CN104299661A - Transient test control method and system used in debugging and starting process of nuclear power station - Google Patents
Transient test control method and system used in debugging and starting process of nuclear power station Download PDFInfo
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- CN104299661A CN104299661A CN201410535939.8A CN201410535939A CN104299661A CN 104299661 A CN104299661 A CN 104299661A CN 201410535939 A CN201410535939 A CN 201410535939A CN 104299661 A CN104299661 A CN 104299661A
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- G21D3/06—Safety arrangements responsive to faults within the plant
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Abstract
The invention discloses a transient test control method and system used in a debugging and starting process of a nuclear power station, which are used for solving the technical problems in the prior art that the program is complicated, guiding points and operation sheets are excessive and the execution efficiency is low when SOP (State Occurrence Procedure) of a unit of the nuclear power station is used for processing a single nuclear power accident, so that the whole accident processing efficiency in a transient testing process of the nuclear power station is low; the decreasing speed of temperatures and pressure of a primary circuit is high under the special conditions without reactor core residual heat and the like during the debugging and starting process, the SOP cannot control in time, and the requirements on the control of the unit in a testing process cannot be completely met. The method comprises the following steps: starting the SOP of the unit of the nuclear power station and a transient test control regulation; carrying out accident detection on the unit of the nuclear power station through the transient test control regulation to obtain detection information; and determining an accident type of the unit of the nuclear power station based on the detection information, determining an accident processing policy based on the accident type, and intercepting a circulating execution manner of the SOP based on the processing policy, so as to carry out intervene control on the unit of the nuclear power station.
Description
Technical field
The present invention relates to technical field of nuclear power, particularly relate to the transient test control method in a kind of nuclear power station debugging start-up course and system.
Background technology
Pressurized-water reactor nuclear power plant is primarily of part compositions such as pressurized water reactor, primary Ioops system and secondary coolant circuit systems, and primary Ioops system one is connected to reactor core, and other end is connected to steam generator, and wherein, steam generator is connected with secondary coolant circuit system.In the process of nuclear power station generating, the reactor core that pressurized water reactor is made up of low-enrichment uranium carries out nuclear fission reaction, discharges a large amount of heat energy; Chilled 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 flows to steam generator; Hoard in a vapor generator and have light-water (hereinafter referred to as secondary circuit water), pass to secondary circuit water by the heat of heat transfer process primary Ioops water, after secondary circuit water is heated, produce the generating of Steam Actuation turbodynamo.
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 carry out single system debugging to each composition system of nuclear power station, comprising: cold examination; heat examination, charging, red switch; grid-connected, a series of debugging such as generating, thus guarantee that unit can safe and reliable operation.Wherein heat examination is link the most key before reactor reaction cartridge material.
Great transient test during heat examination specifically comprises: COC test, BAS test and the test of peace note, wherein, COC test (I & C Power Outage Tests) i.e. nuclear power plant instrument control instrument dead electricity test, it is distinctive large-scale united test in nuclear power station debugging, this test objective is the safe controllabilitys of checking nuclear power generating sets under power conditions out of hand, the instrument control instrument power supply system of nuclear power station comprises, and normally runs 48V direct supply LCA or LCB, the 110V direct supply LBA etc. that necessary instrument control instrucment and meter plant equipment powers to unit, BAS electrical source exchange test (Electrical Power Supply Change Over Tests) i.e. nuclear power station electrical source of power switching tests, mainly verify under the various operating modes of dead electricity, the correctness of the transfer sequence of service power, wherein, electrical source of power is mainly power-equipment (as main pump, the auxiliary feed water pump etc.) power supply of nuclear power station, Safety Injection (be called for short peace note) system is when the pipeline generation break accident of reactor coolant loop or main steam system, there is provided reactor core emergent cooling, under reactor coolant loop rupture event, can fuel sheath failure be prevented and ensure geometric configuration and the integrality of reactor core, when vapour line breaks, inject high concentration boron water, compensate due to uncontrollably produce steam cause reactor coolant cross cold and cause volume change and reactive increase, and the test of peace note is a large-scale special project test during nuclear power generating sets uniting and adjustment, peace note test objective is the correctness in order to check the rear each system auto-action of peace note, reactor jumps the triggering of heap, the triggering of phase security shell isolation CIA (Containment Isolation Phase A) signal and corresponding auto-action, and the uncap peace beam amount that adjusts during cold examination of nuclear power generating sets is carried out School Affairs and come into force.
But, great transient test during heat examination is all along with the great virtual protection action of each system under test (SUT), also can there is larger change in set state thereupon, if now do not control set state, damage can be caused to nuclear power generating sets equipment, as too highly in primary Ioops system pressure cause pressurizer safety valve unlatching etc., need to be controlled and stable set state by a series of technological means, thus in heat examination process, reduce empirical risk, and can at the appropriate opertaing device of links, and then alleviate or avoid causing device damage, the serious consequences such as unit is out of control.
From the ridge Australia second phase, there is accident at unit or carry out in unit failure test process, prior art Main Basis malfunction protocol controls unit, namely adopt station guide accident treatment program SOP (State Occurrence Procedure), select six status function parameters (the water loading amount of the subcriticality of reactor, primary Ioops water loading amount, primary Ioops pressure and temperature, steam generator, the integrality of steam generator and the integrality of containment) to carry out definite kernel electrification processing policy.In actual moving process, although the accident kind of nuclear power station has a lot, the physical state of nuclear power station is limited, and the information that nuclear power operator can be obtained at master-control room by SOP determines the physical state of reactor core; Under accident conditions, by the situation of six status function parameters of reflection unit, suitable strategy can be chosen to control unit to ensure the safety of reactor core.For the accident occurred, SOP, in the process of check processing, can constantly judge above-mentioned six status function parameters, and by result feedback to operator, operator carries out accident orientation according to the data of feedback again, and revises accident treatment strategy; Visible, it is the large advantage of one that SOP can process superposition accident (as primary Ioops cut, the Nuclear Power Accident etc. losing external power simultaneously).
But, because the great test in heat examination all belongs to specific single incident, that is, during heat examination, transient test generally can not cause six status function (subcriticalities of reactor of nuclear steam supply system NSSS (Nuclear Steam Supply System), primary Ioops water loading amount, primary Ioops pressure and temperature, the water loading amount of steam generator, the integrality of steam generator and the integrality of containment) degradation, now stablize unit and mainly concentrate on steam generator (SG) water lev el control, on primary Ioops temperature and Stress control and primary Ioops water content.Visible, for single Nuclear Power Accident (as losing external power) situation, SOP judges six status functions repeatedly simultaneously, can be caused the accident handling procedure complexity, guiding point is many, and (namely to feed back to the accident information of operator many for SOP, make the accident probability pointed by accident information many), operation sheet many (operation task of namely carrying out for the accident probability determined is many), make for single accident treatment reduction, loaded down with trivial details, execution efficiency is low, the treatment effeciency that finally causes the accident is low; In addition, for distinctive without residual heat of nuclear core situation between the debugging starting period, primary Ioops temperature and pressure declines comparatively fast, and SOP can not control in time, can not the needs of adequacy test completely, and unit allocation difficulty even may be caused to strengthen.
That is, when processing single Nuclear Power Accident, program is complicated, guiding point is many, operation sheet is many, execution efficiency is low for the station guide accident treatment code SOP that there is nuclear power station unit in prior art, and cause the inefficient technical matters of overall accident treatment in nuclear power station transient test process, also exist between the debugging starting period distinctive without situations such as residual heat of nuclear core, primary Ioops temperature and pressure declines very fast, SOP can not control in time, can not meet the technical matters to the needs of unit allocation in process of the test completely.
Summary of the invention
The embodiment of the present application debugs transient test control method in start-up course and system by providing a kind of nuclear power station, the station guide accident treatment code SOP program when processing single Nuclear Power Accident solving prior art center power station unit is complicated, guiding point is many, operation sheet is many, execution efficiency is low, and cause the inefficient technical matters of overall accident treatment in nuclear power station transient test process, and for distinctive without situations such as residual heat of nuclear core between the debugging starting period, primary Ioops temperature and pressure declines very fast, SOP can not control in time, the technical matters to the needs of unit allocation in process of the test can not be met completely, achieve and by described transient test control procedure, the single accident occurred in heat examination transient test is judged efficiently and intervened, when needed, described transient test control procedure interrupts the round-robin implementation of SOP, and intervention control is carried out to described nuclear power station unit, meet the treatment principle of SOP, compensate for the deficiency of SOP in single accident treatment, both described transient test control procedure and SOP combine and more fully can carry out unit failure process, and it is with strong points when controlling set state, program performs succinct, can smoothly and complete transient test efficiently.
On the one hand, the embodiment of the present application provides the transient test control method in a kind of nuclear power station debugging start-up course, and described method comprises the steps:
S1, when nuclear power station transient test starts, start the station guide accident treatment code of nuclear power station unit, start the transient test control procedure of described nuclear power station unit simultaneously;
S2, by described transient test control procedure, accident detection is carried out to described nuclear power station unit, obtain Detection Information;
S3, determine the accident pattern of described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and interrupt the round-robin implementation of described station guide accident treatment code based on described processing policy, and intervention control is carried out to described nuclear power station unit.
Optionally, when the power supply of described nuclear power station unit being switched to the power switching operations of accessory power supply from primary power in the front simulation of step S1, step S3 specifically comprises:
Determine that the accident pattern of described nuclear power station unit is that the power supply of described nuclear power station unit is switched to from primary power the single accident of the first kind that accessory power supply causes described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport based on described Detection Information;
Based on the single accident of the described first kind, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the standard-sized sheet signal of the auxiliary feedwater operation valve controlling the described nuclear power station unit of reset, and regulate the aperture of described auxiliary feedwater operation valve to presetting aperture, the Steam Turbine Bypass System simultaneously controlling described nuclear power station unit stops outside discharged steam, and the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
By controlling the enabling signal of the auxiliary feedwater system of the described nuclear power station unit of reset, and the feedwater flow that described auxiliary feedwater system carries out auxiliary feedwater to the steam generator of described nuclear power generating sets is adjusted to minimum preset flow, the blowdown flow rate simultaneously controlling the steam generator blowdown system of described nuclear power generating sets is reduced to default blowdown flow rate, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
Optionally, when the power supply of described nuclear power station unit being switched to the power switching operations of accessory power supply from primary power in the front simulation of step S1, step S3 also comprises:
Based on described Detection Information determine the accident pattern of described nuclear power station unit be described nuclear power station unit power from primary power be switched to accessory power supply cause described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport after the single accident of Equations of The Second Kind that is energized again;
Based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and before the described main pump of startup, by adjusting setting value of pressure to the first preset pressure value of the Steam Turbine Bypass System of described nuclear power station unit, and the valve controlling described Steam Turbine Bypass System is in closed condition, and the shower valve of the voltage stabilizer of described nuclear power station unit is set to automatic control mode, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
Carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured;
After the described main pump of startup, be in automatic operation mode by controlling described Steam Turbine Bypass System, the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown.
Optionally, when nuclear power station unit described in the front simulation of step S1 be the 48V direct supply of instrument control instrument power supply in described unit dead electricity operation time, step S3 specifically comprises:
Determine that the accident pattern of described nuclear power station unit is the single accident of the 3rd class causing the pneumatic valve of the described auxiliary feedwater system of described nuclear power generating sets to be opened for the 48V direct supply dead electricity of instrument control instrument power supply in described unit of described nuclear power station unit based on described Detection Information;
Based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and be in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, and control described auxiliary feedwater system carries out aperture from the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power generating sets, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured;
By the aperture of auxiliary feedwater operation valve described in regulating and controlling, remain on described SG to make the water level of described steam generator to adjust water level, or being in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station unit remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
By controlling the letdown line of voltage stabilizer of the described primary Ioops system of isolation, and control the described voltage stabilizer of isolation on fill pipeline, the water level realizing controlling described voltage stabilizer remains on voltage stabilizing and to adjust water level; Wherein, when the water level of described voltage stabilizer adjusts water level in described voltage stabilizing, described nuclear power generating sets stable operation can be ensured.
Optionally, when triggering the operation of peace note signal of described nuclear power station unit in the front simulation of step S1, step S3 also comprises:
Determine that the accident pattern of described nuclear power station unit is that the peace note signal of described nuclear power station unit is triggered the single accident of the 4th class causing the primary Ioops system of the safety injection system of described nuclear power station unit to described nuclear power station unit to carry out Safety Injection based on described Detection Information;
Based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and be in closed condition by the Steam Turbine Bypass System controlling described nuclear power station unit, and when the temperature of described primary Ioops system rises to preset temperature, the setting value of pressure of described Steam Turbine Bypass System is adjusted to the second preset pressure value, and the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
After described nuclear power station unit continues to carry out Safety Injection operation preset duration, control the boron injection tank of the described nuclear power station unit of isolation, the water level realizing the voltage stabilizer controlling described nuclear power station unit remains on required value water level; Wherein, when the water level of described voltage stabilizer is at described required value water level, described nuclear power generating sets stable operation can be ensured;
Carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
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, and described system comprises:
Process code start unit, for when nuclear power station transient test starts, starts the station guide accident treatment code of nuclear power station unit, starts the transient test control procedure of described nuclear power station unit simultaneously;
Detection Information acquiring unit, for carrying out accident detection by described transient test control procedure to described nuclear power station unit, obtains Detection Information;
Unit failure processing unit, for determining the accident pattern of described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and interrupt the round-robin implementation of described station guide accident treatment code based on described processing policy, and intervention control is carried out to described nuclear power station unit.
Optionally, when nuclear power station transient test starts, and when the power supply of described nuclear power station unit is switched to the power switching operations of accessory power supply from primary power by simulation, described unit failure processing unit, specifically comprises:
First accident pattern determination module, for determining that based on described Detection Information the accident pattern of described nuclear power station unit is that the power supply of described nuclear power station unit is switched to from primary power the single accident of the first kind that accessory power supply causes described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport;
First temperature, pressure control module, for based on the single accident of the described first kind, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the standard-sized sheet signal of the auxiliary feedwater operation valve controlling the described nuclear power station unit of reset, and regulate the aperture of described auxiliary feedwater operation valve to presetting aperture, the Steam Turbine Bypass System simultaneously controlling described nuclear power station unit stops outside discharged steam, and the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
One SG water lev el control module, for based on the single accident of the described first kind, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the enabling signal of the auxiliary feedwater system controlling the described nuclear power station unit of reset, and the feedwater flow that described auxiliary feedwater system carries out auxiliary feedwater to the steam generator of described nuclear power generating sets is adjusted to minimum preset flow, the blowdown flow rate simultaneously controlling the steam generator blowdown system of described nuclear power generating sets is reduced to default blowdown flow rate, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
Optionally, when nuclear power station transient test starts, and when the power supply of described nuclear power station unit is switched to the power switching operations of accessory power supply from primary power by simulation, described unit failure processing unit, specifically comprises:
Second accident pattern determination module, for determine based on described Detection Information the accident pattern of described nuclear power station unit be described nuclear power station unit power supply from primary power be switched to accessory power supply cause described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport after the single accident of Equations of The Second Kind that is energized again;
Second temperature, pressure control module, for based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and before the described main pump of startup, by adjusting setting value of pressure to the first preset pressure value of the Steam Turbine Bypass System of described nuclear power station unit, and the valve controlling described Steam Turbine Bypass System is in closed condition, and the shower valve of the voltage stabilizer of described nuclear power station unit is set to automatic control mode, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown,
2nd SG water lev el control module, for based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured;
3rd temperature, pressure control module, for based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and after the described main pump of startup, be in automatic operation mode by controlling described Steam Turbine Bypass System, the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown.
Optionally, when nuclear power station transient test starts, and when simulating the dead electricity operation of the 48V direct supply for instrument control instrument power supply in described unit of described nuclear power station unit, described unit failure processing unit, specifically comprises:
3rd accident pattern determination module, for determining that based on described Detection Information the accident pattern of described nuclear power station unit is the single accident of the 3rd class causing the pneumatic valve of the described auxiliary feedwater system of described nuclear power generating sets to be opened for the 48V direct supply dead electricity of instrument control instrument power supply in described unit of described nuclear power station unit;
Three S's G water lev el control module, for based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and be in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, and control described auxiliary feedwater system carries out aperture from the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power generating sets, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, the water level realizing controlling described steam generator remains on SG and to adjust water level, wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured,
4th temperature, pressure control module, for based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the aperture of auxiliary feedwater operation valve described in regulating and controlling, remain on described SG to make the water level of described steam generator to adjust water level, or being in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station unit remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
First water level control of pressurizer module, for based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and by controlling the letdown line of the voltage stabilizer of isolating described primary Ioops system, and control the described voltage stabilizer of isolation on fill pipeline, the water level realizing controlling described voltage stabilizer remains on voltage stabilizing and to adjust water level; Wherein, when the water level of described voltage stabilizer adjusts water level in described voltage stabilizing, described nuclear power generating sets stable operation can be ensured.
Optionally, when nuclear power station transient test starts, and when simulation triggers the operation of peace note signal of described nuclear power station unit, described unit failure processing unit, specifically comprises:
4th accident pattern determination module, for determining that based on described Detection Information the accident pattern of described nuclear power station unit is that the peace note signal of described nuclear power station unit is triggered the single accident of the 4th class causing the primary Ioops system of the safety injection system of described nuclear power station unit to described nuclear power station unit to carry out Safety Injection;
5th temperature, pressure control module, for based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and be in closed condition by the Steam Turbine Bypass System controlling described nuclear power station unit, and when the temperature of described primary Ioops system rises to preset temperature, the setting value of pressure of described Steam Turbine Bypass System is adjusted to the second preset pressure value, and the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
Second water level control of pressurizer module, for based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and after described nuclear power station unit continues to carry out Safety Injection operation preset duration, control the boron injection tank of the described nuclear power station unit of isolation, the water level realizing the voltage stabilizer controlling described nuclear power station unit remains on required value water level; Wherein, when the water level of described voltage stabilizer is at described required value water level, described nuclear power generating sets stable operation can be ensured;
4th SG water lev el control module, for based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
The one or more technical schemes provided in the embodiment of the present application, at least have following technique effect or advantage:
Due in the embodiment of the present application, a kind of transient test control method is proposed by the transient test in starting for debugging, and when nuclear power station transient test starts, start station guide accident treatment code and the transient test control procedure of nuclear power station unit simultaneously, wherein, transient test control procedure is the additional transient test control procedure of of SOP, detects obtain Detection Information for carrying out accident to nuclear power station unit, further, based on this Detection Information determination accident pattern, and draft accident treatment strategy, and interrupt the round-robin implementation of described station guide accident treatment code based on described processing policy, and intervention control is carried out to described nuclear power station unit, described accident treatment strategy can judge the single accident occurred in transient test and intervenes efficiently, the station guide accident treatment code SOP program when processing single Nuclear Power Accident efficiently solving prior art center power station unit is complicated, guiding point is many, operation sheet is many, execution efficiency is low, and cause the inefficient technical matters of overall accident treatment in nuclear power station transient test process, and for distinctive without situations such as residual heat of nuclear core between the debugging starting period, primary Ioops temperature and pressure declines very fast, SOP can not control in time, the technical matters to the needs of unit allocation in process of the test can not be met completely, compensate for the deficiency of SOP in single accident treatment, both described transient test control procedure and SOP combine, more fully can carry out unit failure process, and it is with strong points when controlling set state, program performs succinct, can smoothly and complete transient test efficiently.
Accompanying drawing explanation
In order to be illustrated more clearly in the embodiment of the present invention or technical scheme of the prior art, be briefly described to the accompanying drawing used required in embodiment or description of the prior art below, apparently, accompanying drawing in the following describes is only embodiments of the invention, for those of ordinary skill in the art, under the prerequisite not paying creative work, other accompanying drawing can also be obtained according to the accompanying drawing provided.
The one loop of nuclear power station system architecture schematic diagram that Fig. 1 provides for the embodiment of the present application;
The process flow diagram of the transient test control method in a kind of nuclear power station debugging start-up course that Fig. 2 provides for the embodiment of the present application;
The steam generator water level control system architecture schematic diagram of the nuclear power station that Fig. 3 provides 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 provides for the embodiment of the present application;
Relation schematic diagram is let out under the voltage stabilizer of the nuclear power station that Fig. 5 provides for the embodiment of the present application fills;
The safety injection system structural representation of the nuclear power station that Fig. 6 provides for the embodiment of the present application;
The structured flowchart of the transient test control system in the nuclear power station debugging start-up course that Fig. 7 A-Fig. 7 E provides for the embodiment of the present application.
Embodiment
The embodiment of the present application is by providing the transient test control method in a kind of nuclear power station debugging start-up course, the station guide accident treatment code SOP program when processing single Nuclear Power Accident solving prior art center power station unit is complicated, guiding point is many, operation sheet is many, execution efficiency is low, and cause the inefficient technical matters of overall accident treatment in nuclear power station transient test process, and for distinctive without situations such as residual heat of nuclear core between the debugging starting period, primary Ioops temperature and pressure declines very fast, SOP can not control in time, the needs to unit allocation in process of the test can not be met completely, cause the unmanageable technical matters of unit, achieve and by described transient test control procedure, the single accident occurred in heat examination transient test is judged efficiently and intervened, when needed, described transient test control procedure interrupts the round-robin implementation of SOP, and intervention control is carried out to described nuclear power station unit, meet the treatment principle of SOP, compensate for the deficiency of SOP in single accident treatment, both described transient test control procedure and SOP combine and more fully can carry out unit failure process, and it is with strong points when controlling set state, program performs succinct, can smoothly and complete transient test efficiently, and provide the technique effect of reference frame for the accident treatment in actual motion.
The technical scheme of the embodiment of the present application is for solving the problems of the technologies described above, and general thought is as follows:
The embodiment of the present application provides the transient test control method in a kind of nuclear power station debugging start-up course, described method comprises: when nuclear power station transient test starts, start the station guide accident treatment code of nuclear power station unit, start the transient test control procedure of described nuclear power station unit simultaneously; By described transient test control procedure, accident detection is carried out to described nuclear power station unit, obtain Detection Information; The accident pattern of described nuclear power station unit is determined based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and interrupt the round-robin implementation of described station guide accident treatment code based on described processing policy, and intervention control is carried out to described nuclear power station unit.
Visible, in the embodiment of the present application, a kind of transient test control method is proposed by the transient test in starting for debugging, and when nuclear power station transient test starts, start station guide accident treatment code and the transient test control procedure of nuclear power station unit simultaneously, wherein, transient test control procedure is the additional transient test control procedure of of SOP, detects obtain Detection Information for carrying out accident to nuclear power station unit, further, based on this Detection Information determination accident pattern, and draft accident treatment strategy, and interrupt the round-robin implementation of described station guide accident treatment code based on described processing policy, and intervention control is carried out to described nuclear power station unit, described accident treatment strategy can judge the single accident occurred in transient test and intervenes efficiently, the station guide accident treatment code SOP program when processing single Nuclear Power Accident efficiently solving prior art center power station unit is complicated, guiding point is many, operation sheet is many, execution efficiency is low, and cause the inefficient technical matters of overall accident treatment in nuclear power station transient test process, and for distinctive without situations such as residual heat of nuclear core between the debugging starting period, primary Ioops temperature and pressure declines very fast, SOP can not control in time, the technical matters to the needs of unit allocation in process of the test can not be met completely, compensate for the deficiency of SOP in single accident treatment, both described transient test control procedure and SOP combine, more fully can carry out unit failure process, and it is with strong points when controlling set state, program performs succinct, can smoothly and complete transient test efficiently, and provide reference frame for the accident treatment in actual motion.
In order to better understand technique scheme, below in conjunction with Figure of description and concrete embodiment, technique scheme is described in detail, the specific features being to be understood that in the embodiment of the present application and embodiment is the detailed description to technical scheme, instead of the restriction to technical scheme, when not conflicting, the technical characteristic in the embodiment of the present application and embodiment can combine mutually.
Embodiment one
In actual applications, the primary Ioops system of nuclear power station comprises three loops, please refer to Fig. 1, be the structural representation of a loop of primary Ioops system, comprise: reactor core 101, main pump 102, voltage stabilizer 103, steam generator 104 (primary Ioops side) and various backup system; Wherein, backup system comprises: auxiliary steam generator 104 outwards release water vapor main steam system VVP, be the main feed system ARE (not relating in heat examination) of steam generator 104 water filling and auxiliary feedwater system ASG; Be injected with primary Ioops water 100 in primary coolant circuit pipe, under the dynamic action of main pump 102, order about primary Ioops water 100 and circulate in primary coolant circuit pipe; In the process of circulation, primary Ioops water 100 flows through the heat that reactor core 101 takes away reactor core, transfers heat to the secondary circuit water 105 in steam generator 104 through superheater tube section.Concrete, in primary Ioops, pressure remains on about 15.5MPa.a, the primary Ioops water 100 in loop can be heated to about 327.6 DEG C and do not seethe with excitement under this pressure; The primary Ioops water of 327.6 DEG C flows in the heat-transfer pipe 104-1 of steam generator 104, and the secondary circuit water 105 pressure in steam generator 104 being about about 6.89MPa.a is heated to seethe with excitement (temperature about 283.6 DEG C), form water vapor, then water vapor delivered to steam turbine by main steam system VVP and be used for promoting turbine engine running generating; The primary Ioops water 100 releasing heat energy in heat-transfer pipe 104-1 to reactor core 101, completes primary Ioops circulation with the temperature reflux of about 292.4 DEG C.Due in steam generator 104 secondary circuit water 105 be heated after can become water vapor, auxiliary feedwater system ASG can inject water in steam generator 104, to maintain the water level balance in steam generator 104.
The ruuning situation of the hot functional test of nuclear power station unit when mainly test reactor original state is hot shutdown condition, and when some great transient state actions appear in unit, the accident that may occur for unit positions analysis, and determine accident treatment strategy, thus ensure that set state maintains controllable state.Wherein, reactor hot shutdown refers to, temporary shutdown, (temperature is 291.4 DEG C for running temperature when primary Ioops system (i.e. coolant system) keeps Hot zero power load and pressure, pressure is 15.5MPa.a), secondary coolant circuit system is in hot stand-by duty, at any time can load carrying (namely can drive turbodynamo work at any time); The temperature of primary Ioops and secondary circuit is maintained by the acting of reactor core 101 waste heat and main pump 102 (i.e. cooling medium pump); Primary Ioops pressure is controlled automatically by voltage stabilizer 103.
Before carrying out transient test, first to carry out test to prepare, namely test responsible official and carry out original state setting by debugged program, reactor is arranged on hot shutdown condition, and, in order to ensure accuracy and the security of test, before on-test, test responsible official will confirm the original state of reactor.When on-test, first the transient state action that in hot examination process, unit may occur is simulated, as unit power loss, electrical source exchange, peace note signal are triggered, then execution the embodiment of the present application provides the transient test control method step in a kind of nuclear power station debugging start-up course, please refer to Fig. 2:
S201: when nuclear power station transient test starts, starts the station guide accident treatment code of nuclear power station unit, starts the transient test control procedure of described nuclear power station unit simultaneously; Wherein, described transient test control procedure is specially for the auxiliary accident treatment program that nuclear power station transient test (comprising: BAS test, the test of COC test box peace note) is drafted, can be combined with station guide accident treatment code SOP, efficiently complete the accident treatment in described transient test process;
S202: carry out accident detection to described nuclear power station unit by described transient test control procedure, obtains Detection Information;
S203: the accident pattern determining described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and interrupt the round-robin implementation of described station guide accident treatment code based on described processing policy, and intervention control is carried out to described nuclear power station unit.
In concrete heat examination transient test process; due to some transient state actions that may occur when unit operation can be simulated; the intrinsic operational system of nuclear power station can carry out virtual protection action; but the virtual protection action of system can bring set state to change; during as primary power dead electricity; unit can be powered from primary power and is switched to accessory power supply by system; in this process; main pump dead electricity can be caused to stop transport; thus the temperature and pressure in primary Ioops system is impacted, if it is hardly imaginable not carry out control consequence.Test these transient state actions executed in process are unit accidents in actual moving process; In actual applications, when unit has an accident, unit can running status guiding accident treatment code (SOP) detect accident, and determines resolution policy, to realize controling effectively to set state.Certainly, heat examination transient test is actual is exactly the accident that may occur in simulation unit actual moving process, equally, initiate mode can to lead accident treatment code (SOP) when unit is tested; In the application's scheme, work out according to the experience of the transient test of heat examination in the past the transient test control procedure that a set of single accident (as power loss, electrical source exchange etc.) for occurring in test carries out detection and accident treatment; And when on-test, described transient test control procedure is started while starting state guiding accident treatment code (SOP), respectively by two accident treatment codes, accident is carried out to nuclear power station unit and detect acquisition two groups of Detection Information, further, based on two groups of Detection Information determination accident patterns, and draft accident treatment strategy.
That is, when transient test starts, on the one hand, test responsible official carries out auto-action inspection by debugged program (i.e. preprepared accident program SOP and transient test control procedure), report to the police and check, and utilize the instruments such as the record of digital control system DCS, daily record, external registering instrument, camera video recording to carry out parameter testing record; On the other hand, test responsible official sends out operational order (as tested required operation, restoring electricity) according to debugged program to operations staff, carries out control operation to make operations staff to unit.That is, the operational process of whole transient test is: according to preprepared accident program, performs accidental operation, monitors unit, restores electricity, recover unit work.
In the embodiment of the present application, described transient test control procedure can judge the single accident that heat is tried to occur in transient test and processes efficiently, compensate for the deficiency of SOP in single accident treatment, transient test control procedure and station guide accident treatment code combine and can more fully process the unit failure in heat examination transient test, and it is with strong points when controlling set state, program performs succinct, heat examination transient test can be completed smoothly, can verify whether SOP effectively runs when unit failure simultaneously, and provide reference frame for the accident treatment in actual motion.
Embodiment two
Due to during heat examination, reactor is not feeded, therefore there is no residual heat of nuclear core, the heat in primary Ioops mainly runs the heat produced from primary Ioops main pump, after primary Ioops main pump is all stopped transport, primary Ioops will lose thermal source, can not set up Natural Circulation, if do not carry out relevant control operation, the medial temperature in primary Ioops and pressure will comparatively fast decline, and when primary Ioops sub-cooled, cooling medium (primary Ioops water) can be made to shrink.But in this test, primary Ioops water sub-cooled is shunk, and can not carry out Natural Circulation, primary Ioops P-T region finally may be made to exceed operation limit value, cause transient impact to primary Ioops equipment at primary Ioops.。
In the present embodiment, the transient state action of stopping transport for main pump is tested.Concrete, when hot function test starts, the main pump of primary Ioops system, all in operation, first simulates the power switching operations main pump power supply of described nuclear power station unit being switched to accessory power supply from primary power; When practical operation, described power switching operations can be after 500KV power supply is lost step-down transformer to auxiliary transformer switching action (being called in actual tests that BAS56 test), also can be normal power source to standby power supply blocked operation (being called in actual tests that BAS57 tests), can also be that dead electricity for normally running the 110V direct current LBA power supply that necessary station-service equipment is powered to unit operates (being called in actual tests that COC53 tests); When doing these power switching operations, the main pump in primary Ioops system can be caused all to stop transport.In the process of test, perform the method (as shown in Figure 2) of step S201 ~ S202, step S203: the accident pattern determining described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and the round-robin implementation of described station guide accident treatment code is interrupted based on described processing policy, and intervention control is carried out to described nuclear power station unit, specifically comprise:
Determine that the accident pattern of described nuclear power station unit is that the power supply of described nuclear power station unit is switched to from primary power the single accident of the first kind that accessory power supply causes described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport based on described Detection Information;
Based on the single accident of the described first kind, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the standard-sized sheet signal of the auxiliary feedwater operation valve controlling the described nuclear power station unit of reset, and regulate the aperture of described auxiliary feedwater operation valve to presetting aperture, the Steam Turbine Bypass System GCT simultaneously controlling described nuclear power station unit stops outside discharged steam, and the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
By controlling the enabling signal of the auxiliary feedwater system ASG of the described nuclear power station unit of reset, and the feedwater flow that described auxiliary feedwater system ASG carries out auxiliary feedwater to the steam generator SG of described nuclear power generating sets is adjusted to minimum preset flow, the blowdown flow rate simultaneously controlling the steam generator blowdown system APG of described nuclear power generating sets is reduced to default blowdown flow rate, and the water level realizing controlling described steam generator SG remains on SG and to adjust water level; Wherein, when the water level of described steam generator SG adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
Specifically, when carrying out above-mentioned test, can by controlling from following three aspects nuclear power generating sets:
(1) primary Ioops temperature and pressure controls
For the problem avoiding above-mentioned primary Ioops sub-cooled to trigger peace note, the temperature and pressure of the primary Ioops system controlling described nuclear power station is needed to remain within the scope of the temperature and pressure of described nuclear power station standard hot shutdown.Lower mask body introduces the control method of primary Ioops temperature and pressure:
Please refer to Fig. 3, be the water level control system structural drawing of steam generator, steam generator SG is a cavity container, and cavity inside is hoarded secondary circuit water 302; The bottom of steam generator SG is provided with heat-transfer pipe 301-1, trickle in the pipeline be connected with heat-transfer pipe 301-1 road water 303 (in Fig. 3, ducted arrow indicates the flow direction of water) once, heat-transfer pipe 301-1 is used for when contacting with primary Ioops water 303, and the heat in primary Ioops water 303 is passed to secondary circuit water 302; The lower sidewall of steam generator SG arranges blow-off line 301-2, for being connected with steam generator blowdown system APG; Auxiliary feedwater pipeline 301-3 is provided with, for being connected with auxiliary feedwater system ASG in the middle part of the sidewall of steam generator SG; The top of steam generator SG is provided with row's jet chimney 301-4, for being connected with turbodynamo 304 with the Steam Turbine Bypass System GCT in main steam system; In process of the test, turbodynamo 304 does not work, and is communicated with Steam Turbine Bypass System GCT exports the steam produced mainly through row's jet chimney 301-4.Because steam generator SG can constantly by GCT vent water vapor, and by APG blowdown, in order to keep the water balance in secondary circuit, the water of equivalent can be injected to steam generator SG by auxiliary feedwater system ASG simultaneously, because the temperature of the water newly injected is lower, the heat that heat trnasfer obtains primary Ioops water can be quickly move through; Visible, outwards being discharged vapours by Steam Turbine Bypass System GCT and received auxiliary feedwater system ASG to steam generator SG water supply is the two large principal elements that secondary circuit water 302 takes away primary Ioops water 303 heat.When primary Ioops normally works, this course of work can ensure the temperature and pressure balance of primary Ioops and secondary circuit; But when primary Ioops main pump is stopped transport, primary Ioops loses thermal source, if now secondary circuit still takes away the heat of primary Ioops according to above-mentioned working method, the heat of primary Ioops and pressure will decline fast.Please continue to refer to Fig. 3, the auxiliary feedwater pipeline 301-3 that auxiliary feedwater system ASG feeds water to steam generator SG is provided with auxiliary feedwater operation valve (305-1 and 305-2), can by controlling the standard-sized sheet signal of reset auxiliary feedwater operation valve (305-1 and 305-2), and regulate the aperture of described auxiliary feedwater operation valve (305-1 and 305-2) to presetting aperture, aperture by auxiliary feedwater operation valve adjusts to less than 5% of standard-sized sheet, preferably situation is in closed condition for adjusting to auxiliary feedwater by-pass valve control (305-1 and 305-2), stop the outside discharged steam of Steam Turbine Bypass System GCT simultaneously, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown, wherein, the temperature and pressure scope of nuclear power station standard hot shutdown be primary Ioops temperature within the scope of 284 DEG C ~ 291 DEG C, pressure is in 135 ~ 155 barometric pressure range.
(2) steam generator water level control
While controlling the temperature and pressure of primary Ioops system, also need to control the water level of steam generator, concrete control method is as follows:
Please continue to refer to Fig. 3, auxiliary feedwater system ASG comprises auxiliary feedwater operation valve (305-1 and 305-2), auxiliary feed water pump and auxiliary feed-water tank 306, wherein, auxiliary feed water pump comprises two by the electronic auxiliary feed water pump (ASG001PO and ASG002PO) of power supply as power resources, and two are passed through the turbine driven auxiliary feed-water pump (ASG003PO and ASG004PO) of vapour source as power resources; Auxiliary feedwater system ASG comprises two-way feedwater route to steam generator SG feedwater, one tunnel is, auxiliary feedwater pipeline 301-3 is connected with two electronic auxiliary feed water pumps (ASG001PO and ASG002PO), and lead to auxiliary feed-water tank 306, between auxiliary feedwater pipe 301-3 and electronic auxiliary feed water pump (ASG001PO and ASG002PO), be provided with auxiliary feedwater operation valve 305-1; Another road is, auxiliary feedwater pipeline 301-3 and two turbine driven auxiliary feed-water pump (ASG003PO and ASG004PO), and lead to auxiliary feed-water tank 306, between auxiliary feedwater pipe 301-3 and auxiliary feedwater pneumatic pump (ASG003PO and ASG004PO), be provided with auxiliary feedwater operation valve 305-2.Auxiliary feedwater system is by auxiliary feedwater pump work, water in auxiliary feed-water tank is pumped to steam generator SG, wherein, can pass through to control the rotating speed of auxiliary feed water pump (ASG001PO ~ ASG004PO) and the aperture of water supply control valve (305-2,305-2), control the confluent of auxiliary feedwater system ASG to steam generator SG.
Concrete, in process of the test, when primary Ioops main pump is all stopped transport, auxiliary feedwater system ASG receives enabling signal, need the enabling signal controlling reset auxiliary feedwater system ASG, and the feedwater flow that described auxiliary feedwater system ASG carries out auxiliary feedwater to the steam generator SG of described nuclear power generating sets is adjusted to zero, the blowdown flow rate simultaneously controlling the steam generator blowdown system APG of described nuclear power generating sets is reduced to zero, and the water level realizing controlling described steam generator SG remains on SG and to adjust water level; When the water level of described steam generator SG adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.In all embodiments of the application, the range of steam generator SG is (-1.8m ~+1.8m), described SG adjust water level be specially (-0.58m ~-0.6m) namely meet application requirement.
In addition, in specific implementation process, can feed water to steam generator by blocking auxiliary feedwater system, controlling the water level of steam generator; Concrete, need staff to carry out human intervention stoppage in transit auxiliary feed water pump, thus stop auxiliary feedwater system feeding water to steam generator SG; Wherein, electronic auxiliary feed water pump (ASG001PO, ASG002PO) is stopped transport by disconnecting power switch realization, and auxiliary feedwater pneumatic pump (ASG003PO, ASG004PO) is stopped transport and realized by overspeed protection tripping valve.
Embodiment three
In specific implementation process, primary Ioops system comprises three loops (No. 1 loop, No. 2 loops and 3 ring road), and each loop comprises a main pump and a steam generator.Concrete, No. 1 loop comprises No. 1 main pump RCP001PO and No. 1 steam generator SG1; No. 2 loops comprise No. 2 main pump RCP002PO and No. 1 steam generator SG2; 3 ring road comprises No. 3 main pump RCP003PO and No. 3 steam generator SG3; Further, three loops share an auxiliary feedwater system ASG and Steam Turbine Bypass System GCT.
The primary Ioops temperature, pressure control method mentioned in embodiment two is applicable to control method when three main pumps (RCP001PO ~ RCP003PO) are stopped transport, in specific implementation process, when after electrical source exchange success, main pump again can be energized and starts and start working, in this course, should be noted that and prevent primary Ioops superheated and cause primary Ioops superheated and superpressure, the unit allocation method after electrical source exchange success will be highlighted in the present embodiment.
The present embodiment mainly for be analog power switch disconnect primary power and be switched to accessory power supply be described nuclear power station unit main pump for electric test (being called that BAS54 tests), the power supply of main pump is switched to auxiliary transformer by main-transformer, be that main pump is powered by auxiliary transformer LGB/LGC, wherein, LGB, LGC are to the permanent switchboard of 6.6kV also needing the station-service equipment (comprising main pump) run to power during unit outage.This test is only for the operation that is energized after the main pump dead electricity stoppage in transit of No. 1 loop, and namely No. 2 loops and 3 ring road all have neither part nor lot in test in the present embodiment.
In the process of test, when hot function test starts, the main pump RCP001PO of primary Ioops system normally runs, first the power switching operations No. 1 main pump RCP001PO power supply of described nuclear power station unit being switched to accessory power supply from primary power is performed, perform the method (as shown in Figure 2) of step S201 ~ S202, step S203: the accident pattern determining described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and the round-robin implementation of described station guide accident treatment code is interrupted based on described processing policy, and intervention control is carried out to described nuclear power station unit, specifically comprise:
Based on described Detection Information determine the accident pattern of described nuclear power station unit be described nuclear power station unit power supply from primary power be switched to accessory power supply cause described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport after the single accident of Equations of The Second Kind that is energized again;
Based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and before the described main pump of startup, by adjusting setting value of pressure to the first preset pressure value of the Steam Turbine Bypass System GCT of described nuclear power station unit, and the valve controlling described Steam Turbine Bypass System GCT is in closed condition, and the shower valve of the voltage stabilizer of described nuclear power station unit is set to automatic control mode, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown,
Carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator SG of described nuclear power station unit by the auxiliary feedwater system ASG that controls the described nuclear power station unit of adjustment, the confluent that described steam generator SG is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator SG remains on SG and to adjust water level; Wherein, when the water level of described steam generator SG adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured;
After the described main pump of startup, be in automatic operation mode by controlling described Steam Turbine Bypass System GCT, the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown.
Specifically, when carrying out above-mentioned test, can by controlling from following three aspects nuclear power generating sets:
(1), before starting main pump, primary Ioops temperature and pressure controls
In concrete process of the test, for No. 1 loop, comprise main pump RCP001PO, steam generator SG1, Steam Turbine Bypass System GCT-a at this loop, illustrate in embodiment two, in the process of electrical source exchange, main pump RCP001PO can run out of steam and out of service within a period of time, primary Ioops temperature, pressure is made to have certain decline, thus primary Ioops water is reduced to the heat of the secondary circuit Water transport in steam generator SG1, air pressure in steam generator SG1 reduces, as when main pump RCP001PO normally works, air pressure in steam generator SG1 is 7.6MPa, after main pump RCP001PO stops transport, the air pressure in steam generator SG1 is for being reduced to 7.3MPa, but, in order in the process that normally works at main pump RCP001PO, Steam Turbine Bypass System GCT-a can discharged steam normally, the setting value of pressure of usual setting Steam Turbine Bypass System GCT-a equals the air pressure in steam generator SG1, as 7.6MPa, just can ensure that the steam that steam generator SG1 produces can be discharged from GCT-a smoothly, the current gas pressure in steam generator SG1 is caused to be reduced to 7.3MPa if stopped transport 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, so when electrical source exchange success, main pump RCP001PO be again energized work time, first the heat that primary Ioops produces needs the secondary circuit water heating in steam generator SG1, the steam making its air pressure rise to the generation of 7.6MPa guarantee by 7.3MPa is discharged from Steam Turbine Bypass System GCT-a, and take away heat primary Ioops temperature is reduced, that is, make to rise in the process of 7.6MPa atmospherically in steam generator SG1 in the main pump RCP001PO heat production that works, the heat of primary Ioops is in lasting propradation always, primary Ioops is probably caused to occur the phenomenon of overheated overvoltage.Therefore, for the main pump RCP001PO in above-mentioned primary Ioops system in electrical source exchange test, before main pump RCP001PO starts, need the setting value of pressure adjusting Steam Turbine Bypass System GCT-a to preset pressure value, wherein, preset pressure value is close to the current gas pressure value in steam generator SG1, and as when current gas pressure value is 7.3MPa, preset pressure value is (7.3 ~ 7.4) MPa; Further, as shown in Figure 3, the row's jet chimney 301-4 being communicated with steam generator SG and Steam Turbine Bypass System GCT is provided with steam turbine vent valve 307, in order to prevent secondary circuit when not heat production stopped transport by primary Ioops main pump, still passing through the outside discharged steam of Steam Turbine Bypass System, take away the heat in primary Ioops, control the steam turbine vent valve 307 of closing Steam Turbine Bypass System GCT; In order to can automatically open when overheated overvoltage phenomenon appears in primary Ioops system shower valve be primary Ioops cooling, the shower valve of voltage stabilizer is set to automatic control mode; Above three treatment steps, can implement separately, also can combination in any implement; After carrying out above safeguard measure; restart main pump; the temperature and pressure that effectively can control the primary Ioops system of described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown; wherein, the temperature and pressure scope of nuclear power station standard hot shutdown be primary Ioops temperature within the scope of 284 DEG C ~ 291 DEG C, pressure is within the scope of 13.9MPa.a ~ 15.5MPa.a.
In addition, due in actual moving process, three main pumps in primary Ioops system can work simultaneously, and in each stage, the duty of three main pumps is the same, in order to ensure that three loops are when discharged steam, the air pressure in three loops is in equilibrium state, usually the setting value of pressure of the Steam Turbine Bypass System of three loops is carried out identical setting.
(2) steam generator water level control
Three loops of nuclear power generating sets share an auxiliary feedwater system, the steam generator (SG1, SG2, SG3) of three loops is connected with auxiliary feedwater system respectively by three auxiliary feedwater pipelines, and in order to control the confluent of auxiliary feedwater system to each steam generator, each feedwater piping is provided with auxiliary feedwater operation valve, i.e. No. 1 corresponding No. 1 auxiliary feedwater operation valve of loop, No. 2 corresponding No. 2 auxiliary feedwater operation valves of loop, the corresponding No. 3 auxiliary feedwater operation valves in 3 ring road; When in the process in test, when only No. 1 loop being tested, namely only having main pump RCP001PO operationally, adjusting No. 1 auxiliary feedwater operation valve of the confluent for controlling No. 1 steam generator SG1, auxiliary feedwater system ASG is supplied water to steam generator SG1 by auxiliary feedwater pipeline; Owing to whether working regardless of other loop in three loops, steam generator SG2 in No. 2 loops and the steam generator SG3 in 3 ring road needs by the outside sewage effluent of blowdown control system, in the present embodiment, for No. 2 loops and 3 ring road, respectively by the aperture of control No. 2 auxiliary feedwater operation valves and No. 3 auxiliary feedwater operation valves, to make auxiliary feedwater control system to steam generator SG2, SG3 feedwater, thus compensate the blowdown flow rate of SG2 and the blowdown flow rate of SG3.
Certainly, in specific implementation process, if when the main pump in No. 2 loops and 3 ring road does not participate in test, also the blowoff valve of steam generator SG2 and steam generator SG3 can cut out, now auxiliary feedwater system only need supply water to steam generator SG1, and do not need to supply water to steam generator SG2, SG3, thus ensure the water level balance of SG1, SG2 and SG3.
(3), after starting main pump, primary Ioops temperature and pressure controls
In specific implementation process, after the described main pump of startup, automatic mode is in by controlling Steam Turbine Bypass System, to keep primary Ioops system temperature and pressure to remain within the scope of the temperature and pressure of described nuclear power station standard hot shutdown, namely primary Ioops temperature within the scope of 284 DEG C ~ 291 DEG C, pressure is within the scope of 13.9MPa.a ~ 15.5MPa.a.Concrete, because the heat in primary Ioops is gone out by secondary circuit water-band, and the vapour pressure in steam generator affects by primary Ioops temperature, namely the vapour pressure value of steam generator and primary Ioops temperature have corresponding relation, and Steam Turbine Bypass System can control pneumatic valve according to temperature in primary Ioops system, as when main pump is stopped transport, primary Ioops temperature reduces, cause the vapour pressure in steam generator to reduce, Steam Turbine Bypass System closes pneumatic valve, to ensure that primary Ioops temperature no longer reduces; And for example when main pump restarts, primary Ioops temperature rises, the vapour pressure in steam generator is caused to rise, Steam Turbine Bypass System opens pneumatic valve, and setting value of pressure is set to close to vapour pressure value current in steam generator, primary Ioops temperature no longer rises, to ensure that primary Ioops there will not be overheated overvoltage phenomenon.
Embodiment four
In hot function test, the factor that the primary Ioops temperature and pressure of unit, steam generator water level and voltage stabilizer water level can be caused out of control also: be 48V direct supply LCA or the LCB dead electricity of instrument control instrument power supply in described unit.
Concrete, please refer to Fig. 3, auxiliary feedwater system ASG comprises extra feed valve (305-1 and 305-2), auxiliary feed water pump and auxiliary feed-water tank 306, wherein, auxiliary feed water pump comprises two by the electronic auxiliary feed water pump (ASG001PO and ASG002PO) of power supply as power resources, and two by the turbine driven auxiliary feed-water pump (ASG003PO and ASG004PO) of source of the gas as power resources; Water in auxiliary feed-water tank 306, by auxiliary feedwater pump operation, pumps in steam generator SG by auxiliary feedwater system ASG; Wherein, electronic auxiliary feed water pump ASG001PO and electronic auxiliary feed water pump ASG002PO uses driven by power as power resources; Turbine driven auxiliary feed-water pump ASG003PO and turbine driven auxiliary feed-water pump ASG004PO uses steam driven as power resources.Concrete, nuclear power generating sets comprise three loops: No. 1 loop, No. 2 loops, 3 ring road, each loop comprises a main pump and a steam generator, three steam generators share an auxiliary feedwater system altogether, and the steam generator that auxiliary feedwater system is three loops respectively by different auxiliary feedwater operation valves supplies water; Please refer to Fig. 4, it is the turbine driven auxiliary feed-water pump control schematic diagram of a loop in three loops, turbine driven auxiliary feed-water pump ASG003PO with ASG004PO is connected with row's jet chimney 401 of main steam system (comprising Steam Turbine Bypass System GCT and steam turbine 402), and the steam source pipe road 401-1 for connecting row's jet chimney 401 and pneumatic pump ASG003PO is provided with pneumatic valve ASG137VV, ASG138VV and overspeed protection valve ASG135VV; Wherein, pneumatic valve ASG137VV and pneumatic valve ASG138VV is connected in parallel, and connects with overspeed protection valve ASG135VV respectively, for controlling the air demand of main steam system to pneumatic pump ASG003PO; In addition; steam source pipe road 401-2 for connecting row's jet chimney and pneumatic pump ASG004PO is provided with pneumatic valve ASG237VV, ASG238VV and overspeed protection valve ASG235VV; wherein; pneumatic valve ASG237VV and pneumatic valve ASG238VV is connected in parallel; and connect with overspeed protection valve ASG235VV respectively, for controlling the air demand of main steam system to pneumatic pump ASG004PO.In actual applications, 48V DC control supply LCA is that pneumatic valve ASG137VV and ASG237VV powers, and 48V DC control supply LCB is that pneumatic valve ASG138VV and ASG238VV powers.Under normal circumstances, LCA and LCB normal power supply, pneumatic valve ASG137VV, ASG237VV, ASG138VV and ASG238VV are in closed condition, and turbine driven auxiliary feed-water pump does not run; When LCA or LCB dead electricity, pneumatic valve ASG137/237VV can open, and for pneumatic pump ASG003PO and ASG004PO provides vapour source, makes its startup optimization.In addition, the connecting tube of auxiliary feedwater system and each steam generator is provided with auxiliary feedwater operation valve, as shown in Figure 4, the feedwater piping of the steam generator of auxiliary feedwater system and a loop is provided with an auxiliary feedwater operation valve ASG013VD.When LCA or LCB dead electricity, the automatic standard-sized sheet of auxiliary feedwater operation valve ASG013VD of auxiliary feedwater system is the steam generator water filling of place loop; In like manner, in specific implementation process, the auxiliary feedwater operation valve of other two loops can the automatic standard-sized sheet of dead electricity be also the steam generator water filling of respective place loop.
Due to, pneumatic pump ASG003PO, ASG004PO cannot speed governing, and when the 48V direct current supply losing LCA/LCB, auxiliary feedwater operation valve ASG013VD keeps dead electricity full-gear, cannot adjust flux, and staff cannot carry out Long-distance Control auxiliary feedwater system to the confluent in steam generator in master-control room, thus the water level of steam generator can be caused too high.
In the present embodiment, carry out testing (this test is called that COC50/51 tests) for above-mentioned transient state situation, first, at hot shutdown condition, simulate the dead electricity operation of the 48V direct supply for instrument control instrument power supply in described unit of described nuclear power station unit, then, in the process of test, perform the method (as shown in Figure 2) of step S201 ~ S202, step S203: the accident pattern determining described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and the round-robin implementation of described station guide accident treatment code is interrupted based on described processing policy, and intervention control is carried out to described nuclear power station unit, specifically comprise:
Determine that the accident pattern of described nuclear power station unit is the single accident of the 3rd class causing the pneumatic valve of the described auxiliary feedwater system of described nuclear power generating sets to be opened for the 48V direct supply dead electricity of instrument control instrument power supply in described unit of described nuclear power station unit based on described Detection Information;
Based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and be in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system ASG, and control described auxiliary feedwater system ASG carries out aperture from the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator SG of described nuclear power generating sets, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured;
By the aperture of auxiliary feedwater operation valve described in regulating and controlling, remain on described SG to make the water level of described steam generator SG to adjust water level, or being in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system ASG, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station unit remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
By controlling the letdown line of voltage stabilizer of the described primary Ioops system of isolation, and control the described voltage stabilizer of isolation on fill pipeline, the water level realizing controlling described voltage stabilizer remains on voltage stabilizing and to adjust water level; Wherein, when the water level of described voltage stabilizer adjusts water level in described voltage stabilizing, described nuclear power generating sets stable operation can be ensured.
Specifically, the unit allocation scheme of following three aspects is comprised in the present embodiment:
(1) steam generator water level control
Due to overspeed protection valve ASG135VV connect with pneumatic valve ASG137/138VV, overspeed protection valve ASG235VV connects with pneumatic valve ASG237/238VV; by providing 110V power supply to overspeed protection threshold switch control module; ASG135/235VV is closed; thus block main steam system to pneumatic pump ASG003PO and ASG004PO air feed, pneumatic pump is stopped transport.In actual applications, when LCA and LCB dead electricity, carry out output from manual adjustments auxiliary feedwater system ASG to steam generator SG by staff to the on-the-spot neutral point destroying auxiliary feedwater operation valve by all auxiliary feed water pumps out of service, thus the water level controlling steam generator SG remains on SG adjusts water level.
(2) temperature and pressure of primary Ioops system controls
The water level of steam generator SG is too high, and the vapour pressure in steam generator SG can be caused to raise, thus increases air capacity, and takes away larger primary Ioops heat, and primary Ioops temperature and pressure finally can be caused unbalance.
Under normal circumstances, when hot shutdown, the ideal temperature of primary Ioops system should be 291 DEG C, but in actual mechanical process be impossible make the temperature of primary Ioops remain on exactly 291 DEG C constant, but fluctuate near 291 DEG C, namely the temperature fluctuation range of primary Ioops represents primary Ioops temperature stability; According to practical application request, require to be divided into two kinds of situations to the temperature stability of primary Ioops system, one is that stability requirement is high, and two is that stability requirement is not high; Wherein, stability requirement is high, and to refer to primary Ioops temperature fluctuation range less, i.e. fluctuation within the scope of (291 ± X) DEG C; Stability requirement is not high, and to refer to primary Ioops temperature fluctuation range comparatively large, and be greater than (291+X) DEG C as temperature or be 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 the aperture of staff to the auxiliary feedwater operation valve ASG013VD of Field adjustment auxiliary feedwater system, thus the water level of control steam generator SG remains on SG adjusts water level; When primary Ioops temperature stabilization is less demanding, by the electronic auxiliary feed water pump of start and stop (ASG001PO, ASG002PO) or turbine driven auxiliary feed-water pump (ASG003PO, ASG004PO), stop supplying water to steam generator, thus control the water level of steam generator and remain on SG and to adjust water level; Thus control primary Ioops temperature within the scope of 284 DEG C ~ 291 DEG C, pressure is at about 15.5MPa.a.
(3) water lev el control of primary Ioops steady pressure of system device
Please refer to Fig. 5, first introduce structure and the principle of work of the voltage stabilizer of primary Ioops system.Fig. 5 comprises two water circulation systems.Wherein, one water circulation system comprises: reactor core 501, steam generator 502, main pump 503, water circulation principle is that primary Ioops water is through reactor core 501, take away the heat of reactor core 501, the primary Ioops current that temperature rises are through steam generator 502, transfer heat to the secondary circuit water in steam generator 502, the primary Ioops water reducing temperature, under the effect of main pump 503, returns to reactor core 501.Another water circulation system is the water level control of pressurizer system in primary Ioops system, mainly comprises: voltage stabilizer 504, on fill pipeline 505, letdown line 506, volume control tank 507 and high-pressure safety injection pump 508; When normally working, in order to maintain voltage stabilizer 504 ordinary water level, water in primary Ioops is discharged by letdown line 506 after decrease temperature and pressure process, enters volume control tank 507, pressurize through high-pressure safety injection pump 508 again, fill pipeline 505 on being passed through by water after pressurization afterwards and refill primary Ioops, thus realize the control to the voltage stabilizer water level be connected with primary Ioops; Wherein, the charging stream amount of above filling pipeline 505 is identical with the letdown flow value of letdown line 506.
Nuclear power plant voltage stabilizer 504 is the visual plants in nuclear reaction primary Ioops system, and when steady-state operation, it keeps normal primary Ioops pressure, when transient state its by primary Ioops pressure limitation in permissible value.In addition, voltage stabilizer also as the buffer tank of reactor coolant, buffering primary Ioops expand with heat and contract with cold produce volume change.As shown in Figure 5, under nominal power, in voltage stabilizer 504, about 60% is saturation water 504-1 (being positioned at the bottom of voltage stabilizer container), and 40% is saturated vapour 504-2 (being positioned at the top of voltage stabilizer container); Bottom voltage stabilizer 504, (fluid zone) is connected with the heat pipe section of a loop by Surge line piping, and primary Ioops system other parts are water-filled systems, and the pressure in voltage stabilizer 504 will reach whole primary Ioops system.The water level of voltage stabilizer 504 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 arranged in the fluid zone of voltage stabilizer internal tank, when in voltage stabilizer, pressure reduces, the water of fluid zone is heated, to maintain pressure equilibrium in voltage stabilizer.The principal element of voltage stabilizer SEA LEVEL VARIATION is caused to have: (1) load (water level namely in steam generator 502) changes makes reactor coolant (primary Ioops water) medial temperature change the volume change causing primary Ioops water, wherein, primary Ioops water communicates with the bottom of voltage stabilizer 504, and the water entered bottom voltage stabilizer 504 is the saturation water 504-1 in voltage stabilizer 504; (2) voltage stabilizer 504 charging stream amount and letdown flow imbalance.Voltage stabilizer 504 water level can regulate near setting valve by water level control of pressurizer protection system, guarantees that voltage stabilizer operating condition can meet pressure controlled needs, and proterctive equipment safety.In this test, when after LCA or the LCB direct current supply losing 48V, letdown line 506 there will be automatism isolation (as shown in Figure 5, let out isolation valve 506-1 under closedown), namely letdown line 506 does not carry out draining, but now on fill pipeline 505 still water filling in net voltage stabilizer 504, if do not control, water level in voltage stabilizer 504 continuous rising can even bury in oblivion the vapour chamber on voltage stabilizer 504 top, and make voltage stabilizer 504 lose the function of voltage stabilizing, consequence is hardly imaginable.After LCA or LCB dead electricity, voltage stabilizer water level rises, and when the indicating graduation value of the gauge glass of voltage stabilizer 504 exceedes 30% of its full scale, controls isolation to be filled pipeline (as shown in Figure 5, pass is closed and filled isolation valve 505-1); In actual applications, manually isolate by staff and fill pipeline 505; Thus make the water level of voltage stabilizer 504 remain on voltage stabilizing to adjust water level.In specific implementation process, the range of described voltage stabilizer is (-6m ~+0.38m), and described voltage stabilizing adjusts water level not higher than 30% (namely not higher than the-3m of voltage stabilizer range) of voltage stabilizer range.
Embodiment five
In actual applications, the safety injection system of nuclear power station unit carries out Safety Injection to primary Ioops system, is cause for primary coolant circuit pipe cut the safety practice that the accident of primary Ioops dehydration is taked.In order to verify when Safety Injection, the protection act of unit is correct, needs to carry out the test of peace note when heat is tried.Concrete, peace note test (TP RIS 60) is the large-scale special project test of during nuclear power generating sets uniting and adjustment, this test objective is in order to the correctness of each system auto-action after checking peace note, reactor jump triggering, the phase security shell isolation (CIA of heap, Containment Isolation Phase A) triggering of signal and corresponding auto-action, and the uncap peace beam amount that adjusts during cold examination of nuclear power generating sets is carried out School Affairs and come into force.
After this testing requirements triggers peace note signal; Safety Injection (SI; Safety Injection) and phase security shell isolates (CIA) relevant equipment correct operation, actuation time meets the demands, pacify note sequence of movement and containment isolation order meets reactor protection system (RPR; Reactor Protection) logic, high-pressure safety injection (HHSI, High Head Safety Injection) pump flow meets the demands, the boric acid of boron injection tank (RIS004BA) is injected in major loop.
In the present embodiment, test for the transient state action of peace note, first, when hot function test starts, simulation triggers the operation of the peace note signal of described nuclear power station unit, concrete, first adopts steam generator " two high one low " signal to trigger the action of peace note.In the present embodiment, trigger peace note by No. 2 loops in unit three loops to start, namely first No. 2 steam generator SG2 are arranged atmosphere controlling valve GCT132VV to be placed in manually, then row's atmosphere controlling valve GCT132VV is opened successively to 40%, 70%, 95% aperture, the action of peace note can be triggered.After demonstrating above-mentioned peace note index, in order to avoid the test of peace note causes unit to be difficult to control, and the harm brought and economic loss.In the process of checking peace note index, the impact that may bring to be noted according to peace and take measures to control primary Ioops temperature, voltage stabilizer water level and steam generator water level.In specific implementation process, perform the method (as shown in Figure 2) of step S201 ~ S202, step S203: the accident pattern determining described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and the round-robin implementation of described station guide accident treatment code is interrupted based on described processing policy, and intervention control is carried out to described nuclear power station unit, specifically comprise:
Determine that the accident pattern of described nuclear power station unit is that the peace note signal of described nuclear power station unit is triggered the single accident of the 4th class causing the primary Ioops system of the safety injection system of described nuclear power station unit to described nuclear power station unit to carry out Safety Injection based on described Detection Information;
Based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and be in closed condition by the Steam Turbine Bypass System GCT controlling described nuclear power station unit, and when the temperature of described primary Ioops system rises to preset temperature, the setting value of pressure of described Steam Turbine Bypass System GCT is adjusted to the second preset pressure value, and the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
After described nuclear power station unit continues to carry out Safety Injection operation preset duration, control the boron injection tank of the described nuclear power station unit of isolation, the water level realizing the voltage stabilizer controlling described nuclear power station unit remains on required value water level; Wherein, when the water level of described voltage stabilizer is at described required value water level, described nuclear power generating sets stable operation can be ensured;
Carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator SG of described nuclear power station unit by the auxiliary feedwater system ASG that controls the described nuclear power station unit of adjustment, the confluent that described steam generator SG is got by described auxiliary feedwater operation valve and the water discharge of described steam generator SG balance, and the water level realizing controlling described steam generator SG remains on SG and to adjust water level; Wherein, when the water level of described steam generator SG adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
Specifically, the unit allocation scheme of following three aspects is comprised in the present embodiment:
(1) primary Ioops temperature controls
After peace note signal triggers, safety injection system is to reactor core water filling, guarantee is flooded and is cooled reactor core, prevent molten heap, keep the integrality of reactor core, but in the peace note process of the test of heat examination, reactor core is less than charging, the major heat of primary Ioops runs the heat produced from primary Ioops main pump, start owing to triggering peace note by increasing No. 2 steam generator SG2 row air, primary Ioops temperature can be caused to decline, and then main pump operation heating makes primary Ioops temperature rise, if do not controlled, even the unmanageable scenes such as voltage stabilizer full water can be caused.
To this, after peace note triggers, close Steam Turbine Bypass System first rapidly, prevent it in the process of peace note, continue outwards to export steam, take away the heat of primary Ioops, and cause primary Ioops temperature to decline further; Certainly, in the process, the main pump of primary Ioops still produces heat in operation, rise to prevent primary Ioops temperature that ideal value (291 DEG C) is front causes primary Ioops to expand because steam generator does not have outside discharges heat, in the process that primary Ioops temperature rises, the setting valve of Steam Turbine Bypass System can be turned down, thus while appropriate primary Ioops heat can be taken away, be unlikely to make primary Ioops temperature increase too fast, and remain within the scope of the temperature and pressure of standard hot shutdown.
(2) water level control of pressurizer
Due to after peace note signal triggers, safety injection system is to the water filling of primary Ioops system, but primary Ioops system does not have cut in test, the water of so pacifying note can be hoarded at primary Ioops, if do not controlled, voltage stabilizer full water can be caused and vapour chamber is buried in oblivion, especially in the process of primary Ioops constant temperature rising, primary Ioops water is due to expanded by heating, water level can rise faster, to this, in the present embodiment, by the above-mentioned method controlled primary Ioops temperature, the too fast rising of the water level of voltage stabilizer can be avoided, remain on described required value water level by the water level of isolation boron injection tank control voltage stabilizer simultaneously.In specific implementation process, the range of voltage stabilizer is (-6m ~+3.8m), and described required value water level is 0.9m, and that is, when the water level of voltage stabilizer is 0.9m, system starts the intervention operation of above-mentioned water level control of pressurizer, isolation boron injection tank.
In addition, in unit actual moving process, reactor is equipped with nuclear reaction material, and the origin of heat of primary Ioops system is reactor core nuclear fission, and to this, after peace note signal triggers, safety injection system can to the water filling of primary Ioops system and note boron; Concrete, safety injection system, to reactor core water filling, ensures flood and cool reactor core, prevents molten heap, keeps the integrality of reactor core; Safety injection system notes boron to reactor core, for absorbing reactor core neutron, the reaction velocity of the reactor that slows down; Note test to make peace more to tally with the actual situation, after peace note signal is triggered, safety injection system is simultaneously to primary Ioops water filling and note boron.Concrete, as shown in Figure 6, for the safety injection system structural representation of nuclear power station, safety injection system comprises: material-changing water tank 601 (for providing peace water filling in the present embodiment), high-pressure safety injection pump 602, low pressure safety injection pump 603, peace note isolation valve (604-1,604-2), boron injection tank 605; Wherein, safety injection system carries out peace note by two paths to primary Ioops system: high-pressure safety injection path and low pressure peace note path.Concrete, the principle of work in high-pressure safety injection path is, the peace water filling in material-changing water tank 601, under the driving effect of high-pressure safety injection pump 602, when pacifying note isolation valve 604 and being in opening, injects primary Ioops system by boron injection tank 605; Low pressure peace note path principle of work is that the peace water filling in material-changing water tank 601, under the driving effect of low pressure safety injection pump 603, directly injects primary Ioops system.During due to test, low pressure peace notes the pressure of pressure lower than primary Ioops system in path, and namely safety injection system cannot carry out peace note by low pressure peace note path to primary Ioops, pins path carry out peace note to primary Ioops mainly through high pressure.In figure 6, boron injection tank 605 is driven by high-pressure safety injection pump 602 and injects peace fluid injection body to primary Ioops, and that is, it is the main injection means that peace is noted that boron injects; But at the trial, reactor core, less than charging, after the water level detecting voltage stabilizer reaches described required value, should be isolated boron injection tank 605 in time, avoid injecting too much peace fluid injection body to primary Ioops, and causes unit to be difficult to control.Please continue to refer to Fig. 6, the pipeline of connection high-pressure safety injection pump 602 and boron injection tank 605 is provided with to pacify and notes isolation valve 604-1, and the pipeline between boron injection tank 605 and primary Ioops reactor core is also provided with pacify and notes isolation valve 604-2, the isolation of boron injection tank 605 is in closed condition to realize by controlling peace note isolation valve 604-1 and/or pacifying note isolation valve 604-2, first isolation valve (604-1 is noted at master-control room by remote pilot peace, 604-2), in order to prevent cannot to note isolation valve (604-1 by remote pilot peace at master-control room, 604-2), should prepare for the direct experiment box from electrical panel operation boron injection tank isolation valve before the test, and arrange special messenger at electrical panel place, cannot control by carrying out intervention by test box in time during remote pilot peace note isolation valve at master-control room.Carrying out intervention for preventing electrical panel place test box to lose efficacy, also needing to arrange special messenger to intervene on the spot in peace note isolation 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 control is urgent like that in not having BAS/COC to test, and focuses on avoiding primary Ioops temperature to rise too fast at the test initial stage by control ASG.Concrete, carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator SG of described nuclear power station unit by the auxiliary feedwater system ASG that controls the described nuclear power station unit of adjustment, the confluent that described steam generator SG is got by described auxiliary feedwater operation valve and the water discharge of described steam generator SG balance, and the water level realizing controlling described steam generator SG remains on SG and to adjust water level; Wherein, when the water level of described steam generator SG adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
Embodiment six
Please refer to Fig. 7 A, the transient test control system in the embodiment of the present application in a kind of nuclear power station debugging start-up course, described system comprises:
Process code start unit 701, for when nuclear power station transient test starts, starts the station guide accident treatment code of nuclear power station unit, starts the transient test control procedure of described nuclear power station unit simultaneously;
Detection Information acquiring unit 702, for carrying out accident detection by described transient test control procedure to described nuclear power station unit, obtains Detection Information;
Unit failure processing unit 703, for determining the accident pattern of described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and interrupt the round-robin implementation of described station guide accident treatment code based on described processing policy, and intervention control is carried out to described nuclear power station unit.
In specific implementation process, described transient test control system also comprises unit failure analogue unit 700, for when nuclear power station transient test starts, simulates the interruption of service that described nuclear power station unit occurs in operational process.
Further, please refer to Fig. 7 B, when nuclear power station transient test starts, unit failure analogue unit 700 simulates the power switching operations power supply of described nuclear power station unit being switched to accessory power supply from primary power, and described unit failure processing unit 703, specifically comprises:
First accident pattern determination module 7031-1, for determining that based on described Detection Information the accident pattern of described nuclear power station unit is that the power supply of described nuclear power station unit is switched to from primary power the single accident of the first kind that accessory power supply causes described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport;
First temperature, pressure control module 7031-2, for based on the single accident of the described first kind, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the standard-sized sheet signal of the auxiliary feedwater operation valve controlling the described nuclear power station unit of reset, and regulating the aperture of described auxiliary feedwater operation valve to presetting aperture, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
One SG water lev el control module 7031-3, for based on the single accident of the described first kind, interrupt the round-robin implementation of described station guide accident treatment code, and stop outside discharged steam by the Steam Turbine Bypass System controlling described nuclear power station unit, and the enabling signal of the auxiliary feedwater system of the described nuclear power station unit that resets, and the feedwater flow that described auxiliary feedwater system carries out auxiliary feedwater to the steam generator of described nuclear power generating sets is adjusted to minimum preset flow, the blowdown flow rate simultaneously controlling the steam generator blowdown system of described nuclear power generating sets is reduced to default blowdown flow rate, the water level realizing controlling described steam generator remains on SG and to adjust water level, wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
In specific implementation process, please refer to Fig. 7 C, when nuclear power station transient test starts, unit failure analogue unit 700 simulates the power switching operations power supply of described nuclear power station unit being switched to accessory power supply from primary power, described unit failure processing unit 703, specifically comprises:
Second accident pattern determination module 7032-1, for determine based on described Detection Information the accident pattern of described nuclear power station unit be described nuclear power station unit power supply from primary power be switched to accessory power supply cause described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport after the single accident of Equations of The Second Kind that is energized again;
Second temperature, pressure control module 7032-2, for based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and before the described main pump of startup, by adjusting setting value of pressure to the first preset pressure value of the Steam Turbine Bypass System of described nuclear power station unit, and the valve controlling described Steam Turbine Bypass System is in closed condition, and the shower valve of the voltage stabilizer of described nuclear power station unit is set to automatic control mode, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown,
2nd SG water lev el control module 7032-3, for based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured;
3rd temperature, pressure control module 7032-4, for based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and after the described main pump of startup, be in automatic operation mode by controlling described Steam Turbine Bypass System, the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown.
In specific implementation process, please refer to Fig. 7 D, when nuclear power station transient test starts, unit failure analogue unit 700 simulates the dead electricity operation of the 48V direct supply for instrument control instrument power supply in described unit of described nuclear power station unit, described unit failure processing unit 703, specifically comprises:
3rd accident pattern determination module 7033-1, for determining that based on described Detection Information the accident pattern of described nuclear power station unit is the single accident of the 3rd class causing the pneumatic valve of the described auxiliary feedwater system of described nuclear power generating sets to be opened for the 48V direct supply dead electricity of instrument control instrument power supply in described unit of described nuclear power station unit;
Three S's G water lev el control module 7033-2, for based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and be in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, and control described auxiliary feedwater system carries out aperture from the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power generating sets, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, the water level realizing controlling described steam generator remains on SG and to adjust water level, wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured,
4th temperature, pressure control module 7033-3, for based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the aperture of auxiliary feedwater operation valve described in regulating and controlling, remain on described SG to make the water level of described steam generator to adjust water level, or being in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station unit remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
First water level control of pressurizer module 7033-4, for based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and by controlling the letdown line of the voltage stabilizer of isolating described primary Ioops system, and control the described voltage stabilizer of isolation on fill pipeline, the water level realizing controlling described voltage stabilizer remains on voltage stabilizing and to adjust water level; Wherein, when the water level of described voltage stabilizer adjusts water level in described voltage stabilizing, described nuclear power generating sets stable operation can be ensured.
In specific implementation process, please refer to Fig. 7 E, when nuclear power station transient test starts, the simulation of unit failure analogue unit triggers the operation of the peace note signal of described nuclear power station unit, and described unit failure processing unit 703, specifically comprises:
4th accident pattern determination module 7034-1, for determining that based on described Detection Information the accident pattern of described nuclear power station unit is that the peace note signal of described nuclear power station unit is triggered the single accident of the 4th class causing the primary Ioops system of the safety injection system of described nuclear power station unit to described nuclear power station unit to carry out Safety Injection;
5th temperature, pressure control module 7034-2, for based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and be in closed condition by the Steam Turbine Bypass System controlling described nuclear power station unit, and when the temperature of described primary Ioops system rises to preset temperature, the setting value of pressure of described Steam Turbine Bypass System is adjusted to the second preset pressure value, and the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
Second water level control of pressurizer module 7034-3, for based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and after described nuclear power station unit continues to carry out Safety Injection operation preset duration, control the boron injection tank of the described nuclear power station unit of isolation, the water level realizing the voltage stabilizer controlling described nuclear power station unit remains on required value water level; Wherein, when the water level of described voltage stabilizer is at described required value water level, described nuclear power generating sets stable operation can be ensured;
4th SG water lev el control module 7034-4, for based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
According to description above, transient test control system in the examination of above-mentioned nuclear power station heat is for realizing the transient test control method in the examination of above-mentioned nuclear power station heat, so the course of work of this system is consistent with one or more embodiments of said method, just repeat no longer one by one at this.
Those skilled in the art should understand, embodiments of the invention can be provided as method, system or computer program.Therefore, the present invention can adopt the form of complete hardware embodiment, completely software implementation or the embodiment in conjunction with software and hardware aspect.And the present invention can adopt in one or more form wherein including the upper computer program implemented of computer-usable storage medium (including but not limited to magnetic disk memory, CD-ROM, optical memory etc.) of computer usable program code.
The present invention describes with reference to according to the process flow diagram of the method for the embodiment of the present invention, equipment (system) and computer program and/or block scheme.Should understand can by the combination of the flow process in each flow process in computer program instructions realization flow figure and/or block scheme and/or square frame and process flow diagram and/or block scheme and/or square frame.These computer program instructions can being provided to the processor of multi-purpose computer, special purpose computer, Embedded Processor or other programmable data processing device to produce a machine, making the instruction performed by the processor of computing machine or other programmable data processing device produce device for realizing the function of specifying in process flow diagram flow process or multiple flow process and/or block scheme square frame or multiple square frame.
These computer program instructions also can be stored in can in the computer-readable memory that works in a specific way of vectoring computer or other programmable data processing device, the instruction making to be stored in this computer-readable memory produces the manufacture comprising command device, and this command device realizes the function of specifying in process flow diagram flow process or multiple flow process and/or block scheme square frame or multiple square frame.
These computer program instructions also can be loaded in computing machine or other programmable data processing device, make on computing machine or other programmable devices, to perform sequence of operations step to produce computer implemented process, thus the instruction performed on computing machine or other programmable devices is provided for the step realizing the function of specifying in process flow diagram flow process or multiple flow process and/or block scheme square frame or multiple square frame.
Although describe the preferred embodiments of the present invention, those skilled in the art once obtain the basic creative concept of cicada, then can make other change and amendment to these embodiments.So claims are intended to be interpreted as comprising preferred embodiment and falling into all changes and the amendment of the scope of the invention.
Obviously, those skilled in the art can carry out various change and modification to the present invention and not depart from the spirit and scope of the present invention.Like this, if these amendments of the present invention and modification belong within the scope of the claims in the present invention and equivalent technologies thereof, then the present invention is also intended to comprise these change and modification.
Claims (10)
1. the transient test control method in nuclear power station debugging start-up course, it is characterized in that, described method comprises the steps:
S1, when nuclear power station transient test starts, start the station guide accident treatment code of nuclear power station unit, start the transient test control procedure of described nuclear power station unit simultaneously;
S2, by described transient test control procedure, accident detection is carried out to described nuclear power station unit, obtain Detection Information;
S3, determine the accident pattern of described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and interrupt the round-robin implementation of described station guide accident treatment code based on described processing policy, and intervention control is carried out to described nuclear power station unit.
2. transient test control method as claimed in claim 1, it is characterized in that, when the power supply of described nuclear power station unit being switched to the power switching operations of accessory power supply from primary power in the front simulation of step S1, step S3 specifically comprises:
Determine that the accident pattern of described nuclear power station unit is that the power supply of described nuclear power station unit is switched to from primary power the single accident of the first kind that accessory power supply causes described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport based on described Detection Information;
Based on the single accident of the described first kind, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the standard-sized sheet signal of the auxiliary feedwater operation valve controlling the described nuclear power station unit of reset, and regulate the aperture of described auxiliary feedwater operation valve to presetting aperture, the Steam Turbine Bypass System simultaneously controlling described nuclear power station unit stops outside discharged steam, and the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
By controlling the enabling signal of the auxiliary feedwater system of the described nuclear power station unit of reset, and the feedwater flow that described auxiliary feedwater system carries out auxiliary feedwater to the steam generator of described nuclear power generating sets is adjusted to minimum preset flow, the blowdown flow rate simultaneously controlling the steam generator blowdown system of described nuclear power generating sets is reduced to default blowdown flow rate, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
3. transient test control method as claimed in claim 1, it is characterized in that, when the power supply of described nuclear power station unit being switched to the power switching operations of accessory power supply from primary power in the front simulation of step S1, step S3 also comprises:
Based on described Detection Information determine the accident pattern of described nuclear power station unit be described nuclear power station unit power supply from primary power be switched to accessory power supply cause described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport after the single accident of Equations of The Second Kind that is energized again;
Based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and before the described main pump of startup, by adjusting setting value of pressure to the first preset pressure value of the Steam Turbine Bypass System of described nuclear power station unit, and the valve controlling described Steam Turbine Bypass System is in closed condition, and the shower valve of the voltage stabilizer of described nuclear power station unit is set to automatic control mode, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
Carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured;
After the described main pump of startup, be in automatic operation mode by controlling described Steam Turbine Bypass System, the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown.
4. transient test control method as claimed in claim 1, is characterized in that, when nuclear power station unit described in the front simulation of step S1 be the dead electricity of the 48V direct supply of instrument control instrument power supply in described unit operate time, step S3 specifically comprises:
Determine that the accident pattern of described nuclear power station unit is the single accident of the 3rd class causing the pneumatic valve of the described auxiliary feedwater system of described nuclear power generating sets to be opened for the 48V direct supply dead electricity of instrument control instrument power supply in described unit of described nuclear power station unit based on described Detection Information;
Based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and be in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, and control described auxiliary feedwater system carries out aperture from the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power generating sets, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured;
By the aperture of auxiliary feedwater operation valve described in regulating and controlling, remain on described SG to make the water level of described steam generator to adjust water level, or being in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station unit remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
By controlling the letdown line of voltage stabilizer of the described primary Ioops system of isolation, and control the described voltage stabilizer of isolation on fill pipeline, the water level realizing controlling described voltage stabilizer remains on voltage stabilizing and to adjust water level; Wherein, when the water level of described voltage stabilizer adjusts water level in described voltage stabilizing, described nuclear power generating sets stable operation can be ensured.
5. transient test control method as claimed in claim 1, is characterized in that, when triggering the operation of peace note signal of described nuclear power station unit in the front simulation of step S1, step S3 also comprises:
Determine that the accident pattern of described nuclear power station unit is that the peace note signal of described nuclear power station unit is triggered the single accident of the 4th class causing the primary Ioops system of the safety injection system of described nuclear power station unit to described nuclear power station unit to carry out Safety Injection based on described Detection Information;
Based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and be in closed condition by the Steam Turbine Bypass System controlling described nuclear power station unit, and when the temperature of described primary Ioops system rises to preset temperature, the setting value of pressure of described Steam Turbine Bypass System is adjusted to the second preset pressure value, and the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
After described nuclear power station unit continues to carry out Safety Injection operation preset duration, control the boron injection tank of the described nuclear power station unit of isolation, the water level realizing the voltage stabilizer controlling described nuclear power station unit remains on required value water level; Wherein, when the water level of described voltage stabilizer is at described required value water level, described nuclear power generating sets stable operation can be ensured;
Carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
6. the transient test control system in nuclear power station debugging start-up course, it is characterized in that, described system comprises:
Process code start unit, for when nuclear power station transient test starts, starts the station guide accident treatment code of nuclear power station unit, starts the transient test control procedure of described nuclear power station unit simultaneously;
Detection Information acquiring unit, for carrying out accident detection by described transient test control procedure to described nuclear power station unit, obtains Detection Information;
Unit failure processing unit, for determining the accident pattern of described nuclear power station unit based on described Detection Information, and the processing policy of described accident is determined based on described accident pattern, and interrupt the round-robin implementation of described station guide accident treatment code based on described processing policy, and intervention control is carried out to described nuclear power station unit.
7. transient test control system as claimed in claim 6, it is characterized in that, when nuclear power station transient test starts, and when the power supply of described nuclear power station unit is switched to the power switching operations of accessory power supply from primary power by simulation, described unit failure processing unit, specifically comprises:
First accident pattern determination module, for determining that based on described Detection Information the accident pattern of described nuclear power station unit is that the power supply of described nuclear power station unit is switched to from primary power the single accident of the first kind that accessory power supply causes described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport;
First temperature, pressure control module, for based on the single accident of the described first kind, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the standard-sized sheet signal of the auxiliary feedwater operation valve controlling the described nuclear power station unit of reset, and regulate the aperture of described auxiliary feedwater operation valve to presetting aperture, the Steam Turbine Bypass System simultaneously controlling described nuclear power station unit stops outside discharged steam, and the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
One SG water lev el control module, for based on the single accident of the described first kind, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the enabling signal of the auxiliary feedwater system controlling the described nuclear power station unit of reset, and the feedwater flow that described auxiliary feedwater system carries out auxiliary feedwater to the steam generator of described nuclear power generating sets is adjusted to minimum preset flow, the blowdown flow rate simultaneously controlling the steam generator blowdown system of described nuclear power generating sets is reduced to default blowdown flow rate, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
8. transient test control system as claimed in claim 6, it is characterized in that, when nuclear power station transient test starts, and when the power supply of described nuclear power station unit is switched to the power switching operations of accessory power supply from primary power by simulation, described unit failure processing unit, specifically comprises:
Second accident pattern determination module, for determine based on described Detection Information the accident pattern of described nuclear power station unit be described nuclear power station unit power supply from primary power be switched to accessory power supply cause described nuclear power station unit primary Ioops main pump dead electricity to be stopped transport after the single accident of Equations of The Second Kind that is energized again;
Second temperature, pressure control module, for based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and before the described main pump of startup, by adjusting setting value of pressure to the first preset pressure value of the Steam Turbine Bypass System of described nuclear power station unit, and the valve controlling described Steam Turbine Bypass System is in closed condition, and the shower valve of the voltage stabilizer of described nuclear power station unit is set to automatic control mode, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown,
2nd SG water lev el control module, for based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured;
3rd temperature, pressure control module, for based on the single accident of described Equations of The Second Kind, interrupt the round-robin implementation of described station guide accident treatment code, and after the described main pump of startup, be in automatic operation mode by controlling described Steam Turbine Bypass System, the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown.
9. transient test control system as claimed in claim 6, it is characterized in that, when nuclear power station transient test starts, and when simulating the dead electricity operation of the 48V direct supply for instrument control instrument power supply in described unit of described nuclear power station unit, described unit failure processing unit, specifically comprises:
3rd accident pattern determination module, for determining that based on described Detection Information the accident pattern of described nuclear power station unit is the single accident of the 3rd class causing the pneumatic valve of the described auxiliary feedwater system of described nuclear power generating sets to be opened for the 48V direct supply dead electricity of instrument control instrument power supply in described unit of described nuclear power station unit;
Three S's G water lev el control module, for based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and be in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, and control described auxiliary feedwater system carries out aperture from the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power generating sets, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, the water level realizing controlling described steam generator remains on SG and to adjust water level, wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured,
4th temperature, pressure control module, for based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and pass through the aperture of auxiliary feedwater operation valve described in regulating and controlling, remain on described SG to make the water level of described steam generator to adjust water level, or being in shut down condition by the auxiliary feed water pump controlling described auxiliary feedwater system, the temperature and pressure realizing the primary Ioops system controlling described nuclear power station unit remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
First water level control of pressurizer module, for based on the single accident of described 3rd class, interrupt the round-robin implementation of described station guide accident treatment code, and by controlling the letdown line of the voltage stabilizer of isolating described primary Ioops system, and control the described voltage stabilizer of isolation on fill pipeline, the water level realizing controlling described voltage stabilizer remains on voltage stabilizing and to adjust water level; Wherein, when the water level of described voltage stabilizer adjusts water level in described voltage stabilizing, described nuclear power generating sets stable operation can be ensured.
10. transient test control system as claimed in claim 6, is characterized in that, when nuclear power station transient test starts, and when simulation triggers the operation of peace note signal of described nuclear power station unit, described unit failure processing unit, specifically comprises:
4th accident pattern determination module, for determining that based on Detection Information the accident pattern of described nuclear power station unit is that the peace note signal of described nuclear power station unit is triggered the single accident of the 4th class causing the primary Ioops system of the safety injection system of described nuclear power station unit to described nuclear power station unit to carry out Safety Injection;
5th temperature, pressure control module, for based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and be in closed condition by the Steam Turbine Bypass System controlling described nuclear power station unit, and when the temperature of described primary Ioops system rises to preset temperature, the setting value of pressure of described Steam Turbine Bypass System is adjusted to the second preset pressure value, and the temperature and pressure realizing controlling described primary Ioops system remains within the scope of the temperature and pressure of described nuclear power station standard hot shutdown;
Second water level control of pressurizer module, for based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and after described nuclear power station unit continues to carry out Safety Injection operation preset duration, control the boron injection tank of the described nuclear power station unit of isolation, the water level realizing the voltage stabilizer controlling described nuclear power station unit remains on required value water level; Wherein, when the water level of described voltage stabilizer is at described required value water level, described nuclear power generating sets stable operation can be ensured;
4th SG water lev el control module, for based on the single accident of described 4th class, interrupt the round-robin implementation of described station guide accident treatment code, and carried out the aperture of the auxiliary feedwater operation valve of auxiliary feedwater to the steam generator of described nuclear power station unit by the auxiliary feedwater system that controls the described nuclear power station unit of adjustment, the confluent that described steam generator is got by described auxiliary feedwater operation valve and the water discharge of described steam generator balance, and the water level realizing controlling described steam generator remains on SG and to adjust water level; Wherein, when the water level of described steam generator adjusts water level at described SG, described nuclear power generating sets stable operation can be ensured.
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