CN104299661B - Transient test control method and system used in debugging and starting process of nuclear power station - Google Patents

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

Transient test control method and system in a kind of nuclear power station debugging start-up course

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.