main power source
The single accident of the first kind of stoppage in transit;
First temperature, pressure control module, for based on the single accident of the first kind, interrupting the station guide accident
Process the round-robin implementation of code, and the standard-sized sheet letter of the auxiliary feedwater control valve of the nuclear power station unit station that resets by control
Number, and the aperture of the auxiliary feedwater control valve is adjusted to default aperture, while controlling by the steam turbine of the nuclear power station unit station
Road system stopping is outside to discharge steam to realize that the temperature and pressure for controlling the primary Ioops system of the nuclear power station is maintained at described
In the range of the temperature and pressure of nuclear power station standard hot shutdown;
First SG water lev el control modules, for based on the single accident of the first kind, interrupting at the station guide accident
The round-robin implementation of reason code, and the enabling signal of the auxiliary feedwater system of the nuclear power station unit station that resetted by control, and
The auxiliary feedwater system is adjusted to into minimum to the feedwater flow that the steam generator of the nuclear power generating sets carries out auxiliary feedwater
Preset flow, while the blowdown flow rate for controlling the steam generator blowdown system of the nuclear power generating sets is reduced to default blowdown flow rate, comes
Realize that the water level of the control steam generator is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator is in institute
State SG adjust water level when, ensure that the nuclear power generating sets stable operation.
Optionally, when nuclear power station transient test starts, and simulate the power supply of the nuclear power station unit station from main power source switching
To accessory power supply power switching operations when, the unit failure processing unit is specifically included:
Second accident pattern determining module, for determining the accident pattern of the nuclear power station unit station based on the detection information
Power supply for the nuclear power station unit station is switched to accessory power supply and causes the nuclear power station unit station primary Ioops main pump dead electricity from main power source
The single accident of Equations of The Second Kind being powered again after stoppage in transit;
Second temperature pressure control module, for based on the single accident of the Equations of The Second Kind, interrupting the station guide accident
The round-robin implementation of code is processed, and before the main pump is started, by the turbine by pass for adjusting the nuclear power station unit station
The setting value of pressure of system is to the first preset pressure value, and the valve of the control Steam Turbine Bypass System is closed,
And be set to automatic control mode to realize controlling the one of the nuclear power station by the shower valve of the manostat of the nuclear power station unit station
The temperature and pressure of circuit system is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;
2nd SG water lev el control modules, for based on the single accident of the Equations of The Second Kind, interrupting at the station guide accident
The round-robin implementation of reason code, and by the auxiliary feedwater system of the control adjustment nuclear power station unit station to the nuclear power station machine
The steam generator of group carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater, makes the steam generator by the auxiliary
The confluent that water supply control valve gets is realized controlling the steam generator with the displacement balance of the steam generator
Water level be maintained at SG and adjust water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that
The nuclear power generating sets stable operation;
3rd temperature, pressure control module, for based on the single accident of the Equations of The Second Kind, interrupting the station guide accident
The round-robin implementation of code is processed, and after the main pump is started, by controlling the Steam Turbine Bypass System in automatic
Mode of operation is maintained at the temperature of the nuclear power station standard hot shutdown realizing the temperature and pressure for controlling the primary Ioops system
In pressure limit.
Optionally, when nuclear power station transient test starts, and simulate the nuclear power station unit station for instrument control instrument in the unit
When the dead electricity of the 48V DC sources that table is powered is operated, the unit failure processing unit is specifically included:
3rd accident pattern determining module, for determining the accident pattern of the nuclear power station unit station based on the detection information
The 48V DC source dead electricity for instrument control instrument power supply in the unit for the nuclear power station unit station causes the nuclear power generating sets
The single accident of the 3rd class that the pneumatic operated valve of the auxiliary feedwater system is opened;
3rd SG water lev el control modules, for based on the single accident of the 3rd class, interrupting at the station guide accident
The round-robin implementation of reason code, and stoppage in transit state is in by controlling the auxiliary feed water pump of the auxiliary feedwater system, and
Controlling the auxiliary feedwater system carries out to the steam generator of the nuclear power generating sets auxiliary feedwater control valve of auxiliary feedwater
Aperture, makes the row of the confluent that the steam generator is got by the auxiliary feedwater control valve and the steam generator
Water balance is adjusted water level realizing that the water level for controlling the steam generator is maintained at SG;Wherein, when the steam generator
Water level when the SG adjusts water level, ensure that the nuclear power generating sets stable operation;
4th temperature, pressure control module, for based on the single accident of the 3rd class, interrupting the station guide accident
The round-robin implementation of code is processed, and by controlling to adjust the aperture of the auxiliary feedwater control valve, so that the steam is sent out
The water level of raw device is maintained at the SG and adjusts water level, or by controlling the auxiliary feed water pump of the auxiliary feedwater system in stopping transport
State is stopped realizing that the temperature and pressure for controlling the primary Ioops system of the nuclear power station unit station is maintained at the nuclear power station standard hot
In the range of the temperature and pressure of heap;
First water level control of pressurizer module, for based on the single accident of the 3rd class, interrupting the station guide thing
Therefore the round-robin implementation of code is processed, and isolate the letdown line of the manostat of the primary Ioops system by control, and
Pipeline is filled on the control isolation manostat adjust water level realizing that the water level for controlling the manostat is maintained at voltage stabilizing;Its
In, when the water level of the manostat adjusts water level in the voltage stabilizing, ensure that the nuclear power generating sets stable operation.
Optionally, when nuclear power station transient test starts, and the operation of the peace note signal of the triggering nuclear power station unit station is simulated
When, the unit failure processing unit is specifically included:
4th accident pattern determining module, for determining the accident pattern of the nuclear power station unit station based on the detection information
Peace note signal for the nuclear power station unit station is triggered the safety injection system for causing the nuclear power station unit station to the nuclear power station unit station
Primary Ioops system carry out the single accident of the 4th class of Safety Injection;
5th temperature, pressure control module, for based on the single accident of the 4th class, interrupting the station guide accident
The round-robin implementation of code is processed, and is closed by controlling the Steam Turbine Bypass System of the nuclear power station unit station, and
When the temperature of the primary Ioops system rises to preset temperature, the setting value of pressure of the Steam Turbine Bypass System is adjusted to into
Two preset pressure values are maintained at the nuclear power station standard hot shutdown realizing the temperature and pressure for controlling the primary Ioops system
In the range of temperature and pressure;
Second water level control of pressurizer module, for based on the single accident of the 4th class, interrupting the station guide thing
Therefore the round-robin implementation of code is processed, and after the nuclear power station unit station persistently carries out Safety Injection operation preset duration, control
The boron injection tank of the system isolation nuclear power station unit station is maintained at the water level of realizing the manostat for controlling the nuclear power station unit station will
Evaluation water level;Wherein, when the water level of the manostat is in the required value water level, ensure that the nuclear power generating sets are stably transported
OK;
4th SG water lev el control modules, for based on the single accident of the 4th class, interrupting at the station guide accident
The round-robin implementation of reason code, and by the auxiliary feedwater system of the control adjustment nuclear power station unit station to the nuclear power station machine
The steam generator of group carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater, makes the steam generator by the auxiliary
The confluent that water supply control valve gets is realized controlling the steam generator with the displacement balance of the steam generator
Water level be maintained at SG and adjust water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that
The nuclear power generating sets stable operation.
One or more technical schemes provided in the embodiment of the present application, at least have the following technical effect that or advantage:
Due in the embodiment of the present application, by proposing a kind of transient test control for the transient test in debugging startup
Method processed, and when nuclear power station transient test starts, while starting station guide accident treatment code and the wink of nuclear power station unit station
State controlling test code, wherein, transient test control procedure is an additional transient test control procedure of SOP, for right
Nuclear power station unit station carries out accident detection and obtains detection information;Further, accident pattern is determined based on the detection information, and drafts thing
Therefore strategy is processed, and the round-robin implementation of the station guide accident treatment code is interrupted based on the process strategy, and
Intervention control is carried out to the nuclear power station unit station;The accident treatment strategy can be entered to the single accident occurred in transient test
Row efficiently judgement and intervention, efficiently solves station guide accident treatment code SOP of nuclear power station unit station in prior art
When single Nuclear Power Accident is processed, program is complicated, guiding point is more, the single many, execution efficiency of operation is low, and causes in nuclear power station transient state
The low technical problem of overall accident treatment efficiency in process of the test, and it is distinctive without residual heat of nuclear core etc. for during debugging startup
Situation, primary Ioops temperature and pressure declines comparatively fast, and SOP can not be controlled in time, it is impossible to fully meet in process of the test to machine
The technical problem of the needs of group control, compensate for deficiencies of the SOP in single accident treatment, the transient test control procedure and
Both SOP are combined, and can more fully carry out unit failure process, and the with strong points, program performing when set state is controlled
Succinctly, smoothly and transient test can be efficiently completed.
Description of the drawings
In order to be illustrated more clearly that the embodiment of the present invention or technical scheme of the prior art, below will be to embodiment or existing
The accompanying drawing to be used needed for having technology description is briefly described, it should be apparent that, drawings in the following description are only this
Inventive embodiment, for those of ordinary skill in the art, on the premise of not paying creative work, can be with basis
The accompanying drawing of offer obtains other accompanying drawings.
The one loop of nuclear power station system structure diagram that Fig. 1 is provided for the embodiment of the present application;
Fig. 2 debugs the stream of the transient test control method in start-up course for a kind of nuclear power station that the embodiment of the present application is provided
Cheng Tu;
The steam generator water level control system structure diagram of the nuclear power station that Fig. 3 is provided for the embodiment of the present application;
The auxiliary steam-operating feed pump control system structural representation of the nuclear power station that Fig. 4 is provided for the embodiment of the present application;
Relation schematic diagram is let out under filling on the manostat of the nuclear power station that Fig. 5 is provided for the embodiment of the present application;
The safety injection system structural representation of the nuclear power station that Fig. 6 is provided for the embodiment of the present application;
Fig. 7 A- Fig. 7 E debug the transient test control system in start-up course for the nuclear power station that the embodiment of the present application is provided
Structured flowchart.
Specific embodiment
The embodiment of the present application debugs the transient test control method in start-up course by a kind of nuclear power station of offer, solves
When single Nuclear Power Accident is processed, program is complicated, lead for station guide accident treatment code SOP of nuclear power station unit station in prior art
To putting, the single many, execution efficiency of many, operation is low, and causes the low skill of overall accident treatment efficiency during nuclear power station transient test
Art problem, and during debugging is started it is distinctive without residual heat of nuclear core situations such as, primary Ioops temperature and pressure decline it is very fast,
SOP can not be controlled in time, it is impossible to fully meet in process of the test to the needs of unit allocation, cause unit unmanageable
Technical problem, realize is carried out efficiently by the transient test control procedure to the single accident occurred in heat examination transient test
Ground judges and intervenes that when needed, the transient test control procedure interrupts the round-robin implementation of SOP, and to the nuclear power
Unit of standing carries out intervention control, meets the treatment principle of SOP, compensate for deficiencies of the SOP in single accident treatment, the transient state
Both controlling test code and SOP are combined can more fully carry out unit failure process, and be directed to when set state is controlled
The strong, program performing of property is succinct, smoothly and can be efficiently completed transient test, and provides ginseng for the accident treatment in actual motion
Examine the technique effect of foundation.
The technical scheme of the embodiment of the present application is to solve above-mentioned technical problem, and general thought is as follows:
The embodiment of the present application provides the transient test control method that a kind of nuclear power station is debugged in start-up course, methods described
Including:When nuclear power station transient test starts, start the station guide accident treatment code of nuclear power station unit station, while starting described
The transient test control procedure of nuclear power station unit station;Accident is carried out to the nuclear power station unit station by the transient test control procedure
Detection, obtains detection information;The accident pattern of the nuclear power station unit station is determined based on the detection information, and based on the accident
Type determines the process strategy of the accident, and interrupts the station guide accident treatment code based on the strategy that processes
Round-robin implementation, and intervention control is carried out to the nuclear power station unit station.
It can be seen that, in the embodiment of the present application, by proposing a kind of transient test for the transient test in debugging startup
Control method, and when nuclear power station transient test starts, at the same start nuclear power station unit station station guide accident treatment code and
Transient test control procedure, wherein, transient test control procedure is an additional transient test control procedure of SOP, is used for
Accident detection is carried out to nuclear power station unit station and obtains detection information;Further, accident pattern is determined based on the detection information, and is drafted
Accident treatment strategy, and the round-robin implementation that strategy interrupts the station guide accident treatment code is processed based on described,
And intervention control is carried out to the nuclear power station unit station;The accident treatment strategy can be to the single accident of appearance in transient test
Efficiently judged and intervened, efficiently solved the station guide accident treatment code of nuclear power station unit station in prior art
SOP programs when single Nuclear Power Accident is processed are complicated, guiding point is more, the single many, execution efficiency of operation is low, and cause in nuclear power station wink
The low technical problem of overall accident treatment efficiency in state process of the test, and it is distinctive without residual heat of nuclear core for during debugging startup
Situations such as, primary Ioops temperature and pressure declines comparatively fast, and SOP can not be controlled in time, it is impossible to which it is right in process of the test to fully meet
The technical problem of the needs of unit allocation, compensate for deficiencies of the SOP in single accident treatment, the transient test control procedure
Combine with both SOP, can more fully carry out unit failure process, and with strong points, program is held when set state is controlled
Row is succinct, smoothly and can be efficiently completed transient test, and provides reference frame for the accident treatment in actual motion.
In order to be better understood from above-mentioned technical proposal, below in conjunction with Figure of description and specific embodiment to upper
State technical scheme to be described in detail, it should be understood that the specific features in the embodiment of the present application and embodiment are to the application
The detailed description of technical scheme, rather than to the restriction of technical scheme, in the case where not conflicting, the application is implemented
Technical characteristic in example and embodiment can be mutually combined.
Embodiment one
In actual applications, the primary Ioops system of nuclear power station includes three loops, refer to Fig. 1, is primary Ioops system
The structural representation of one loop, including:Reactor core 101, main pump 102, manostat 103, steam generator 104 (primary Ioops side) with
And various aid systems;Wherein, aid system includes:Auxiliary steam generator 104 outwards discharges the main steam system of vapor
VVP, for the main feed system ARE (being not related in heat examination) and auxiliary feedwater system ASG of the water filling of steam generator 104;One time
Primary Ioops water 100 is injected with the pipeline of road, under the dynamic action of main pump 102, primary Ioops water 100 is ordered about in primary coolant circuit pipe
Circulation;During circulation, primary Ioops water 100 flows through the heat that reactor core 101 takes away reactor core, through heat pipe section by heat transfer
To the secondary circuit water 105 in steam generator 104.Specifically, pressure is maintained at 15.5MPa.a or so, here pressure in primary Ioops
Primary Ioops water 100 in loop can be heated to about 327.6 DEG C and not seethed with excitement under strong;327.6 DEG C of primary Ioops water flows into steam
In the heat-transfer pipe 104-1 of generator 104, and pressure in steam generator 104 is about into the secondary circuit water of 6.89MPa.a or so
105 are heated to seething with excitement (about 283.6 DEG C of temperature), form vapor, then vapor is delivered to into steam turbine by main steam system VVP
For promoting turbogenerator operating to generate electricity;The primary Ioops water 100 of heat energy is released in heat-transfer pipe 104-1 with 292.4 DEG C of left sides
Right temperature reflux completes primary Ioops circulation to reactor core 101.Due in steam generator 104 secondary circuit water 105 be heated after meeting
Be changed into vapor, auxiliary feedwater system ASG can inject water in steam generator 104, to maintain steam generator 104 in water
Position balance.
The hot functional test of nuclear power station is mainly the operation of unit when test reactor original state is hot shutdown condition
Situation, and when some great transient actions occurs in unit, for the accident that unit is likely to occur positioning analysises are carried out, and really
Accident treatment strategy is made, so as to ensure that set state maintains controllable state.Wherein, reactor hot shutdown refers to, temporary
Shutdown, (temperature is 291.4 to the running temperature and pressure during primary Ioops system (i.e. coolant system) holding Hot zero power load
DEG C, pressure is 15.5MPa.a), secondary coolant circuit system is in hot stand-by duty, at any time can (i.e. at any time can band with load carrying
Dynamic steam turbine generator work);The temperature of primary Ioops and secondary circuit is done by the waste heat of reactor core 101 and main pump 102 (i.e. cooling medium pump)
Work(is maintaining;Primary Ioops pressure is automatically controlled by manostat 103.
Before transient test is carried out, first have to carry out test preparation, i.e. test director to carry out initially by debugging routine
State is arranged, and reactor is arranged on into hot shutdown condition, also, the accuracy in order to ensure test and safety, in experiment opening
Before beginning, test director will confirm to the original state of reactor.At on-test, machine during heat examination is simulated first
The transient action that group is likely to occur, such as unit power loss, power supply switching, peace note signal are triggered, and then perform the application reality
The transient test control method step that example is debugged in start-up course there is provided a kind of nuclear power station is applied, Fig. 2 is refer to:
S201:When nuclear power station transient test starts, start the station guide accident treatment code of nuclear power station unit station, while
Start the transient test control procedure of the nuclear power station unit station;Wherein, the transient test control procedure is to be specifically designed for nuclear power
Stand transient test (including:BAS tests, the peace note test of COC test boxs) the auxiliary accident treatment program drafted, can lead with state
It is used in combination to accident treatment code SOP, efficiently completes the accident treatment during the transient test;
S202:Accident detection is carried out to the nuclear power station unit station by the transient test control procedure, detection letter is obtained
Breath;
S203:The accident pattern of the nuclear power station unit station is determined based on the detection information, and based on the accident pattern
Determine the process strategy of the accident, and the circulation that strategy interrupts the station guide accident treatment code is processed based on described
Executive mode, and intervention control is carried out to the nuclear power station unit station.
During concrete heat examination transient test, moved due to some transient states being likely to occur in unit operation can be simulated
Make, the intrinsic runtime of nuclear power station can carry out virtual protection action, but the virtual protection action of system can bring set state
Change, during such as main power source dead electricity, unit can be powered and be switched to accessory power supply from main power source by system, in this process,
Main pump dead electricity can be caused to stop transport, so as to impact to the temperature and pressure in primary Ioops system, if not being controlled consequence not
May envision.These transient actions during test is applied are accident of the unit in actual moving process;In actual applications,
When unit occurs accident, unit meeting running status is oriented to accident treatment code (SOP) and accident is detected, and determines solution
Strategy, to realize controling effectively set state.Certainly, it is exactly to simulate unit actual motion mistake that heat examination transient test is actual
The accident being likely to occur in journey, equally, can enable station guide accident treatment code (SOP) when unit is tested;In the application
In scheme, according to the experience of conventional heat examination transient test worked out it is a set of for be likely to occur in test single accident (as electricity
Source dead electricity, power supply switching etc.) carry out detecting the transient test control procedure with accident treatment;And at on-test, opening
Start the transient test control procedure while dynamic station guide accident treatment code (SOP), respectively by two accidents at
Reason code carries out accident detection to nuclear power station unit station and obtains two groups of detection informations, further, based on two groups of detection informations thing is determined
Therefore type, and draft accident treatment strategy.
That is, when transient test starts, on the one hand, it is (i.e. preprepared that test director presses debugging routine
Accident program SOP and transient test control procedure) auto-action inspection is carried out, report to the police and check, and utilize numerical control system
The instruments such as record, daily record, external monitor, the camera video recording of DCS carry out parameter testing record;On the other hand, test director
According to debugging routine to operations staff send out operational order (as test needed for operation, restore electricity), so that operations staff couple
Unit is controlled operation.That is, the running of whole transient test is:According to preprepared accident program,
Perform accidental operation, monitoring unit, restore electricity, recover unit work.
In the embodiment of the present application, the transient test control procedure can be to the single thing of appearance in heat examination transient test
Therefore efficiently judged and processed, compensate for deficiencies of the SOP in single accident treatment, transient test control procedure and state
It is oriented to accident treatment code to combine and more fully can process the unit failure in heat examination transient test, and in control
With strong points during set state, program performing is succinct, heat examination transient test can be smoothly completed, while being able to verify that SOP in machine
Whether effectively run during group accident, and reference frame is provided for the accident treatment in actual motion.
Embodiment two
Because during heat examination, reactor does not feed, therefore without residual heat of nuclear core, the heat in primary Ioops is essentially from one time
Heat produced by the main pump operation of road, after primary Ioops main pump is all stopped transport, primary Ioops will lose thermal source, can not set up nature
Circulation, if not carrying out relevant control operation, the mean temperature and pressure in primary Ioops will comparatively fast decline, and when primary Ioops are excessive
During cooling, shrink can coolant (primary Ioops water).But in this test, primary Ioops water sub-cooled is shunk, in primary Ioops
Natural Circulation can not be carried out, primary Ioops P-T region may finally be made beyond operation limit value, wink is caused to primary Ioops equipment
State is impacted..
In the present embodiment, the transient action stopped transport for main pump is tested.Specifically, start in hot function test
When, the main pump of primary Ioops system is simulated be switched to the main pump power supply of the nuclear power station unit station from main power source first all in operation
The power switching operations of accessory power supply;In practical operation, the power switching operations can be blood pressure lowering after 500KV power supplys are lost
The switching action (in actual tests be referred to as BAS56 test) of transformator to auxiliary transformer, can also be normal power source to standby
The handover operation (in actual tests be referred to as BAS57 test) of power supply, can also be to be normally to run necessary station-service to unit
The dead electricity operation (being referred to as COC53 tests in actual tests) of the 110V direct current LBA power supplys that equipment is powered;Doing these power supply switchings
During operation, the main pump in primary Ioops system can be caused all to stop transport.During test, the side of execution step S201~S202
Method (as shown in Figure 2), step S203:The accident pattern of the nuclear power station unit station is determined based on the detection information, and based on institute
The process strategy that accident pattern determines the accident is stated, and the station guide accident treatment is interrupted based on the process strategy
The round-robin implementation of code, and intervention control is carried out to the nuclear power station unit station, specifically include:
Based on the detection information determine power supply that the accident pattern of the nuclear power station unit station is the nuclear power station unit station from
Main power source is switched to the single accident of the first kind that accessory power supply causes the nuclear power station unit station primary Ioops main pump dead electricity to be stopped transport;
Based on the single accident of the first kind, the round-robin implementation of the station guide accident treatment code is interrupted, and
The standard-sized sheet signal of the auxiliary feedwater control valve of the nuclear power station unit station that resetted by control, and adjust the auxiliary feedwater control
The aperture of valve, while Steam Turbine Bypass System GCT for controlling the nuclear power station unit station stops outwards discharge steam, is come to default aperture
Realize the primary Ioops system of the control nuclear power station temperature and pressure be maintained at the nuclear power station standard hot shutdown temperature and
In pressure limit;
Resetted the enabling signal of the auxiliary feedwater system ASG of the nuclear power station unit station by control, and by it is described aid in
Water system ASG to the feedwater flow that the steam generator SG of the nuclear power generating sets carries out auxiliary feedwater is adjusted to minimum default stream
Amount, while the blowdown flow rate for controlling steam generator blowdown system APG of the nuclear power generating sets is reduced to default blowdown flow rate to realize
The water level for controlling the steam generator SG is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator SG is in institute
State SG adjust water level when, ensure that the nuclear power generating sets stable operation.
Specifically, when above-mentioned test is carried out, can be by being controlled to nuclear power generating sets in terms of three below:
(1) primary Ioops temperature and pressure control
To avoid the problem of above-mentioned primary Ioops sub-cooled triggering peace note, the primary Ioops system for controlling the nuclear power station is needed
Temperature and pressure be maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown.Lower mask body introduces primary Ioops temperature
The control method of degree and pressure:
Fig. 3 is refer to, is the water level control system structure chart of steam generator, steam generator SG is a cavity container,
Cavity inside is hoarded secondary circuit water 302;The bottom of steam generator SG is provided with heat-transfer pipe 301-1, with heat-transfer pipe 301-1 phases
Trickle in pipeline even road water 303 (arrow in Fig. 3 in pipeline indicates the flow direction of water) once, heat-transfer pipe 301-1 is used for
When contacting with primary Ioops water 303, by the heat transfer in primary Ioops water 303 to secondary circuit water 302;The side of steam generator SG
Wall bottom arranges blow-off line 301-2, for being connected with steam generator blowdown system APG;In the side wall of steam generator SG
Portion is provided with auxiliary feedwater pipeline 301-3, for being connected with auxiliary feedwater system ASG;It is provided with the top of steam generator SG
Row jet chimney 301-4, for being connected with Steam Turbine Bypass System GCT in main steam system and steam turbine generator 304;In test
During, steam turbine generator 304 does not work, main to be produced by the 301-4 connection Steam Turbine Bypass System GCT outputs of row's jet chimney
Steam.Because steam generator SG can constantly pass through GCT vent water vapors, and by APG blowdowns, in order to keep secondary circuit
In water balance, simultaneously the water of equivalent can be injected to steam generator SG by auxiliary feedwater system ASG, due to new injection
The temperature of water is relatively low, can quickly move through the heat that heat transfer obtains primary Ioops water;It can be seen that, by Steam Turbine Bypass System GCT
It is that secondary circuit water 302 takes away primary Ioops that outwards discharge vapourss and reception auxiliary feedwater system ASG supply water to steam generator SG
Two big principal elements of the heat of water 303.When primary Ioops normal work, this course of work can ensure that primary Ioops and secondary circuit
Temperature and pressure balance;But, when primary Ioops main pump is stopped transport, primary Ioops lose thermal source, if now secondary circuit is still pressed
The heat of primary Ioops is taken away according to above-mentioned working method, the heat and pressure of primary Ioops will rapid decreases.Please continue to refer to Fig. 3,
Auxiliary feedwater control valve is provided with auxiliary feedwater pipeline 301-3 that auxiliary feedwater system ASG feeds water to steam generator SG
(305-1 and 305-2), can pass through the standard-sized sheet signal of control reset auxiliary feedwater control valve (305-1 and 305-2), and adjust
The aperture of the auxiliary feedwater control valve (305-1 and 305-2) to default aperture, will auxiliary feedwater control valve aperture adjustment
To less than the 5% of standard-sized sheet, preferably situation is closed to be adjusted to auxiliary feedwater control valve door (305-1 and 305-2),
Stop simultaneously Steam Turbine Bypass System GCT outwards discharge steam realize controlling the temperature of the primary Ioops system of the nuclear power station and
Pressure is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;Wherein, the temperature of nuclear power station standard hot shutdown
With pressure limit be primary Ioops temperature in the range of 284 DEG C~291 DEG C, pressure is in 135~155 barometric pressure ranges.
(2) steam generator water level control
While the temperature and pressure to primary Ioops system is controlled, in addition it is also necessary to which the water level of steam generator is carried out
Control, concrete control method is as follows:
Please continue to refer to Fig. 3, auxiliary feedwater system ASG include auxiliary feedwater control valve (305-1 and 305-2), aid in
Water pump and auxiliary feed-water tank 306, wherein, auxiliary feed water pump include two by power supply as power resources electronic auxiliary feedwater
Pump (ASG001PO and ASG002PO), and two by vapour source as power resources turbine driven auxiliary feed-water pump (ASG003PO and
ASG004PO);Auxiliary feedwater system ASG to steam generator SG feedwater includes two-way feedwater route, is all the way, auxiliary feedwater pipe
Road 301-3 is connected with two electronic auxiliary feed water pumps (ASG001PO and ASG002PO), and leads to auxiliary feed-water tank 306, auxiliary
Help between feed pipe 301-3 and electronic auxiliary feed water pump (ASG001PO and ASG002PO) and be provided with auxiliary feedwater control valve 305-
1;Another road is, auxiliary feedwater pipeline 301-3 and two turbine driven auxiliary feed-water pumps (ASG003PO and ASG004PO), and leads to auxiliary
Feed-tank 306 is helped, is provided between auxiliary feedwater pipe 301-3 and auxiliary feedwater pneumatic pump (ASG003PO and ASG004PO) auxiliary
Help water supply control valve 305-2.Water in auxiliary feed-water tank is pumped to steam and is sent out by auxiliary feedwater system by auxiliary feedwater pump work
Raw device SG, wherein it is possible to pass through the rotating speed and water supply control valve (305- for controlling auxiliary feed water pump (ASG001PO~ASG004PO)
2nd, 305-2) aperture controlling auxiliary feedwater system ASG to the confluent of steam generator SG.
Specifically, in process of the test, when primary Ioops main pump is all stopped transport, auxiliary feedwater system ASG receives startup letter
Number, the enabling signal for controlling reset auxiliary feedwater system ASG is needed, and by the auxiliary feedwater system ASG to the nuclear power machine
The steam generator SG of group carries out the feedwater flow of auxiliary feedwater and is adjusted to zero, while controlling the steam generation of the nuclear power generating sets
The blowdown flow rate of device drainage APG is reduced to zero and adjusts water realizing that the water level for controlling the steam generator SG is maintained at SG
Position;When the water level of the steam generator SG adjusts water level in the SG, the nuclear power generating sets stable operation is ensure that.
In all embodiments of the application, the range of steam generator SG is (- 1.8m~+1.8m), and SG water levels of adjusting are specially
(- 0.58m~-0.6m) meets application requirement.
In addition, in specific implementation process, can feed water to control to steam generator by blocking auxiliary feedwater system
The water level of steam generator;Specifically, need staff to carry out human intervention stoppage in transit auxiliary feed water pump, so as to stop auxiliary to
Water system to steam generator SG feeds water;Wherein, electronic auxiliary feed water pump (ASG001PO, ASG002PO) is stopped transport can pass through to disconnect
Power switch realizes that auxiliary feedwater pneumatic pump (ASG003PO, ASG004PO) is stopped transport and can be realized by overspeed protection tripping valve.
Embodiment three
In specific implementation process, primary Ioops system includes three loops (No. 1 loop, No. 2 loops and 3 ring road), and
And each loop includes a main pump and a steam generator.Specifically, No. 1 loop includes No. 1 main pump RCP001PO and No. 1
Steam generator SG1;No. 2 loops include No. 2 main pump RCP002PO and No. 1 steam generator SG2;3 ring road includes No. 3 main pumps
RCP003PO and No. 3 steam generator SG3;Also, three loops share an auxiliary feedwater system ASG and a turbine by pass
System GCT.
The primary Ioops temperature, pressure control method referred in embodiment two apply to three main pumps (RCP001PO~
Control method when RCP003PO) stopping transport, in specific implementation process, after power supply handover success, main pump can be re-energised and open
Move and start working, in this course, should be noted to prevent primary Ioops superheated and cause primary Ioops superheated and surpass
Pressure, will focus in the present embodiment the unit allocation method introduced after power supply handover success.
The present embodiment is primarily directed to analog power and switches off main power source and be switched to accessory power supply for the nuclear power
Stand unit main pump for electric test (referred to as BAS54 tests), the power supply of main pump is switched to into auxiliary transformation by main transformer
Device, is powered by auxiliary transformer LGB/LGC for main pump, wherein, LGB, LGC be to unit outage during also need run station-service
The permanent distribution boaries of 6.6kV of equipment (including main pump) power supply.This test is powered after stopping transport just for the main pump dead electricity of No. 1 loop and transports
OK, i.e., in the present embodiment No. 2 loops and 3 ring road have neither part nor lot in test.
During test, when hot function test starts, the main pump RCP001PO of primary Ioops system normally runs,
It is first carried out that No. 1 main pump RCP001PO power supply of the nuclear power station unit station is switched to the power supply switching of accessory power supply from main power source
Operation, the method (as shown in Figure 2) of execution step S201~S202, step S203:The core is determined based on the detection information
The accident pattern of power station unit, and the process strategy of the accident is determined based on the accident pattern, and based on the process
Strategy interrupts the round-robin implementation of the station guide accident treatment code, and carries out intervention control to the nuclear power station unit station
System, specifically includes:
Based on the detection information determine power supply that the accident pattern of the nuclear power station unit station is the nuclear power station unit station from
Main power source is switched to the Equations of The Second Kind that accessory power supply causes the nuclear power station unit station primary Ioops main pump dead electricity to be powered again after stopping transport
Single accident;
Based on the single accident of the Equations of The Second Kind, the round-robin implementation of the station guide accident treatment code is interrupted, and
Before the main pump is started, by the setting value of pressure of Steam Turbine Bypass System GCT of the adjustment nuclear power station unit station to first
Preset pressure value, and control the valve of Steam Turbine Bypass System GCT and be closed, and by the nuclear power station unit station
The shower valve of manostat is set to automatic control mode to realize controlling the temperature and pressure of the primary Ioops system of the nuclear power station
It is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;
The steam generation of the auxiliary feedwater system ASG of the nuclear power station unit station to the nuclear power station unit station is adjusted by control
Device SG carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater, the steam generator SG is controlled by the auxiliary feedwater
The confluent that valve gets balances to realize controlling the water level of the steam generator SG with the displacement of the steam generator
It is maintained at SG to adjust water level;Wherein, when the water level of the steam generator SG adjusts water level in the SG, ensure that described
Nuclear power generating sets stable operation;
After the main pump is started, realized by controlling Steam Turbine Bypass System GCT in automatic operation mode
The temperature and pressure for controlling the primary Ioops system is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown.
Specifically, when above-mentioned test is carried out, can be by being controlled to nuclear power generating sets in terms of three below:
(1) start before main pump, the control of primary Ioops temperature and pressure
In concrete process of the test, by taking No. 1 loop as an example, in the loop main pump RCP001PO, steam generator are included
SG1, Steam Turbine Bypass System GCT-a;In embodiment two it is stated that during power supply switches, main pump RCP001PO meetings
Run out of steam and out of service within a period of time so that primary Ioops temperature, pressure has certain decline, so that one time
The heat of the secondary circuit Water transport in Lu Shuixiang steam generator SG1 is reduced, and the air pressure in steam generator SG1 reduces, and such as exists
During main pump RCP001PO normal works, the air pressure in steam generator SG1 is 7.6MPa, after main pump RCP001PO stops transport, is steamed
Air pressure in vapour generator SG1 is to be reduced to 7.3MPa;However, in order to during main pump RCP001PO normal works, vapour
Machine bypath system GCT-a can normally discharge steam, and the setting value of pressure for being normally set up Steam Turbine Bypass System GCT-a is equal to steaming
Air pressure in vapour generator SG1, such as 7.6MPa, it is ensured that the steam that steam generator SG1 is produced can smoothly from GCT-a
Discharge;If stopping transport and causing the current gas pressure in steam generator SG1 to be reduced to 7.3MPa due to main pump RCP001PO power-off,
And the setting value of pressure of Steam Turbine Bypass System GCT-a is still set as 7.6MPa, then as power supply handover success, main pump RCP001PO
When being re-energised work, primary Ioops produce heat firstly the need of by steam generator SG1 secondary circuit water heat so as to gas
Pressing and rise to 7.6MPa by 7.3MPa and just can guarantee that the steam of generation from the discharge of Steam Turbine Bypass System GCT-a, and take away heat makes
Primary Ioops temperature is reduced, that is to say, that the air pressure in main pump RCP001PO work heat production makes steam generator SG1 rises to
During 7.6MPa, the heat of primary Ioops is constantly in lasting propradation, it is more likely that cause primary Ioops overheated mistake occur
The phenomenon of pressure.Therefore, for the main pump RCP001PO in above-mentioned primary Ioops system in power supply switching tests, in main pump
Before RCP001PO starts, the setting value of pressure for adjusting Steam Turbine Bypass System GCT-a is needed to preset pressure value, wherein, preset pressure
Current gas pressure value in the close steam generator SG1 of force value, such as when current gas pressure value is 7.3MPa, preset pressure value is (7.3
~7.4) MPa;Further, as shown in figure 3, in connection steam generator SG and row's jet chimney of Steam Turbine Bypass System GCT
Steam turbine air bleeding valve 307 is provided with 301-4, in order to prevent secondary circuit when primary Ioops main pump stops transport not heat production, still by vapour
Machine bypath system outwards discharges steam, takes away the heat in primary Ioops, and the steam turbine air bleeding valve of Steam Turbine Bypass System GCT is closed in control
307;Lower the temperature for primary Ioops in order to shower valve can be automatically opened up when overheated over-pressed phenomenon occurs in primary Ioops system, by manostat
Shower valve be set to automatic control mode;Three above process step, can individually implement, it is also possible to which combination in any carries out reality
Apply;After above protective measure is carried out, restart main pump, can effectively control the nuclear power station primary Ioops system temperature and
Pressure is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown, wherein, the temperature of nuclear power station standard hot shutdown
With pressure limit be primary Ioops temperature in the range of 284 DEG C~291 DEG C, pressure is in 13.9MPa.a~15.5MPa.a scopes
It is interior.
Further, since in actual moving process, three main pumps in primary Ioops system can work simultaneously, and at each
Stage, the working condition of three main pumps is the same, in order to ensure three loops when steam is discharged, the air pressure in three loops
In poised state, generally the setting value of pressure of the Steam Turbine Bypass System of three loops is carried out into identical setting.
(2) steam generator water level control
Three loops of nuclear power generating sets share an auxiliary feedwater system, the steam generator of three loops (SG1, SG2,
SG3) be connected with auxiliary feedwater system by three auxiliary feedwater pipelines respectively, and in order to auxiliary feedwater system to each
The confluent of steam generator is controlled, and auxiliary feedwater control valve, i.e., No. 1 loop correspondence 1 is provided with each feedwater piping
Number auxiliary feedwater control valve, No. 2 loops No. 2 auxiliary feedwater control valves of correspondence, 3 ring roads No. 3 auxiliary feedwater control valves of correspondence;When
During test, when only testing No. 1 loop, i.e. only main pump RCP001PO operationally, is adjusted for control 1
No. 1 auxiliary feedwater control valve of the confluent of number steam generator SG1, makes auxiliary feedwater system ASG pass through auxiliary feedwater pipeline
Supply water to steam generator SG1;Due to whether working regardless of other loops in three loops, the steam generation in No. 2 loops
Steam generator SG3 in device SG2 and 3 ring road is required for by the outside sewage effluent of blowdown control system, in the present embodiment
In, for No. 2 loops and 3 ring road, respectively by controlling opening for No. 2 auxiliary feedwater control valves and No. 3 auxiliary feedwater control valves
Degree, so that auxiliary feedwater control system feeds water to steam generator SG2, SG3, so as to compensate the blowdown flow rate of SG2 and the blowdown of SG3
Amount.
Certainly, in specific implementation process, if No. 2 loops and the main pump in 3 ring road are not involved in test, it is also possible to
The blowoff valve of steam generator SG2 and steam generator SG3 is closed, now auxiliary feedwater system only need to be to steam generator
SG1 supplies water, without supplying water to steam generator SG2, SG3, so as to ensure the water level balance of SG1, SG2 and SG3.
(3) start after main pump, the control of primary Ioops temperature and pressure
In specific implementation process, after the main pump is started, automatic mold can be in by control Steam Turbine Bypass System
Formula, to keep primary Ioops system temperature and pressure to be maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown, i.e.,
Primary Ioops temperature is in the range of 284 DEG C~291 DEG C, pressure is in the range of 13.9MPa.a~15.5MPa.a.Specifically, due to one
Heat in loop is taken out of by secondary circuit water, and the vapour pressure in steam generator is affected by primary Ioops temperature, i.e. steam
The vapour pressure value of generator has corresponding relation with primary Ioops temperature, and Steam Turbine Bypass System can be according to temperature in primary Ioops system to gas
Dynamic valve is controlled, and such as when main pump is stopped transport, primary Ioops temperature is reduced, and causes the vapour pressure in steam generator to reduce, by steam turbine
Road system closes pneumatic operated valve, to ensure that primary Ioops temperature is no longer reduced;And for example when main pump restarts, in primary Ioops temperature
Rise, cause the vapour pressure in steam generator to rise, Steam Turbine Bypass System opens pneumatic operated valve, and setting value of pressure is disposed proximate to
Current vapour pressure value in steam generator, primary Ioops temperature no longer rises, to ensure that primary Ioops are not in overheated over-pressed phenomenon.
Example IV
In hot function test, the primary Ioops temperature and pressure of unit, steam generator water level and steady can be caused
Depressor water level factor out of control can also be:For the 48V DC source LCA or LCB dead electricity of instrument control instrument power supply in the unit.
Specifically, Fig. 3 is refer to, auxiliary feedwater system ASG includes extra feed valve (305-1 and 305-2), auxiliary feedwater
Pump and auxiliary feed-water tank 306, wherein, auxiliary feed water pump include two by power supply as power resources electronic auxiliary feed water pump
(ASG001PO and ASG002PO), and two by source of the gas as power resources turbine driven auxiliary feed-water pump (ASG003PO and
ASG004PO);Water in auxiliary feed-water tank 306 is pumped to steam generation by auxiliary feedwater system ASG by auxiliary feedwater pump operation
In device SG;Wherein, electronic auxiliary feed water pump ASG001PO and electronic auxiliary feed water pump ASG002PO use driven by power as dynamic
Power is originated;Turbine driven auxiliary feed-water pump ASG003PO and turbine driven auxiliary feed-water pump ASG004PO use steam drive to come as power
Source.Specifically, nuclear power generating sets include three loops:No. 1 loop, No. 2 loops, 3 ring roads, each loop include main pump and
One steam generator, altogether three steam generators share an auxiliary feedwater system, auxiliary feedwater system is not respectively by
Same auxiliary feedwater control valve is that the steam generator of three loops supplies water;Fig. 4 is refer to, is a loop in three loops
Turbine driven auxiliary feed-water pump control schematic diagram, turbine driven auxiliary feed-water pump ASG003PO and ASG004PO and main steam system (including
Steam Turbine Bypass System GCT and steam turbine 402) row's jet chimney 401 be connected, for connection row's jet chimney 401 and steam-operating
Pneumatic operated valve ASG137VV, ASG138VV and overspeed protection valve ASG135VV are provided with the vapour source pipeline 401-1 of pump ASG003PO;
Wherein, pneumatic operated valve ASG137VV and pneumatic operated valve ASG138VV are connected in parallel, and connect with overspeed protection valve ASG135VV respectively, use
In control air demand of the main steam system to pneumatic pump ASG003PO;In addition, for connection row's jet chimney and pneumatic pump
Pneumatic operated valve ASG237VV, ASG238VV and overspeed protection valve ASG235VV are provided with the vapour source pipeline 401-2 of ASG004PO, its
In, pneumatic operated valve ASG237VV and pneumatic operated valve ASG238VV is connected in parallel, and connects with overspeed protection valve ASG235VV respectively, is used for
Control air demand of the main steam system to pneumatic pump ASG004PO.In actual applications, 48V DC control supplies LCA is pneumatic
Valve ASG137VV and ASG237VV power, and 48V DC control supplies LCB powers for pneumatic operated valve ASG138VV and ASG238VV.It is logical
In the case of often, LCA and LCB normal power supplies, pneumatic operated valve ASG137VV, ASG237VV, ASG138VV and ASG238VV are in closing
State, turbine driven auxiliary feed-water pump does not run;When LCA or LCB dead electricity, pneumatic operated valve ASG137/237VV can be opened, and be pneumatic pump
ASG003PO and ASG004PO provides vapour source so as to startup optimization.In addition, in auxiliary feedwater system and each steam generator
Auxiliary feedwater control valve is provided with connecting pipe, as shown in figure 4, the steam generator of auxiliary feedwater system and a loop
Auxiliary feedwater control valve ASG013VD is provided with feedwater piping.When LCA or LCB dead electricity, auxiliary feedwater system it is auxiliary
Help the steam generator water filling that the automatic standard-sized sheets of water supply control valve ASG013VD are place loop;In the same manner, in specific implementation process,
The auxiliary feedwater control valve of other two loops also can the automatic standard-sized sheet of dead electricity be each place loop steam generator water filling.
Due to, pneumatic pump ASG003PO, ASG004PO cannot speed governing, and in the 48V direct current supplys for losing LCA/LCB
In the case of, auxiliary feedwater control valve ASG013VD keeps dead electricity full-gear, it is impossible to adjust flow, and staff in master control
Interior cannot carry out remotely control auxiliary feedwater system to the confluent in steam generator, so as to cause steam generator
Water level is too high.
In the present embodiment, (this test is referred to as COC50/51 tests) is tested for above-mentioned transient condition, first,
Hot shutdown condition, the dead electricity behaviour for the 48V DC sources of instrument control instrument power supply in the unit for simulating the nuclear power station unit station
Make, then, during test, the method (as shown in Figure 2) of execution step S201~S202, step S203:Based on described
Detection information determines the accident pattern of the nuclear power station unit station, and determines the process plan of the accident based on the accident pattern
Slightly, and based on described the round-robin implementation that strategy interrupts the station guide accident treatment code is processed, and to the core
Power station unit carries out intervention control, specifically includes:
Determine that the accident pattern of the nuclear power station unit station is the nuclear power station unit station for described based on the detection information
The 48V DC source dead electricity of instrument control instrument power supply causes the pneumatic operated valve of the auxiliary feedwater system of the nuclear power generating sets in unit
The single accident of the 3rd class opened;
Based on the single accident of the 3rd class, the round-robin implementation of the station guide accident treatment code is interrupted, and
Stoppage in transit state is in by controlling the auxiliary feed water pump of the auxiliary feedwater system ASG, and controls the auxiliary feedwater system
ASG carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater to the steam generator SG of the nuclear power generating sets, makes the steam
Generator balances to realize by the confluent that the auxiliary feedwater control valve gets with the displacement of the steam generator
The water level for controlling the steam generator is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator is in the SG
Adjust water level when, ensure that the nuclear power generating sets stable operation;
By the aperture for controlling to adjust the auxiliary feedwater control valve, so that the water level of the steam generator SG is maintained at
The SG adjusts water level, or realizes control by controlling the auxiliary feed water pump of the auxiliary feedwater system ASG in stoppage in transit state
The temperature and pressure for making the primary Ioops system of the nuclear power station unit station is maintained at the temperature and pressure of the nuclear power station standard hot shutdown
In the range of power;
The manostat is isolated by the letdown line of the manostat of the control isolation primary Ioops system, and control
On fill pipeline and adjust water level realizing that the water level for controlling the manostat is maintained at voltage stabilizing;Wherein, when the water level of the manostat
When water level is adjusted in the voltage stabilizing, the nuclear power generating sets stable operation is ensure that.
Specifically, in the present embodiment including the unit allocation scheme of following three aspects:
(1) steam generator water level control
Connected with pneumatic operated valve ASG137/138VV due to overspeed protection valve ASG135VV, overspeed protection valve ASG235VV and gas
Dynamic valve ASG237/238VV series connection, by providing 110V power supplys to overspeed protection threshold switch control module, makes ASG135/235VV
Close, supply to pneumatic pump ASG003PO and ASG004PO so as to block main steam system so that steam-operating pump shutdown.Actually should
With in, in the case of LCA and LCB dead electricity, can be by all auxiliary feed water pumps out of service and by staff to scene
The neutral point of destruction auxiliary feedwater control valve adjusting auxiliary feedwater system ASG manually to the output of steam generator SG, from
And the water level for controlling steam generator SG is maintained at SG and adjusts water level.
(2) the temperature and pressure control of primary Ioops system
The water level of steam generator SG is too high, and the vapour pressure in steam generator SG can be caused to raise, so as to increase capacity,
And larger primary Ioops heat is taken away, eventually result in primary Ioops temperature and pressure unbalance.
Under normal circumstances, in hot shutdown, the ideal temperature of primary Ioops system should be 291 DEG C, but in practical operation
Be in journey impossible make primary Ioops temperature be accurately maintained in 291 DEG C it is constant, but fluctuate near 291 DEG C, primary Ioops
Temperature fluctuation range represents primary Ioops temperature stability;According to practical application request, the temperature stability to primary Ioops system
Requirement is divided into two kinds of situations, and one is that stability requirement is high, and two is that stability requirement is not high;Wherein, stability requirement height is referred to
Primary Ioops temperature fluctuation range is less, i.e., fluctuate in the range of (291 ± X) DEG C;Stability requirement is not high to refer to primary Ioops temperature
Degree fluctuation range is larger, such as temperature more than (291+X) DEG C or less than (291-X) DEG C, wherein, X is integer, can value be 5.
When the temperature stabilization of primary Ioops system requires higher, by staff to Field adjustment auxiliary feedwater system
The aperture of auxiliary feedwater control valve ASG013VD, adjusts water level so as to the water level for controlling steam generator SG is maintained at SG;When one
When loop temperature stability requirement is not high, can be aided in by start and stop electronic auxiliary feed water pump (ASG001PO, ASG002PO) or steam-operating
Feed pump (ASG003PO, ASG004PO), stops being supplied water to steam generator, so as to the water level for controlling steam generator is maintained at
SG adjusts water level;So as to control primary Ioops temperature in the range of 284 DEG C~291 DEG C, pressure is in 15.5MPa.a or so.
(3) water lev el control of primary Ioops steady pressure of system device
Fig. 5 is refer to, the structure and operation principle of the manostat of primary Ioops system are introduced first.Fig. 5 includes two water
Blood circulation.Wherein, a water circulation system includes:Reactor core 501, steam generator 502, main pump 503, water circulation principle is one time
Road water takes away the heat of reactor core 501 through reactor core 501, and the primary Ioops water that temperature rises flows through steam generator 502, by heat
The secondary circuit water in steam generator 502 is passed to, the primary Ioops water of temperature is reduced in the presence of main pump 503, is returned to
Reactor core 501.Another water circulation system is the water level control of pressurizer system in primary Ioops system, is mainly included:Manostat 504,
On fill pipeline 505, letdown line 506, volume control tank 507 and high-pressure safety injection pump 508;In normal work, in order to remain steady
The ordinary water level of depressor 504, the water in primary Ioops is discharged by letdown line 506 and enters volumetric void fraction Jing after decrease temperature and pressure process
Case 507, then pressurizeed through high-pressure safety injection pump 508, afterwards the water after pressurization is refilled into one time by above filling pipeline 505
Road, so as to realize the control pair the manostat water level being connected with primary Ioops;Wherein, the charging stream amount for above filling pipeline 505 is let out with
The letdown flow value of pipeline 506 is identical.
Nuclear power plant voltage stabilizer 504 is the visual plant in nuclear reaction primary Ioops system, and in steady-state operation, it keeps normal
Primary Ioops pressure, in transient state its by primary Ioops pressure limit in permissible value.Additionally, manostat is also cooled down as reactor
The buffer tank of agent, buffers primary Ioops and expands with heat and contract with cold the change in volume of generation.As shown in figure 5, under nominal power, manostat
About 60% is saturation water 504-1 (being located at the bottom of manostat container) in 504, and 40% is that saturated vapor 504-2 (is located at manostat
The top of container);The bottom of manostat 504 (fluid zone) is connected by Surge line piping with the heat pipe section of a loop, primary Ioops system
Other parts are a water-filled systems, and the pressure in manostat 504 will reach whole primary Ioops system.Manostat 504
Water level can not be too high or too low, otherwise can build-up of pressure failure of adjustment or electric heater is exposed burns, wherein, electric heater is located at
In fluid zone inside manostat container, in manostat during reduced pressure, the water of fluid zone is heated, to maintain manostat
Middle pressure balance.Causing the principal element of manostat SEA LEVEL VARIATION has:(1) load (water level i.e. in steam generator 502) changes
Change changes reactor coolant (primary Ioops water) mean temperature to cause the change in volume of primary Ioops water, wherein, primary Ioops water with
The bottom of manostat 504 communicates, and the water into the bottom of manostat 504 is saturation water 504-1 in manostat 504;(2) voltage stabilizing
The charging stream amount of device 504 is uneven with letdown flow.Water level control of pressurizer protection system can exist the water level regulation of manostat 504
Near setting valve, it is ensured that manostat operating condition disclosure satisfy that pressure controlled needs, and protection equipment safety.In this test
In, after LCA the or LCB direct current supplys of 48V are lost, letdown line 506 occurs automatism isolation (as shown in figure 5, letting out under closing
Isolating valve 506-1), i.e. letdown line 506 does not carry out draining, but now on fill pipeline 505 still in net manostat 504
Water filling, if not being controlled, the water level in manostat 504 can constantly rise or even bury in oblivion the vapour chamber on the top of manostat 504, make steady
Depressor 504 loses the function of voltage stabilizing, and consequence is hardly imaginable.In order to avoid manostat water level rises after LCA or LCB dead electricity,
When the indicating graduation value of the water gauge of manostat 504 exceedes the 30% of its full scale, pipeline is filled (such as Fig. 5 institutes in control isolation
Show, isolating valve 505-1 is filled in closing);In actual applications, can be by filling pipeline 505 on staff manually isolation;From
And the water level of manostat 504 is maintained at voltage stabilizing and is adjusted water level.In specific implementation process, the range of the manostat is (- 6m
~+0.38m), voltage stabilizing water level of adjusting is not higher than the 30% -3m of manostat range (be not higher than) of manostat range.
Embodiment five
In actual applications, the safety injection system of nuclear power station unit station carries out Safety Injection to primary Ioops system, is for one time
Road pipeline cut and cause the safety measure that the accident of primary Ioops dehydration takes.In order to verify in Safety Injection, the guarantor of unit
Shield action is correct, and needs carry out peace note test in heat examination.Specifically, peace note test (TP RIS 60) is nuclear power generating sets joint debugging
One large-scale special test of period, the test objective is for correctness, the reaction of each system auto-action after checking peace to note
Heap jumps the triggering of heap, the triggering of phase security shell isolation (CIA, Containment Isolation Phase A) signal and phase
The peace beam amount adjusted during the auto-action answered, and cold examination of uncapping to nuclear power generating sets is verified and come into force.
After test requirements document triggering peace note signal, Safety Injection (SI, Safety Injection) and phase security shell every
Meet requirement, peace note sequence of movement and containment isolation order from (CIA) related equipment correct operation, movement time and meet anti-
Answer heap protection system (RPR, Reactor Protection) logic, high-pressure safety injection (HHSI, High Head Safety
Injection) flow of pump meets requirement, the boric acid of boron injection tank (RIS004BA) and is injected in major loop.
In the present embodiment, tested for peace note transient action, first, when hot function test starts, simulation
The operation of the peace note signal of the nuclear power station unit station is triggered, specifically, is touched initially with steam generator " two high one is low " signal
Send out peace note action.In the present embodiment, started by No. 2 loops triggering peace note in three loops of unit, i.e., first by No. 2 steam
Generator SG2 row atmosphere controlling valve GCT132VV are placed in manually, then will arrange atmosphere controlling valve GCT132VV open successively to 40%,
70%th, 95% aperture, can trigger peace note action.After above-mentioned peace note index is demonstrated, in order to avoid peace note test is caused
Unit is difficult to control to, and the harm that brings and economic loss.During checking peace note index, may be brought according to peace note
Impact take measures to control primary Ioops temperature, manostat water level and steam generator water level.In specific implementation process, hold
The method (as shown in Figure 2) of row step S201~S202, step S203:The nuclear power station unit station is determined based on the detection information
Accident pattern, and the process strategy of the accident is determined based on the accident pattern, and interrupt based on the process strategy
The round-robin implementation of the station guide accident treatment code, and intervention control is carried out to the nuclear power station unit station, concrete bag
Include:
The peace note letter that the accident pattern of the nuclear power station unit station is the nuclear power station unit station is determined based on the detection information
Number being triggered causes the safety injection system of the nuclear power station unit station to carry out Safety Injection to the primary Ioops system of the nuclear power station unit station
The single accident of the 4th class;
Based on the single accident of the 4th class, the round-robin implementation of the station guide accident treatment code is interrupted, and
It is closed by controlling Steam Turbine Bypass System GCT of the nuclear power station unit station, and in the temperature of the primary Ioops system
When rising to preset temperature, the setting value of pressure of Steam Turbine Bypass System GCT is adjusted to the second preset pressure value to realize
The temperature and pressure for controlling the primary Ioops system is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;
After the nuclear power station unit station persistently carries out Safety Injection operation preset duration, the control isolation nuclear power station unit station
Boron injection tank be maintained at required value water level the water level of realizing the manostat for controlling the nuclear power station unit station;Wherein, when described
The water level of manostat ensure that the nuclear power generating sets stable operation in the required value water level;
The steam generation of the auxiliary feedwater system ASG of the nuclear power station unit station to the nuclear power station unit station is adjusted by control
Device SG carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater, the steam generator SG is controlled by the auxiliary feedwater
The confluent that valve gets is realized controlling the water of the steam generator SG with the displacement balance of the steam generator SG
Position is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator SG adjusts water level in the SG, ensure that institute
State nuclear power generating sets stable operation.
Specifically, in the present embodiment including the unit allocation scheme of following three aspects:
(1) primary Ioops temperature control
After peace note signal is triggered, safety injection system is to reactor core water filling, it is ensured that flood and cool down reactor core, prevents molten heap, keeps
The integrity of reactor core, but in the peace note process of the test of heat examination, reactor core does not feed, the major heat of primary Ioops from
The heat that the operation of primary Ioops main pump is produced, due to being started by increasing No. 2 steam generator SG2 row's air triggering peace notes, can make
Into primary Ioops temperature drop, then main pump operation heating rises primary Ioops temperature, if be not controlled, or even can cause steady
The unmanageable scene such as depressor full water.
In this regard, peace note triggering after, close Steam Turbine Bypass System rapidly first, prevent its peace note during, continue to
Outer output steam, takes away the heat of primary Ioops, and further results in primary Ioops temperature drop;Certainly, in the process, primary Ioops
Main pump still produce heat in operation, in order to prevent primary Ioops temperature from rising to before ideal value (291 DEG C) due to steam generation
Device causes primary Ioops to expand without outwards discharge heat, during primary Ioops temperature rises, can be by Steam Turbine Bypass System
Setting valve turn down such that it is able to while taking away appropriate primary Ioops heat, be unlikely to make primary Ioops temperature to rise too fast, and
It is maintained in the range of the temperature and pressure of standard hot shutdown.
(2) water level control of pressurizer
Due to after peace note signal is triggered, safety injection system is to primary Ioops system water filling, but in test primary Ioops system
It is without cut, then the water of peace note can be hoarded in primary Ioops, if be not controlled, manostat full water can be caused and by vapour
Chamber is buried in oblivion, and especially during the rising of primary Ioops constant temperature, primary Ioops water can rise more due to expanded by heating, water level
Hurry up, in this regard, in the present embodiment, by the above-mentioned method being controlled to primary Ioops temperature, the water level mistake of manostat can be avoided
It is fast to rise, while the water level that manostat is controlled by isolating boron injection tank is maintained at the required value water level.It had been embodied as
Cheng Zhong, the range of manostat is (- 6m~+3.8m), and the required value water level is 0.9m, that is to say, that when the water level of manostat
For 0.9m when, system starts the intervention operation of above-mentioned water level control of pressurizer, isolates boron injection tank.
In addition, in unit actual moving process, reactor is equipped with nuclear reaction material, the origin of heat of primary Ioops system is
Reactor core nuclear fission, in this regard, after peace note signal is triggered, safety injection system can be to the water filling of primary Ioops system and note boron;Specifically, peace note
System is to reactor core water filling, it is ensured that flood and cool down reactor core, prevents molten heap, keeps the integrity of reactor core;Safety injection system to reactor core is noted
Boron, for the response speed for absorbing reactor core neutron, slowing down reactor;In order that peace note test more tallies with the actual situation, when peace note
After signal is triggered, safety injection system is simultaneously to primary Ioops water filling and note boron.Specifically, as shown in fig. 6, the peace note for nuclear power station is
System structural representation, safety injection system includes:Material-changing water tank 601 (for providing peace water filling in the present embodiment), high-pressure safety injection pump
602nd, low pressure safety injection pump 603, peace note isolating valve (604-1,604-2), boron injection tank 605;Wherein, safety injection system passes through two roads
Radial direction primary Ioops system carries out peace note:High-pressure safety injection path and low pressure peace note path.Specifically, the work in high-pressure safety injection path is former
Manage and be, the peace water filling in material-changing water tank 601 is opened under the driving effect of high-pressure safety injection pump 602 when peace note isolating valve 604 is in
During state, primary Ioops system is injected by boron injection tank 605;Low pressure peace notes path operation principle, the peace in material-changing water tank 601
Water filling is directly injected into primary Ioops system under the driving effect of low pressure safety injection pump 603.Because during test, low pressure peace notes path
Less than the pressure of primary Ioops system, i.e., safety injection system cannot pacify note path by low pressure carry out peace note to pressure to primary Ioops, mainly
Pin path by high pressure carries out peace note to primary Ioops.In figure 6, boron injection tank 605 be by high-pressure safety injection pump 602 drive to
Primary Ioops injection peace fluid injection body, that is to say, that boron injection is the main injection means of peace note;However, at the trial, reactor core is
Without charging, after the water level for detecting manostat reaches the required value, should in time isolate boron injection tank 605, it is to avoid Xiang Yi
Excessive peace fluid injection body is injected in loop, and causes unit to be difficult to control to.Please continue to refer to Fig. 6, connection high-pressure safety injection pump 602 and boron
Peace note isolating valve 604-1, and the pipeline between boron injection tank 605 and primary Ioops reactor core are provided with the pipeline of injection case 605
On be also equipped with peace note isolating valve 604-2, the isolation of boron injection tank 605 is exactly by control peace note isolating valve 604-1 and/or peace
Note isolating valve 604-2 be closed realizing, first master control room by remote pilot peace note isolating valve (604-1,
604-2), in order to prevent that in master control room remote pilot peace note isolating valve (604-1,604-2) cannot be passed through, should prepare before the test
For directly from electrical panel operating the experiment box of boron injection tank isolating valve, and arrange special messenger at electrical panel, with master control room without
Method by by test box carrying out intervention control in time during remote pilot peace note isolating valve.To prevent test box at electrical panel from carrying out
Intervene failure, also need to arrange special messenger to intervene on the spot in peace note isolating valve (604-1,604-2).
(3) steam generator water level control
In peace note process of the test, because main pump is not stopped transport, auxiliary feedwater system ASG reset flow-controls do not have BAS/
It is urgent like that in COC tests, it is preferred that emphasis is to avoid primary Ioops temperature too fast in the rising of test initial stage by controlling ASG.Specifically,
Carried out to the steam generator SG of the nuclear power station unit station by the auxiliary feedwater system ASG of the control adjustment nuclear power station unit station
The aperture of the auxiliary feedwater control valve of auxiliary feedwater, makes the steam generator SG get by the auxiliary feedwater control valve
Confluent and the steam generator SG displacement balance realizing that the water level for controlling the steam generator SG is maintained at
SG adjusts water level;Wherein, when the water level of the steam generator SG adjusts water level in the SG, ensure that the nuclear power machine
Group stable operation.
Embodiment six
Fig. 7 A are refer to, the transient test control system in the embodiment of the present application in a kind of nuclear power station debugging start-up course,
The system includes:
Process code start unit 701, for when nuclear power station transient test starts, the state for starting nuclear power station unit station to be led
To accident treatment code, while starting the transient test control procedure of the nuclear power station unit station;
Detection information acquisition unit 702, for being carried out to the nuclear power station unit station by the transient test control procedure
Accident detection, obtains detection information;
Unit failure processing unit 703, for determining the accident pattern of the nuclear power station unit station based on the detection information,
And the process strategy of the accident is determined based on the accident pattern, and the station guide is interrupted based on the process strategy
The round-robin implementation of accident treatment code, and intervention control is carried out to the nuclear power station unit station.
In specific implementation process, the transient test control system also include unit failure analogue unit 700, for
When nuclear power station transient test starts, the interruption of service that the nuclear power station unit station occurs in running is simulated.
Further, Fig. 7 B are refer to, when nuclear power station transient test starts, unit failure analogue unit 700 is simulated institute
The power supply for stating nuclear power station unit station is switched to the power switching operations of accessory power supply, the unit failure processing unit from main power source
703, specifically include:
First accident pattern determining module 7031-1, for determining the thing of the nuclear power station unit station based on the detection information
Therefore the power supply that type is the nuclear power station unit station is switched to accessory power supply and causes the nuclear power station unit station primary Ioops master from main power source
The single accident of the first kind that pump dead electricity is stopped transport;
First temperature, pressure control module 7031-2, for based on the single accident of the first kind, interrupting the state and leading
To the round-robin implementation of accident treatment code, and pass through control reset the nuclear power station unit station auxiliary feedwater control valve it is complete
ON signal, and adjust the aperture of the auxiliary feedwater control valve and realize controlling one time of the nuclear power station to default aperture
The temperature and pressure of road system is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;
First SG water lev el control modules 7031-3, for based on the single accident of the first kind, interrupting the station guide
The round-robin implementation of accident treatment code, and stop outwards discharge by controlling the Steam Turbine Bypass System of the nuclear power station unit station
Steam, and the enabling signal of the auxiliary feedwater system of the nuclear power station unit station that resets, and by the auxiliary feedwater system to institute
State the steam generator of nuclear power generating sets and carry out the feedwater flow of auxiliary feedwater and be adjusted to minimum preset flow, while controlling the core
The blowdown flow rate of the steam generator blowdown system of group of motors is reduced to default blowdown flow rate to realize controlling the steam generator
Water level is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that institute
State nuclear power generating sets stable operation.
In specific implementation process, Fig. 7 C are refer to, when nuclear power station transient test starts, unit failure analogue unit
The power supply of the nuclear power station unit station is switched to the power switching operations of accessory power supply, the unit thing from main power source for 700 simulations
Therefore processing unit 703, specifically include:
Second accident pattern determining module 7032-1, for determining the thing of the nuclear power station unit station based on the detection information
Therefore the power supply that type is the nuclear power station unit station is switched to accessory power supply and causes the nuclear power station unit station primary Ioops master from main power source
The single accident of Equations of The Second Kind that pump dead electricity is powered again after stopping transport;
Second temperature pressure control module 7032-2, for based on the single accident of the Equations of The Second Kind, interrupting the state and leading
To the round-robin implementation of accident treatment code, and before the main pump is started, by the vapour for adjusting the nuclear power station unit station
The setting value of pressure of machine bypath system is to the first preset pressure value, and controls the valve of the Steam Turbine Bypass System in closing
State, and the shower valve of the manostat of the nuclear power station unit station is set to into automatic control mode to realize controlling the nuclear power
The temperature and pressure of the primary Ioops system stood is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;
2nd SG water lev el control modules 7032-3, for based on the single accident of the Equations of The Second Kind, interrupting the station guide
The round-robin implementation of accident treatment code, and by the auxiliary feedwater system of the control adjustment nuclear power station unit station to the core
The steam generator of power station unit carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater, makes the steam generator pass through institute
State the confluent that auxiliary feedwater control valve gets to realize controlling the steam with the displacement balance of the steam generator
The water level of generator is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator adjusts water level in the SG, energy
Enough ensure the nuclear power generating sets stable operation;
3rd temperature, pressure control module 7032-4, for based on the single accident of the Equations of The Second Kind, interrupting the state and leading
To the round-robin implementation of accident treatment code, and after the main pump is started, by controlling at the Steam Turbine Bypass System
Realize that the temperature and pressure for controlling the primary Ioops system is maintained at the nuclear power station standard hot shutdown in automatic operation mode
Temperature and pressure in the range of.
In specific implementation process, Fig. 7 D are refer to, when nuclear power station transient test starts, unit failure analogue unit
The dead electricity operation for the 48V DC sources of instrument control instrument power supply in the unit of the 700 simulations nuclear power station unit station, the machine
Group accident treatment unit 703, specifically includes:
3rd accident pattern determining module 7033-1, for determining the thing of the nuclear power station unit station based on the detection information
Therefore the 48V DC source dead electricity for instrument control instrument power supply in the unit that type is the nuclear power station unit station causes the nuclear power
The single accident of the 3rd class that the pneumatic operated valve of the auxiliary feedwater system of unit is opened;
3rd SG water lev el control modules 7033-2, for based on the single accident of the 3rd class, interrupting the station guide
The round-robin implementation of accident treatment code, and it is in stoppage in transit shape by controlling the auxiliary feed water pump of the auxiliary feedwater system
State, and control the auxiliary feedwater system auxiliary feedwater control of auxiliary feedwater is carried out to the steam generator of the nuclear power generating sets
The aperture of valve processed, makes confluent and the steam generation that the steam generator got by the auxiliary feedwater control valve
The displacement balance of device is adjusted water level realizing that the water level for controlling the steam generator is maintained at SG;Wherein, when the steam
The water level of generator ensure that the nuclear power generating sets stable operation when the SG adjusts water level;
4th temperature, pressure control module 7033-3, for based on the single accident of the 3rd class, interrupting the state and leading
To the round-robin implementation of accident treatment code, and by controlling to adjust the aperture of the auxiliary feedwater control valve, so that described
The water level of steam generator is maintained at the SG and adjusts water level, or by the auxiliary feed water pump for controlling the auxiliary feedwater system
Realize that the temperature and pressure for controlling the primary Ioops system of the nuclear power station unit station is maintained at the nuclear power station mark in stoppage in transit state
In the range of the temperature and pressure of quasi- hot shutdown;
First water level control of pressurizer module 7033-4, for based on the single accident of the 3rd class, interrupting the state
It is oriented under the round-robin implementation of accident treatment code, and the manostat by the control isolation primary Ioops system and lets out pipe
Line, and the control isolation manostat on fill pipeline and adjust realizing that the water level for controlling the manostat is maintained at voltage stabilizing
Water level;Wherein, when the water level of the manostat adjusts water level in the voltage stabilizing, ensure that the nuclear power generating sets are stably transported
OK.
In specific implementation process, Fig. 7 E are refer to, when nuclear power station transient test starts, unit failure analogue unit mould
Intend the operation of the peace note signal of the triggering nuclear power station unit station, the unit failure processing unit 703 is specifically included:
4th accident pattern determining module 7034-1, for determining the thing of the nuclear power station unit station based on the detection information
Therefore the peace note signal that type is the nuclear power station unit station is triggered and causes the safety injection system of the nuclear power station unit station to the nuclear power
The primary Ioops system of unit of standing carries out the single accident of the 4th class of Safety Injection;
5th temperature, pressure control module 7034-2, for based on the single accident of the 4th class, interrupting the state and leading
To the round-robin implementation of accident treatment code, and by controlling the Steam Turbine Bypass System of the nuclear power station unit station in closing shape
State, and when the temperature of the primary Ioops system rises to preset temperature, the setting value of pressure of the Steam Turbine Bypass System is adjusted
It is whole to be maintained at the nuclear power station standard hot realizing the temperature and pressure for controlling the primary Ioops system to the second preset pressure value
In the range of the temperature and pressure of shutdown;
Second water level control of pressurizer module 7034-3, for based on the single accident of the 4th class, interrupting the state
The round-robin implementation of accident treatment code is oriented to, and when the nuclear power station unit station persistently carries out Safety Injection operation preset duration
Afterwards, control is isolated water level of the boron injection tank of the nuclear power station unit station to realize the manostat for controlling the nuclear power station unit station and is protected
Hold in required value water level;Wherein, when the water level of the manostat is in the required value water level, the nuclear power generating sets be ensure that
Stable operation;
4th SG water lev el control modules 7034-4, for based on the single accident of the 4th class, interrupting the station guide
The round-robin implementation of accident treatment code, and by the auxiliary feedwater system of the control adjustment nuclear power station unit station to the core
The steam generator of power station unit carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater, makes the steam generator pass through institute
State the confluent that auxiliary feedwater control valve gets to realize controlling the steam with the displacement balance of the steam generator
The water level of generator is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator adjusts water level in the SG, energy
Enough ensure the nuclear power generating sets stable operation.
As described above, the transient test control system in above-mentioned nuclear power station heat examination is used to realize above-mentioned nuclear power station heat
Transient test control method in examination, so, the course of work of the system is consistent with one or more embodiments of said method,
Here is just no longer repeated one by one.
Those skilled in the art are it should be appreciated that embodiments of the invention can be provided as method, system or computer program
Product.Therefore, the present invention can be using complete hardware embodiment, complete software embodiment or with reference to the reality in terms of software and hardware
Apply the form of example.And, the present invention can be adopted and wherein include the computer of computer usable program code at one or more
The computer program implemented in usable storage medium (including but not limited to disk memory, CD-ROM, optical memory etc.) is produced
The form of product.
The present invention is the flow process with reference to method according to embodiments of the present invention, equipment (system) and computer program
Figure and/or block diagram are describing.It should be understood that can be by computer program instructions flowchart and/or each stream in block diagram
The combination of journey and/or square frame and flow chart and/or the flow process in block diagram and/or square frame.These computer programs can be provided
The processor of general purpose computer, special-purpose computer, Embedded Processor or other programmable data processing devices is instructed to produce
A raw machine so that produced for reality by the instruction of computer or the computing device of other programmable data processing devices
The device of the function of specifying in present one flow process of flow chart or one square frame of multiple flow processs and/or block diagram or multiple square frames.
These computer program instructions may be alternatively stored in can guide computer or other programmable data processing devices with spy
In determining the computer-readable memory that mode works so that the instruction being stored in the computer-readable memory is produced to be included referring to
Make the manufacture of device, the command device realize in one flow process of flow chart or one square frame of multiple flow processs and/or block diagram or
The function of specifying in multiple square frames.
These computer program instructions also can be loaded in computer or other programmable data processing devices so that in meter
Series of operation steps is performed on calculation machine or other programmable devices to produce computer implemented process, so as in computer or
The instruction performed on other programmable devices is provided for realizing in one flow process of flow chart or multiple flow processs and/or block diagram one
The step of function of specifying in individual square frame or multiple square frames.
, but those skilled in the art once know basic creation although preferred embodiments of the present invention have been described
Property concept, then can make other change and modification to these embodiments.So, claims are intended to be construed to include excellent
Select embodiment and fall into having altered and changing for the scope of the invention.
Obviously, those skilled in the art can carry out the essence of various changes and modification without deviating from the present invention to the present invention
God and scope.So, if these modifications of the present invention and modification belong to the scope of the claims in the present invention and its equivalent technologies
Within, then the present invention is also intended to comprising these changes and modification.
Claims (10)
1. a kind of nuclear power station debugs the transient test control method in start-up course, it is characterised in that methods described includes as follows
Step:
S1, when nuclear power station transient test starts, start nuclear power station unit station station guide accident treatment code, while start institute
State the transient test control procedure of nuclear power station unit station;Wherein, the transient test control procedure is to be specifically designed for nuclear power station transient state
The auxiliary accident treatment program that test is drafted, can be used in combination with station guide accident treatment code, complete in the transient state
Accident treatment in process of the test;
S2, accident detection is carried out to the nuclear power station unit station by the transient test control procedure, obtain detection information;
S3, the accident pattern of the nuclear power station unit station is determined based on the detection information, and institute is determined based on the accident pattern
The process strategy of accident is stated, the process strategy of the accident can be judged the single accident occurred in the transient test
And intervention;And the round-robin implementation that strategy interrupts the station guide accident treatment code is processed based on described, and to institute
Stating nuclear power station unit station carries out intervention control.
2. transient test control method as claimed in claim 1, it is characterised in that when the front simulation in step S1 is by the core
When the power supply of power station unit is switched to the power switching operations of accessory power supply from main power source, step S3 is specifically included:
Determine power supply that the accident pattern of the nuclear power station unit station is the nuclear power station unit station from main electricity based on the detection information
Source is switched to the single accident of the first kind that accessory power supply causes the nuclear power station unit station primary Ioops main pump dead electricity to be stopped transport;
Based on the single accident of the first kind, the round-robin implementation of the station guide accident treatment code is interrupted, and passed through
The standard-sized sheet signal of the auxiliary feedwater control valve of the control reset nuclear power station unit station, and adjust the auxiliary feedwater control valve
Aperture is to default aperture, while the Steam Turbine Bypass System for controlling the nuclear power station unit station stops outwards discharging steam to realize control
The temperature and pressure for making the primary Ioops system of the nuclear power station is maintained at the temperature and pressure model of the nuclear power station standard hot shutdown
In enclosing;
Resetted the enabling signal of the auxiliary feedwater system of the nuclear power station unit station by control, and by the auxiliary feedwater system to
The steam generator of the nuclear power generating sets carries out the feedwater flow of auxiliary feedwater and is adjusted to minimum preset flow, while control is described
The blowdown flow rate of the steam generator blowdown system of nuclear power generating sets is reduced to default blowdown flow rate to realize controlling the steam generator
Water level be maintained at SG and adjust water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that
The nuclear power generating sets stable operation.
3. transient test control method as claimed in claim 1, it is characterised in that when the front simulation in step S1 is by the core
When the power supply of power station unit is switched to the power switching operations of accessory power supply from main power source, step S3 also includes:
Determine power supply that the accident pattern of the nuclear power station unit station is the nuclear power station unit station from main electricity based on the detection information
Source is switched to accessory power supply causes the Equations of The Second Kind that the nuclear power station unit station primary Ioops main pump dead electricity is powered again after stopping transport single
Accident;
Based on the single accident of the Equations of The Second Kind, the round-robin implementation of the station guide accident treatment code is interrupted, and opened
Before moving the main pump, by the setting value of pressure of the Steam Turbine Bypass System of the adjustment nuclear power station unit station to the first preset pressure
Value, and control the valve of the Steam Turbine Bypass System and be closed, and by the spray of the manostat of the nuclear power station unit station
Drench valve to be set to automatic control mode to realize that the temperature and pressure for controlling the primary Ioops system of the nuclear power station is maintained at described
In the range of the temperature and pressure of nuclear power station standard hot shutdown;
Carried out to the steam generator of the nuclear power station unit station by the auxiliary feedwater system of the control adjustment nuclear power station unit station
The aperture of the auxiliary feedwater control valve of auxiliary feedwater, makes what the steam generator was got by the auxiliary feedwater control valve
Confluent is realized that the water level for controlling the steam generator is maintained at SG and is adjusted with the displacement balance of the steam generator
Water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that the nuclear power generating sets are stably transported
OK;
After the main pump is started, realize controlling institute by controlling the Steam Turbine Bypass System in automatic operation mode
The temperature and pressure for stating primary Ioops system is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown.
4. transient test control method as claimed in claim 1, it is characterised in that when nuclear power described in the front simulation in step S1
Stand unit in the unit 48V DC sources of instrument control instrument power supply dead electricity operate when, step S3 is specifically included:
Determine that the accident pattern of the nuclear power station unit station is the nuclear power station unit station for the unit based on the detection information
The 48V DC source dead electricity of middle instrument control instrument power supply causes that the pneumatic operated valve of the auxiliary feedwater system of the nuclear power generating sets is opened
The single accident of three classes;
Based on the single accident of the 3rd class, the round-robin implementation of the station guide accident treatment code is interrupted, and passed through
The auxiliary feed water pump of the auxiliary feedwater system is controlled in stoppage in transit state, and controls the auxiliary feedwater system to the core
The steam generator of group of motors carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater, passes through the steam generator described
The confluent that auxiliary feedwater control valve gets realizes that controlling the steam sends out with the displacement balance of the steam generator
The water level of raw device is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator adjusts water level in the SG, can
Ensure the nuclear power generating sets stable operation;
By the aperture for controlling to adjust the auxiliary feedwater control valve, so that the water level of the steam generator is maintained at the SG
Adjust water level, or realize controlling the core by controlling the auxiliary feed water pump of the auxiliary feedwater system in stoppage in transit state
The temperature and pressure of the primary Ioops system of power station unit is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;
By the letdown line of the manostat of the control isolation primary Ioops system, and the control isolation manostat on fill
Pipeline is adjusted water level realizing that the water level for controlling the manostat is maintained at voltage stabilizing;Wherein, when the water level of the manostat is in institute
State voltage stabilizing adjust water level when, ensure that the nuclear power generating sets stable operation.
5. transient test control method as claimed in claim 1, it is characterised in that when the front simulation triggering in step S1 it is described
During the operation of the peace note signal of nuclear power station unit station, step S3 also includes:
The peace note signal quilt that the accident pattern of the nuclear power station unit station is the nuclear power station unit station is determined based on the detection information
Triggering causes the safety injection system of the nuclear power station unit station that the of Safety Injection is carried out to the primary Ioops system of the nuclear power station unit station
The single accident of four classes;
Based on the single accident of the 4th class, the round-robin implementation of the station guide accident treatment code is interrupted, and passed through
The Steam Turbine Bypass System for controlling the nuclear power station unit station is closed, and the primary Ioops system temperature rise to it is pre-
If during temperature, the setting value of pressure of the Steam Turbine Bypass System is adjusted to into the second preset pressure value to realize control described one
The temperature and pressure of circuit system is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;
After the nuclear power station unit station persistently carries out Safety Injection operation preset duration, the boron of the control isolation nuclear power station unit station
Injection case is maintained at required value water level come the water level for realizing the manostat for controlling the nuclear power station unit station;Wherein, when the voltage stabilizing
The water level of device ensure that the nuclear power generating sets stable operation in the required value water level;
Carried out to the steam generator of the nuclear power station unit station by the auxiliary feedwater system of the control adjustment nuclear power station unit station
The aperture of the auxiliary feedwater control valve of auxiliary feedwater, makes what the steam generator was got by the auxiliary feedwater control valve
Confluent is realized that the water level for controlling the steam generator is maintained at SG and is adjusted with the displacement balance of the steam generator
Water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that the nuclear power generating sets are stably transported
OK.
6. a kind of nuclear power station debugs the transient test control system in start-up course, it is characterised in that the system includes:
Process code start unit, for when nuclear power station transient test starts, starting the station guide accident of nuclear power station unit station
Code is processed, while start the transient test control procedure of the nuclear power station unit station, wherein, the transient test control procedure is
The auxiliary accident treatment program that nuclear power station transient test is drafted is specifically designed for, can be combined with station guide accident treatment code makes
With completing the accident treatment during the transient test;
Detection information acquisition unit, for carrying out accident inspection to the nuclear power station unit station by the transient test control procedure
Survey, obtain detection information;
Unit failure processing unit, for determining the accident pattern of the nuclear power station unit station based on the detection information, and is based on
The accident pattern determines the process strategy of the accident, and the process strategy can be single to what is occurred in the transient test
Accident is judged and is intervened;And process the circulation execution that strategy interrupts the station guide accident treatment code based on described
Mode, and intervention control is carried out to the nuclear power station unit station.
7. transient test control system as claimed in claim 6, it is characterised in that when nuclear power station transient test starts, and mould
When the power supply for planning the nuclear power station unit station is switched to the power switching operations of accessory power supply from main power source, at the unit failure
Reason unit, specifically includes:
First accident pattern determining module, for determining that the accident pattern of the nuclear power station unit station is institute based on the detection information
Stating the power supply of nuclear power station unit station and being switched to accessory power supply from main power source causes the nuclear power station unit station primary Ioops main pump dead electricity to be stopped transport
The single accident of the first kind;
First temperature, pressure control module, for based on the single accident of the first kind, interrupting the station guide accident treatment
The round-robin implementation of code, and the standard-sized sheet signal of the auxiliary feedwater control valve of the nuclear power station unit station that resetted by control, with
And the aperture of the auxiliary feedwater control valve is adjusted to default aperture, while controlling the Steam Turbine Bypass System of the nuclear power station unit station
Stop outwards discharge steam and be maintained at the nuclear power station realizing the temperature and pressure for controlling the primary Ioops system of the nuclear power station
In the range of the temperature and pressure of standard hot shutdown;
First SG water lev el control modules, for based on the single accident of the first kind, interrupting the station guide accident treatment rule
The round-robin implementation of journey, and the enabling signal of the auxiliary feedwater system of the nuclear power station unit station that resetted by control, and by institute
State auxiliary feedwater system and be adjusted to minimum presetting to the feedwater flow that the steam generator of the nuclear power generating sets carries out auxiliary feedwater
Flow, while the blowdown flow rate for controlling the steam generator blowdown system of the nuclear power generating sets is reduced to default blowdown flow rate to realize
The water level for controlling the steam generator is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator is in the SG
Adjust water level when, ensure that the nuclear power generating sets stable operation.
8. transient test control system as claimed in claim 6, it is characterised in that when nuclear power station transient test starts, and mould
When the power supply for planning the nuclear power station unit station is switched to the power switching operations of accessory power supply from main power source, at the unit failure
Reason unit, specifically includes:
Second accident pattern determining module, for determining that the accident pattern of the nuclear power station unit station is institute based on the detection information
Stating the power supply of nuclear power station unit station and being switched to accessory power supply from main power source causes the nuclear power station unit station primary Ioops main pump dead electricity to be stopped transport
The single accident of Equations of The Second Kind being powered again afterwards;
Second temperature pressure control module, for based on the single accident of the Equations of The Second Kind, interrupting the station guide accident treatment
The round-robin implementation of code, and before the main pump is started, by the Steam Turbine Bypass System for adjusting the nuclear power station unit station
Setting value of pressure to the first preset pressure value, and control the valve of the Steam Turbine Bypass System and be closed, and will
The shower valve of the manostat of the nuclear power station unit station is set to automatic control mode to realize controlling the primary Ioops of the nuclear power station
The temperature and pressure of system is maintained in the range of the temperature and pressure of the nuclear power station standard hot shutdown;
2nd SG water lev el control modules, for based on the single accident of the Equations of The Second Kind, interrupting the station guide accident treatment rule
The round-robin implementation of journey, and by the auxiliary feedwater system of the control adjustment nuclear power station unit station to the nuclear power station unit station
Steam generator carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater, makes the steam generator pass through the auxiliary feedwater
The confluent that control valve gets is realized controlling the water of the steam generator with the displacement balance of the steam generator
Position is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that described
Nuclear power generating sets stable operation;
3rd temperature, pressure control module, for based on the single accident of the Equations of The Second Kind, interrupting the station guide accident treatment
The round-robin implementation of code, and after the main pump is started, by controlling the Steam Turbine Bypass System in work automatically
Pattern is maintained at the temperature and pressure of the nuclear power station standard hot shutdown realizing the temperature and pressure for controlling the primary Ioops system
In the range of power.
9. transient test control system as claimed in claim 6, it is characterised in that when nuclear power station transient test starts, and mould
When the dead electricity for the 48V DC sources of instrument control instrument power supply in the unit for intending the nuclear power station unit station is operated, the unit
Accident treatment unit, specifically includes:
3rd accident pattern determining module, for determining that the accident pattern of the nuclear power station unit station is institute based on the detection information
Stating the 48V DC source dead electricity for instrument control instrument power supply in the unit of nuclear power station unit station causes the auxiliary of the nuclear power generating sets
The single accident of the 3rd class that the pneumatic operated valve of water supply system is opened;
3rd SG water lev el control modules, for based on the single accident of the 3rd class, interrupting the station guide accident treatment rule
The round-robin implementation of journey, and it is in stoppage in transit state, and control by controlling the auxiliary feed water pump of the auxiliary feedwater system
The auxiliary feedwater system carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater to the steam generator of the nuclear power generating sets,
Make the displacement of the confluent that the steam generator is got by the auxiliary feedwater control valve and the steam generator
Balance is adjusted water level realizing that the water level for controlling the steam generator is maintained at SG;Wherein, when the water of the steam generator
Position ensure that the nuclear power generating sets stable operation when the SG adjusts water level;
4th temperature, pressure control module, for based on the single accident of the 3rd class, interrupting the station guide accident treatment
The round-robin implementation of code, and by controlling to adjust the aperture of the auxiliary feedwater control valve, so that the steam generator
Water level be maintained at the SG and adjust water level, or be in stoppage in transit shape by controlling the auxiliary feed water pump of the auxiliary feedwater system
State is maintained at the nuclear power station standard hot shutdown realizing the temperature and pressure for controlling the primary Ioops system of the nuclear power station unit station
Temperature and pressure in the range of;
First water level control of pressurizer module, for based on the single accident of the 3rd class, interrupting at the station guide accident
The round-robin implementation of reason code, and the letdown line of the manostat by the control isolation primary Ioops system, and control
Isolate the manostat on fill pipeline and adjust water level realizing that the water level for controlling the manostat is maintained at voltage stabilizing;Wherein, when
The water level of the manostat ensure that the nuclear power generating sets stable operation when water level is adjusted in the voltage stabilizing.
10. transient test control system as claimed in claim 6, it is characterised in that when nuclear power station transient test starts, and mould
During the operation of the peace note signal for intending the triggering nuclear power station unit station, the unit failure processing unit is specifically included:
4th accident pattern determining module, for determining that the accident pattern of the nuclear power station unit station is the core based on detection information
The peace note signal of power station unit is triggered the primary Ioops for causing the safety injection system of the nuclear power station unit station to the nuclear power station unit station
System carries out the single accident of the 4th class of Safety Injection;
5th temperature, pressure control module, for based on the single accident of the 4th class, interrupting the station guide accident treatment
The round-robin implementation of code, and be closed by controlling the Steam Turbine Bypass System of the nuclear power station unit station, and in institute
When the temperature for stating primary Ioops system rises to preset temperature, the setting value of pressure of the Steam Turbine Bypass System is adjusted to into second pre-
If pressure value is maintained at the temperature of the nuclear power station standard hot shutdown realizing the temperature and pressure for controlling the primary Ioops system
In pressure limit;
Second water level control of pressurizer module, for based on the single accident of the 4th class, interrupting at the station guide accident
Reason code round-robin implementation, and when the nuclear power station unit station persistently carry out Safety Injection operation preset duration after, control every
The water level that the manostat for controlling the nuclear power station unit station is realized from the boron injection tank of the nuclear power station unit station is maintained at required value
Water level;Wherein, when the water level of the manostat is in the required value water level, ensure that the nuclear power generating sets stable operation;
4th SG water lev el control modules, for based on the single accident of the 4th class, interrupting the station guide accident treatment rule
The round-robin implementation of journey, and by the auxiliary feedwater system of the control adjustment nuclear power station unit station to the nuclear power station unit station
Steam generator carries out the aperture of the auxiliary feedwater control valve of auxiliary feedwater, makes the steam generator pass through the auxiliary feedwater
The confluent that control valve gets is realized controlling the water of the steam generator with the displacement balance of the steam generator
Position is maintained at SG and adjusts water level;Wherein, when the water level of the steam generator adjusts water level in the SG, ensure that described
Nuclear power generating sets stable operation.
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CN102737742B (en) * | 2011-04-02 | 2015-08-05 | 中广核工程有限公司 | Enter and exit the method for digitizing malfunction protocol under a kind of nuclear power plant accident operating mode |
CN103886083A (en) * | 2014-03-26 | 2014-06-25 | 中广核工程有限公司 | Data processing method and system for transient state test of nuclear power unit |
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