CN111561690B - Control method for dealing with pressure relief accidents of secondary sides of all steam generators - Google Patents
Control method for dealing with pressure relief accidents of secondary sides of all steam generators Download PDFInfo
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- CN111561690B CN111561690B CN202010418693.1A CN202010418693A CN111561690B CN 111561690 B CN111561690 B CN 111561690B CN 202010418693 A CN202010418693 A CN 202010418693A CN 111561690 B CN111561690 B CN 111561690B
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B35/00—Control systems for steam boilers
- F22B35/004—Control systems for steam generators of nuclear power plants
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
Abstract
The invention discloses a control method for dealing with pressure relief accidents of the secondary side of all steam generators, which comprises the following steps of S1, judging the accident occurrence reason according to important state parameters and equipment state conditions of a nuclear power plant; s2, performing fault removing operation of corresponding measures according to the judged accident occurrence reason; s3, if the fault removing operation is successful, executing S31; if the troubleshooting operation is unsuccessful, go to S32; s31, selecting a steam generator in a perfect state, and performing water supply control operation and steam exhaust control operation on the steam generator until a cold shut-down state is achieved; and S32, selecting the steam generator in the fault state and carrying out feedwater control operation on the steam generator until the cold shutdown state is reached.
Description
Technical Field
The invention relates to the field of reactor control, in particular to a control method for dealing with pressure relief accidents of the secondary side of all steam generators.
Background
The following accident conditions in a nuclear power plant will result in an uncontrolled drop in the secondary pressure of all steam generators: a main steam pipeline or a main water supply pipeline on the secondary side of the steam generator is broken, and meanwhile, a valve for isolating the broken opening cannot be closed; the control system for controlling the steam discharge sends out a wrong valve opening signal, which causes the steam of the steam generator to be discharged out of control; the steam discharge valve on the steam pipeline is blocked at the opened position and can not be closed. These accidents all result in an uncontrolled drop in the secondary pressure of the steam generator, which in turn leads to a rapid temperature and pressure drop of the reactor coolant system, with the following consequences:
1. because the reactor core has negative feedback effect, excessive positive feedback can be introduced in accidents, the nuclear power is increased finally, and the integrity of fuel elements is damaged;
2. if the discharge point of the secondary side of the steam generator is in the containment, a large amount of high-energy fluid is discharged into the containment after an accident, so that the temperature and the pressure in the containment are increased, and the safety of the containment is threatened;
3. the pressure of a reactor coolant system is rapidly and greatly reduced in a short period, after the safe injection system is automatically started, the boron-containing solution is continuously injected into a primary loop, and the pressure of the reactor coolant system is gradually recovered; if the injection of the safety injection system is not stopped in time, the pressure of the reactor coolant system can be increased to the opening pressure of the protection valve of the voltage stabilizer, and the voltage stabilizer is triggered to release pressure and discharge. The drastic changes in pressure during this process will also pose a threat to the integrity of the equipment;
4. in a short period, the fluid on the secondary side of the steam generator is quickly discharged to cause partial or even all of the heat transfer tubes to be exposed, and the heat transfer tubes are in a dry state, so that the heat transfer tubes can be influenced by thermal shock when excessive low-temperature feed water is injected into the steam generator in the subsequent power plant state recovery process.
The existing nuclear power plant does not take the measures for dealing with the accidents into consideration sufficiently, so that the invention provides an effective dealing scheme, can relieve the accidents and control the state of the nuclear power plant, and ensures that the nuclear power plant is guided to a safe and controllable state under the accidents.
Disclosure of Invention
The invention aims to provide a control method for dealing with pressure relief accidents of all secondary sides of steam generators.
The invention is realized by the following technical scheme:
a control method for dealing with the pressure relief accident of the secondary side of all the steam generators,
the control method comprises the following steps:
s1, judging the accident occurrence reason according to the important state parameters and the equipment state condition of the nuclear power plant;
s2, performing fault removing operation of corresponding measures according to the judged accident occurrence reason;
s3, if the fault removing operation is successful, executing S31; if the troubleshooting operation is unsuccessful, go to S32;
s31, selecting a steam generator in a perfect state, and performing water supply control operation and steam exhaust control operation on the steam generator until the steam generator reaches a state that a normal waste heat exhaust system can be put into operation;
and S32, selecting the steam generator in the fault state and carrying out water supply control operation on the steam generator until the normal operation state of the waste heat discharge system is reached.
And S4, bringing the loop to a cold shutdown state through a normal waste heat discharge system.
The design concept of the invention is as follows:
the technical scheme provides that after the accident that the pressure of all the steam generators is out of control and reduced, the auxiliary water supply of the steam generators is always controlled, so that the heat of the reactor coolant system (loop system) is discharged by the steam generators, the reactor coolant system (loop system) is smoothly cooled to a state that the normal waste heat discharge system can be accessed, and the integrity of the loop system is ensured.
The technical scheme adopts different operation means according to different faults and corresponding differences, so that the heat of the reactor coolant system (a loop system) is quickly, accurately and reasonably discharged by using the steam generator. In the above technical solution, the method first determines the fault through S1 and S2, and S3, S31 and S32 determine different operation routes according to whether different fault operations succeed or not.
In the above process, if the fault-removing operation is successful, it indicates that the steam generator is still in a controllable state, so that it can be regarded as a complete steam generator, the system pressure and temperature can be gradually controlled by feeding water to the steam generator (the execution unit is auxiliary water feeding) and exhausting steam (the execution unit for exhausting steam is an exhaust steam bypass, such as an exhaust atmosphere passage (an open atmosphere relief valve)), different operations are performed at different pressures and temperatures, for example, due to the occurrence of an accident, the safety injection system has been activated, therefore, when the state parameters of the pressure, the coolant charge and the like of the circuit reach the closing condition of the safety injection system, the safety injection system can be closed, after the temperature and the pressure are continuously reduced and the temperature reaches the control condition of the normal waste heat discharge system, the normal waste heat discharge system is started to be put into operation, and finally the cold shutdown state is reached. If the fault removal operation is not successful in the process, the steam release path of the steam generator cannot be controlled, so that the steam generator can be considered as a fault-state steam generator, at the moment, the system is kept to be slowly reduced in pressure and temperature by only treating water (an execution unit is auxiliary water supply), and different operations are performed under different pressures and temperatures by treating the water supply flow.
The further technical scheme is as follows:
the feedwater control operation comprising: starting auxiliary water supply of the steam generator, closing the auxiliary water supply of the steam generator and adjusting the auxiliary water supply flow of the steam generator;
the exhaust control operation includes: starting a steam exhaust bypass of the steam generator, closing the steam exhaust bypass of the steam generator and adjusting the steam exhaust flow of the steam generator.
The further technical scheme is as follows:
s31 specifically includes:
firstly, carrying out water supply control operation on a steam generator in an intact state until the water content is recovered;
when the temperature and the pressure of the reactor coolant system are reduced to reach the termination condition of the safety injection system, the safety injection system corresponding to the reactor coolant system is switched to be terminated;
after the safety injection system is stopped, the steam generator in a complete state is switched to slowly cool and reduce the pressure of the reactor coolant system so as to adjust the auxiliary water feeding flow and the steam discharge flow to perform water feeding control operation and steam discharge control operation;
after the reactor coolant system is cooled and depressurized to reach the normal residual heat removal system input operation temperature and input operation pressure, the normal residual heat removal system corresponding to the reactor coolant system is switched to be input for operation until a cold shutdown state is reached;
the further technical scheme is as follows:
s32 specifically includes:
performing water supply control operation on the steam generator in a fault state, and adjusting the auxiliary water supply flow of the steam generator for the purpose of slowly cooling and depressurizing a reactor coolant system during the water supply control operation;
when the temperature and the pressure of the reactor coolant system are reduced to reach the termination condition of the safety injection system, the safety injection system corresponding to the reactor coolant system is switched to be terminated;
and after the safety injection system is stopped, after the reactor coolant system is cooled and depressurized to reach the normal residual heat removal system input operation temperature and input operation pressure, the normal residual heat removal system corresponding to the reactor coolant system is put into operation until a cold shutdown state is reached.
The further technical scheme is as follows:
the control method is executed when an accident occurs which causes all the steam generator pressure to drop uncontrollably and after the emergency shutdown and the automatic start of the special safety facilities.
The further technical scheme is as follows:
s2 is repeatedly performed while S32 is performed.
The further technical scheme is as follows:
the specific process of the determined accident occurrence reason is as follows: and identifying the pressure and water content change condition of the steam generator, the change condition of the internal environment of the containment, and the valve and pipeline states of the two loops of the steam generator.
The further technical scheme is as follows:
the specific process of performing the troubleshooting operation of the corresponding measure is as follows:
if the accident is judged to be caused by the rupture of the pipeline of the secondary circuit of the steam generator, the starting of an isolating valve on the pipeline of the secondary circuit of the steam generator is tried to be closed so as to isolate the breach;
and if the accident is judged to be caused by the fact that the valve of the steam generator is opened mistakenly, the valve which is opened mistakenly is tried to be closed.
The further technical scheme is as follows:
after trying to start and close an isolation valve on a pipeline of a secondary loop of the steam generator, if the pressure of the steam generator positioned at the upstream of the isolation valve is recovered, judging that the fault removing operation is successful and judging that the steam generator is a steam generator in a good state; if the pressure of the steam generator located upstream of the isolation valve is not restored, it is determined that the troubleshooting operation is not successful and it is determined that the steam generator is a failed steam generator.
After the mistaken opening valve is tried to be closed, if the mistaken opening valve is closed and the pressure of the steam generator positioned at the upstream of the isolation valve is recovered, judging that the fault removing operation is successful and judging that the steam generator is in a good state; and if the mistakenly opened valve is not closed and the pressure of the steam generator positioned at the upstream of the isolation valve is not recovered, judging that the fault removing operation is not successful and judging that the steam generator is in a fault state.
Specifically, the method comprises the following steps:
the invention is used for controlling and recovering the state of the nuclear power plant after the accident of uncontrollable pressure relief of all secondary sides of steam generators occurs in the nuclear power plant, and the specific contents are as follows:
and judging the reason of the accident according to the important state parameters and the equipment state condition of the nuclear power plant.
Trying to remove the fault, and trying to isolate the break if the initial cause of the accident is that the two-loop pipeline is broken; if the valve is opened mistakenly, the valve is tried to be closed.
If the fault is successfully cleared, the plant state is restored by the following method:
recovering the water content of the intact steam generator, and adjusting the water supply flow and steam discharge of the intact steam generator so as to control the state of a loop system; stopping the flow of the safety injection in time; regulating the water supply flow and steam discharge, and orderly cooling and depressurizing the loop system until the normal waste heat discharge system can be put into operation; and the nuclear power plant is withdrawn to a safe and controllable state of cold shutdown through a normal waste heat discharge system.
If the fault cannot be eliminated, the power plant state is recovered by the following method:
cooling and depressurizing a loop system through a fault steam generator, wherein at the moment, the water supply flow flowing into the steam generator needs to be reasonably controlled, and the reactor coolant system is slowly cooled and depressurized until a normal waste heat discharge system can be put into operation; and then, the nuclear power plant is withdrawn to a safe and controllable state of cold shutdown through a normal waste heat discharge system.
The operation process of the invention does not need to add new systems and equipment of the nuclear power plant, and only needs to use the existing related equipment of the nuclear power plant, and mainly comprises main temperature, water level and pressure measuring devices of the nuclear power plant, an auxiliary water supply system and a steam by-pass discharge system of a steam generator, a safety injection system, a normal waste heat discharge system and other related control systems.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic diagram of a prior art nuclear power plant system.
FIG. 2 is a control flow chart of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1
As shown in fig. 1, the conventional nuclear power plant system includes: reactor, steam generator (can be a plurality of), steam turbine, steam generator carry out the heat interaction through a return circuit and reactor, and steam generator carries out the heat interaction through two return circuits and steam turbine, and steam generator disposes supplementary feedwater, steam exhaust bypass, is provided with on the two return circuits and can starts the isolation valve that is used for keeping apart when the return circuit is crevasse, disposes safety injection system and normal waste heat discharge system on the return circuit.
As shown in fig. 2, the general route of the present invention is: firstly, the system measurable data is utilized to judge to obtain the reasons of the secondary side pressure relief accidents, the responding fault elimination operation is executed according to the reasons, and then the cooling and pressure reduction operation of the primary loop system by utilizing the steam generator is determined to be executed according to the success or failure of the fault elimination operation. In order to quickly and accurately realize the cooling and pressure reduction operation. The invention provides a technical route for carrying heat by a circulation zone of a steam generator when fault removal is successful, at the moment, the state of the body part of the steam generator is good, water supply and steam exhaust operations can be carried out on the steam generator, so that the water supply and the steam exhaust can be gradually matched with the reactor core heat production quantity, the pressure and the temperature of a reactor and a loop system are gradually reduced, a safety injection system in a loop is properly controlled in the process, and after a normal waste heat exhaust system is put into operation, the loop is brought to a cold shutdown state by the system. Meanwhile, the invention provides a technical route for carrying heat to the water supply of the steam generator when the fault is not successfully cleared, at the moment, the body part of the steam generator cannot be controlled, and water supply and steam exhaust circulation cannot be formed, so that the water supply flow of the steam generator can be controlled, the water supply flow meets the requirement of heat conduction, the integrity of a heat transfer pipe of the steam generator is ensured, the pressure and the temperature of a reactor and a loop system are gradually reduced, a safety injection system in a loop is properly controlled in the process, and the loop is brought to a cold shutdown state through the system after a normal waste heat discharge system is put into operation. .
Specifically, the control method comprises the following steps:
s1, judging the accident occurrence reason according to the important state parameters and the equipment state condition of the nuclear power plant;
s2, performing fault removing operation of corresponding measures according to the judged accident occurrence reason;
s3, if the fault removing operation is successful, executing S31; if the troubleshooting operation is unsuccessful, go to S32;
s31, selecting a steam generator in a perfect state, and performing water supply control operation and steam exhaust control operation on the steam generator until a normal state that the waste heat exhaust system can be put into operation is reached;
and S32, selecting the steam generator in the fault state and carrying out water supply control operation on the steam generator until reaching a state that the normal waste heat discharge system can be put into operation.
And S4, bringing the loop to a cold shutdown state through a normal waste heat discharge system.
The design concept of the invention is as follows:
the technical scheme provides that after the accident that the pressure of all the steam generators is out of control and reduced, the auxiliary water supply of the steam generators is always controlled, so that the heat of the reactor coolant system (loop system) is discharged by the steam generators, the reactor coolant system (loop system) is smoothly cooled to a state that the normal waste heat discharge system can be accessed, and the integrity of the loop system is ensured.
The technical scheme adopts different operation means according to different faults and corresponding differences, so that the heat of the reactor coolant system (a loop system) is quickly, accurately and reasonably discharged by using the steam generator. In the above technical solution, the method first determines the fault through S1 and S2, and S3, S31 and S32 determine different operation routes according to whether different fault operations succeed or not.
In the above process, if the fault removal operation is successful, it is indicated that the steam generator is still in a controllable state, and therefore it can be considered as a complete steam generator, the system pressure and temperature can be gradually controlled by supplying water (the execution unit is auxiliary water supply) and discharging steam (the execution unit of the discharging steam is a steam discharging bypass, such as an atmospheric air discharging passage (an atmospheric air release valve is opened)) to the steam generator, and different operations are performed at different pressures and temperatures. If the fault removal operation is not successful in the process, the steam generator cannot be controlled, and therefore the steam generator is considered to be a fault-state steam generator, namely, the steam generator is treated only by water supply (an execution unit is auxiliary water supply), the system is kept to slowly reduce the pressure and the temperature by the water supply treatment, and different operations are executed under different pressures and temperatures.
The invention provides a scheme for dealing with pressure relief accidents of all steam generators of a nuclear power plant, which mainly comprises the following steps: 1) the change condition of important state parameters of the power plant and the equipment state are discriminated, and the initial cause of the accident is identified and confirmed; 2) the fault is eliminated by measures such as manually or locally closing the valve; 3) selecting a proper steam generator in combination with the condition of fault removal, and adjusting the water supply flow according to the state of the steam generator so as to control the state of the nuclear power plant; 4) continuously cooling and depressurizing the reactor coolant system to a condition that a normal waste heat discharge system can be put into use; 5) the nuclear power plant is finally guided to a cold shutdown state by a normal waste heat removal system.
By implementing the scheme, the nuclear power plant under the specific complex accident condition can be smoothly guided to a long-term safe and controllable cold shutdown state step by step.
Example 2
Further examples are:
the feedwater control operation comprising: starting auxiliary water supply of the steam generator, closing the auxiliary water supply of the steam generator and adjusting the auxiliary water supply flow of the steam generator;
the exhaust control operation includes: starting a steam exhaust bypass of the steam generator, closing the steam exhaust bypass of the steam generator and adjusting the steam exhaust flow of the steam generator.
Further examples are:
s31 specifically includes:
firstly, carrying out water supply control operation on a steam generator in an intact state until the water content is recovered;
when the state parameters of the loop reach the safety injection termination condition, the safety injection system corresponding to the reactor coolant system is switched to be terminated;
after the safety injection system is stopped, the steam generator in a complete state is switched to slowly cool and reduce the pressure of the reactor coolant system so as to adjust the auxiliary water feeding flow and the steam discharge flow to perform water feeding control operation and steam discharge control operation;
after the reactor coolant system is cooled and depressurized to reach the normal residual heat removal system input operation temperature and input operation pressure, the normal residual heat removal system corresponding to the reactor coolant system is switched to be input for operation until a cold shutdown state is reached;
further examples are:
s32 specifically includes:
performing water supply control operation on the steam generator in a fault state, wherein during the water supply control operation, the auxiliary water supply flow of the steam generator is adjusted for the purposes of slowly reducing the temperature and the pressure of a reactor coolant system and ensuring the integrity of a heat transfer pipe of the steam generator in the fault state;
when the temperature and the pressure of the reactor coolant system are reduced to reach the termination condition of the safety injection system, the safety injection system corresponding to the reactor coolant system is switched to be terminated;
and after the safety injection system is stopped, after the reactor coolant system is cooled and depressurized to reach the normal residual heat removal system input operation temperature and input operation pressure, the normal residual heat removal system corresponding to the reactor coolant system is put into operation until a cold shutdown state is reached.
Further examples are:
the control method is executed when an accident occurs which causes all the steam generator pressure to drop uncontrollably and after the emergency shutdown and the automatic start of the special safety facilities.
Further examples are:
s2 is repeatedly performed while S32 is performed.
Further examples are:
the specific process of the determined accident occurrence reason is as follows: and identifying the pressure and water content change condition of the steam generator, the change condition of the internal environment of the containment, and the valve and pipeline states of the two loops of the steam generator.
Further examples are:
the specific process of performing the troubleshooting operation of the corresponding measure is as follows:
if the accident is judged to be caused by the rupture of the pipeline of the secondary circuit of the steam generator, the starting of an isolating valve on the pipeline of the secondary circuit of the steam generator is tried to be closed so as to isolate the breach;
and if the accident is judged to be caused by the fact that the valve of the steam generator is opened mistakenly, the valve which is opened mistakenly is tried to be closed.
Further examples are:
after trying to close an isolation valve on a pipeline of a secondary loop of the steam generator, if the pressure of the steam generator positioned at the upstream of the isolation valve is recovered, judging that the fault removing operation is successful and judging that the steam generator is a steam generator in a good state; if the pressure of the steam generator located upstream of the isolation valve is not restored, it is determined that the troubleshooting operation is not successful and it is determined that the steam generator is a failed steam generator.
After the mistaken opening valve is tried to be closed, if the mistaken opening valve is closed and the pressure of the steam generator positioned at the upstream of the isolation valve is recovered, judging that the fault removing operation is successful and judging that the steam generator is in a good state; and if the mistakenly opened valve is not closed and the pressure of the steam generator positioned at the upstream of the isolation valve is not recovered, judging that the fault removing operation is not successful and judging that the steam generator is in a fault state.
Example 3
Taking the attached figures 1 and 2 as examples:
when an uncontrolled pressure drop accident occurs on the secondary side of all steam generators of a nuclear power plant, before an operator does not intervene, a scram signal generated in the accident process triggers a scram, and a starting signal of a special safety facility triggers a safety system comprising a safety injection system and an auxiliary water supply system to be put into operation.
Following operator intervention, the operation is performed according to the details of the invention, as follows:
(1) the accident occurrence reason is judged according to important state parameters and equipment state conditions of the nuclear power plant, and the specific method is to identify the pressure and water content change condition of the steam generator, the change condition of the internal environment of the containment vessel and the valve and pipeline states of the two loops of the steam generator comprehensively.
(2) And performing fault removal operation of corresponding measures according to the determined accident occurrence reason. Troubleshooting operations that may be attempted include:
closing an isolation valve with a manual closing button in a manual closing mode;
for valves that cannot be manually operated or that fail manually, the valve is closed in place, if allowed.
(3) If the fault removing operation is successful, the discharge point is isolated, and the following operations are carried out:
(3.1) after the discharge point is isolated, the steam generator (regarded as a steam generator in a perfect state) whose pressure is stopped to drop temporarily closes its steam discharge path while controlling the auxiliary feed water supply of the steam generator (turning on the auxiliary feed water), gradually restoring its water content, thereby restoring its ability to act as a heat sink.
And (3.2) stopping the operation of the safety injection pump and isolating the safety injection box in time in batches when the termination condition of the safety injection system is met, and finishing the termination operation of the safety injection system.
And (3.3) after the water content of the steam generator in the intact state is recovered, controlling the auxiliary feed water flow and the steam discharge flow, carrying out orderly cooling depressurization on the reactor coolant system through the steam generator at the cooling rate acceptable by the equipment until the temperature and pressure conditions are reduced to the temperature and pressure conditions at which the normal waste heat discharge system can be put into operation, and then carrying out the operation of the step (5).
(4) If the troubleshooting operation is unsuccessful and the discharge point cannot be isolated in a short time, the following operations should be performed first, and at the same time, attempts should be made to isolate the discharge point all the time in the process:
and (4.1) controlling the auxiliary water supply of the steam generator (starting the auxiliary water supply) to ensure that the temperature and the pressure of a reactor coolant system (a primary loop system) are slowly reduced. The setting of the water supply flow needs to comprehensively consider two aspects: the feed water flow should not be too large, and the excessive feed water flow can cause the reactor coolant system to be cooled and depressurized more quickly; the water supply flow should not be too small, which would cause the heat transfer tubes of the steam generator to be exposed and to reach a dry state, and subsequently when the water supply is increased, the dry heat transfer tubes may be subjected to thermal shock.
And (4.2) when the termination condition of the safety injection system is met, stopping the safety injection pump and isolating the safety injection box in time in batches to complete the termination operation of the safety injection system.
And (4.3) continuously reducing the temperature and the pressure of the reactor coolant system to the condition that the normal waste heat discharge system can be put into operation.
(5) And opening a path from the normal waste heat discharge system to a loop system, and continuously cooling the reactor coolant system to a safe and controllable state of cold shutdown through the normal waste heat discharge system.
The invention provides a scheme for dealing with pressure relief accidents of all steam generators of a nuclear power plant, which mainly comprises the following steps: 1) the change condition of important state parameters of the power plant and the equipment state are discriminated, and the initial cause of the accident is identified and confirmed; 2) the fault is eliminated by measures such as manually or locally closing the valve; 3) selecting a proper steam generator in combination with the condition of fault removal, and adjusting the water supply flow according to the state of the steam generator so as to control the state of the nuclear power plant; 4) continuously cooling and depressurizing the reactor coolant system to a condition that a normal waste heat discharge system can be put into use; 5) the nuclear power plant is finally guided to a cold shutdown state by a normal waste heat removal system.
By implementing the scheme, the nuclear power plant under the specific complex accident condition can be smoothly guided to a long-term safe and controllable cold shutdown state step by step.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (10)
1. The control method for dealing with the pressure relief accidents of the secondary side of all the steam generators is characterized in that,
the control method comprises the following steps:
s1, judging the accident occurrence reason according to the important state parameters and the equipment state condition of the nuclear power plant;
s2, performing fault removing operation of corresponding measures according to the judged accident occurrence reason;
s3, if the fault removing operation is successful, executing S31; if the troubleshooting operation is unsuccessful, go to S32;
s31, selecting a steam generator in a perfect state, and performing water supply control operation and steam exhaust control operation on the steam generator until a normal state that the waste heat exhaust system can be put into operation is reached;
s32, selecting a steam generator in a fault state and carrying out water supply control operation on the steam generator until a normal state that the waste heat discharge system can be put into operation is reached;
and S4, bringing the primary circuit to a cold shutdown state through a normal waste heat discharge system.
2. The control method for dealing with the secondary side pressure relief accident of all the steam generators according to claim 1, wherein,
the feedwater control operation comprising: starting auxiliary water supply of the steam generator, closing the auxiliary water supply of the steam generator and adjusting the auxiliary water supply flow of the steam generator;
the exhaust control operation includes: starting a steam exhaust bypass of the steam generator, closing the steam exhaust bypass of the steam generator and adjusting the steam exhaust flow of the steam generator.
3. The control method for dealing with the secondary side pressure relief accident of all the steam generators according to claim 1, wherein,
s31 specifically includes:
firstly, carrying out water supply control operation on a steam generator in an intact state until the water content is recovered;
when the temperature and the pressure of the reactor coolant system are reduced to reach the end operation condition of the safety injection system, the safety injection system corresponding to the reactor coolant system is switched to be stopped;
after the safety injection system is stopped, the steam generator in a complete state is switched to slowly cool and reduce the pressure of the reactor coolant system so as to adjust the auxiliary water feeding flow and the steam discharge flow to perform water feeding control operation and steam discharge control operation;
and after the reactor coolant system is cooled and depressurized to reach the normal residual heat removal system input operation temperature and input operation pressure, performing input operation on the normal residual heat removal system corresponding to the reactor coolant system until a cold shutdown state is reached.
4. The control method for dealing with the secondary side pressure relief accident of all the steam generators according to claim 1, wherein,
s32 specifically includes:
performing water supply control operation on the steam generator in a fault state, and adjusting the auxiliary water supply flow of the steam generator for the purpose of slowly cooling and depressurizing a reactor coolant system during the water supply control operation;
when the temperature and the pressure of the reactor coolant system are reduced to reach the end operation condition of the safety injection system, the safety injection system corresponding to the reactor coolant system is switched to be stopped;
and after the safety injection system is stopped, after the reactor coolant system is cooled and depressurized to reach the normal residual heat removal system input operation temperature and input operation pressure, the normal residual heat removal system corresponding to the reactor coolant system is put into operation until a cold shutdown state is reached.
5. The control method for dealing with the secondary side pressure relief accident of all the steam generators according to claim 1, wherein,
the control method is executed when an accident occurs which causes all the steam generator pressure to drop uncontrollably and after the emergency shutdown and the automatic start of the special safety facilities.
6. The method for controlling the secondary side pressure relief accident of all steam generators according to any one of claims 1 to 5,
s2 is repeatedly performed while S32 is performed.
7. The method for controlling the secondary side pressure relief accident of all steam generators according to any one of claims 1 to 5,
the specific process of the determined accident occurrence reason is as follows: and identifying the pressure and water content change condition of the steam generator, the change condition of the internal environment of the containment, and the valve and pipeline states of the two loops of the steam generator.
8. The method for controlling the secondary side pressure relief accident of all steam generators according to any one of claims 1 to 5,
the specific process of performing the troubleshooting operation of the corresponding measure is as follows:
if the accident is judged to be caused by the rupture of the pipeline of the secondary circuit of the steam generator, the starting of an isolating valve on the pipeline of the secondary circuit of the steam generator is tried to be closed so as to isolate the breach;
and if the accident is judged to be caused by the fact that the valve of the steam generator is opened mistakenly, the valve which is opened mistakenly is tried to be closed.
9. The control method for dealing with the secondary side pressure relief accident of all steam generators of claim 8, wherein,
after trying to start and close an isolation valve on a pipeline of a secondary loop of the steam generator, if the pressure of the steam generator positioned at the upstream of the isolation valve is recovered, judging that the fault removing operation is successful and judging that the steam generator is a steam generator in a good state; if the pressure of the steam generator located upstream of the isolation valve is not restored, it is determined that the troubleshooting operation is not successful and it is determined that the steam generator is a failed steam generator.
10. The control method for dealing with the secondary side pressure relief accident of all steam generators of claim 8, wherein,
after the mistaken opening valve is tried to be closed, if the mistaken opening valve is closed and the pressure of the steam generator positioned at the upstream of the isolation valve is recovered, judging that the fault removing operation is successful and judging that the steam generator is in a good state; and if the mistakenly opened valve is not closed and the pressure of the steam generator positioned at the upstream of the isolation valve is not recovered, judging that the fault removing operation is not successful and judging that the steam generator is in a fault state.
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