CN113972014B - Pile hole water injection control system - Google Patents
Pile hole water injection control system Download PDFInfo
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- CN113972014B CN113972014B CN202111205266.6A CN202111205266A CN113972014B CN 113972014 B CN113972014 B CN 113972014B CN 202111205266 A CN202111205266 A CN 202111205266A CN 113972014 B CN113972014 B CN 113972014B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
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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
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- Y02E30/30—Nuclear fission reactors
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Abstract
The application relates to a pit water injection control system. The pit water injection control system is used for controlling an executing mechanism arranged on a pit water injection pipeline and comprises a first control system and a second control system; the first control system is used for outputting a normally-off signal to the execution mechanism when the pit water injection condition is not met, and stopping outputting the normally-off signal to the execution mechanism when the pit water injection condition is met; the second control system is used for outputting an opening signal to the executing mechanism under the condition that the pit water injection condition is met; the actuating mechanism is started under the condition that the actuating mechanism receives the starting signal and does not receive the normally-closed signal. The application adopts automatic control, breaks away from the requirement of manual operation, and realizes automatic control of pit water injection, thereby effectively reducing the operation time of an executing mechanism and the load of an operator.
Description
Technical Field
The application relates to the technical field of automatic control, in particular to a pit water injection control system.
Background
In the design of a pressurized water reactor nuclear power plant, the radioactive consequences of serious accidents are limited, the emission of radioactive substances into the environment is minimized, and serious accident suppression measures are provided, wherein one of the measures is melt retention, namely, high-radioactivity melt in serious accidents is retained in a pressure container by ensuring the integrity of the pressure container, and the method used is pit water injection; and the pressure vessel is in the high pressure state and the water injection mistake can bring thermal shock, probably lead to the pressure vessel to disintegrate fast, on the contrary produces high risk. Therefore, it is necessary to prevent the water from being erroneously injected into the pit.
In the prior art, manual control is adopted for completing pit water injection, and an isolation valve is electrically isolated to achieve the purpose of preventing false water injection. The method comprises the steps that after the temperature of the outlet of the reactor core reaches a specified temperature, an operator reaches an electric equipment room to execute electric isolation removing work after taking an electric isolation removing ticket, the operator is informed of the fact that the electric isolation removing work is finished, then the operator of the main control room confirms the pit water filling condition and then manually presses an operation button for opening an isolation valve in the main control room to finish pit water filling operation.
However, at present, aiming at preventing the false water injection of the pit, the manual control method is adopted to finish the pit water injection, more time is consumed for opening the isolation valve after the original electrical isolation is released due to manual operation, the environment after serious accidents is complex, the load of related operators is high, the requirement of manual control on the operators is high, and the load of the operators is high.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a pit water injection control system with high reliability that can achieve automatic control.
The pit water injection control system is used for controlling an executing mechanism arranged on a pit water injection pipeline and comprises a first control system and a second control system; the first control system is used for outputting a normally-off signal to the executing mechanism when the pit water injection condition is not met, and stopping outputting the normally-off signal to the executing mechanism when the pit water injection condition is met; the second control system is used for outputting an opening signal to the executing mechanism under the condition that the water injection condition of the pit is met; the actuating mechanism is used for being started under the condition that the starting signal is received and the normally-closed signal is not received.
In one embodiment, the second control system is further connected to a pit water level testing module, and the pit water level testing module is used for sending a closing signal to the second control system under the condition that the pit water level reaches a preset water level value; and after receiving the closing signal sent by the pit water level testing module, the second control system stops outputting the opening signal to the executing mechanism.
In one embodiment, the first control system and the second control system are specifically configured to:
determining whether the water injection condition of the pit is met according to the working state information of the reactor; wherein, the working state information comprises a reactor core outlet temperature value and a loop pressure value; or the operating state information includes the core outlet temperature value, the primary circuit pressure value and the radioactive dose in the containment; or the working state information comprises a reactor core outlet temperature value, a loop pressure value and the hydrogen concentration in the containment;
or the operating state information includes the core outlet temperature value, the one-circuit pressure value, the radioactive dose in the containment vessel, and the hydrogen concentration in the containment vessel.
In one embodiment, the pit water injection control system further comprises:
A plurality of signal acquisition cards, wherein the plurality of signal acquisition cards are used for acquiring working state information; the first control system and the second control system are used for acquiring the working state information from the signal acquisition cards with diversity.
In one embodiment, the operational status information includes a plurality of information types; the first control system and the second control system are used for determining that the pit water injection condition is met when the working state information of various information types meets the corresponding preset conditions.
In one embodiment, the operating condition information includes a core outlet temperature value; the first control system and the second control system are used for acquiring a plurality of reactor core outlet temperature values and determining a next-largest value from the plurality of reactor core outlet temperature values; the first control system and the second control system are used for determining that the reactor core outlet temperature value meets the corresponding preset condition under the condition that the next maximum value is larger than the preset temperature threshold value.
In one embodiment, a plurality of temperature sensors are provided at the core outlet; the first control system and the second control system are used for acquiring the reactor core outlet temperature value measured by each temperature sensor.
In one embodiment, the first control system and the second control system are specifically configured to:
And filtering the plurality of core outlet temperature values, and determining a next-largest value from the plurality of core outlet temperature values obtained after the filtering.
In one embodiment, the operating condition information includes a circuit pressure value; the first control system and the second control system are used for acquiring a plurality of loop pressure values and detecting whether the loop pressure values are smaller than a preset pressure threshold value or not; the first control system and the second control system are used for determining that the loop pressure value meets the corresponding preset condition when the number of the target loop pressure values smaller than the preset pressure threshold value meets the first preset number condition.
In one embodiment, a plurality of pressure sensors are provided in a circuit; the first control system and the second control system are used for acquiring a loop pressure value measured by each pressure sensor.
In one embodiment, the operational status information includes a radiation dose within the containment vessel; the first control system and the second control system are used for acquiring a plurality of radioactive doses and detecting whether each radioactive dose is larger than a preset dose threshold value or not; the first control system and the second control system are used for determining that the radioactive dose meets the corresponding preset condition when the number of the radioactive doses larger than the preset dose threshold meets the second preset number condition.
In one embodiment, a plurality of radiation dose detection devices are disposed within the containment vessel; the first control system and the second control system are used for acquiring the radioactive doses measured by the radioactive dose detection devices.
In one embodiment, the operating state information includes a hydrogen concentration within the containment vessel; the first control system and the second control system are used for acquiring a plurality of hydrogen concentrations and detecting whether each hydrogen concentration is larger than a preset concentration threshold value or not; the first control system and the second control system are used for determining that the hydrogen concentration meets the corresponding preset conditions when the quantity of the hydrogen concentration larger than the preset concentration threshold meets the third preset quantity condition.
In one embodiment, a plurality of hydrogen concentration detection devices are arranged inside the containment vessel; the first control system and the second control system are used for acquiring the hydrogen concentration measured by each hydrogen concentration detection device.
In one embodiment, the pit water injection control system includes at least two first control systems.
In one embodiment, the software program installed in each of the first control systems and the software program installed in the second control system are different.
In one embodiment, at least two execution mechanisms are arranged on the pit water injection pipeline; and the pit water injection control system is used for controlling each executing mechanism.
In one embodiment, the pit water injection control system further comprises a plurality of device driving cards, wherein the plurality of device driving cards are connected with the executing mechanism, and the plurality of device driving cards are used for driving the executing mechanism to be started under the condition that the opening signal is received and the normally-closed signal is not received.
According to the pit water injection control system, the first control system and the second control system control the executing mechanism on the pit water injection pipeline, so that the manual operation requirement is eliminated, automatic pit water injection control is realized, and the operation time of the executing mechanism and the load of an operator are effectively reduced; the first control system outputs a normally-closed signal to the actuating mechanism closing lock under the condition that the pit water injection condition is not met, and sends a release command to the valve closing lock under the condition that the pit water injection condition is met, so that high reliability of preventing pit error water injection is realized.
Drawings
FIG. 1 is a schematic diagram of a manual control pit water injection system according to an embodiment of the present application;
Fig. 2 is a schematic structural diagram of a pit water injection control system according to an embodiment of the present application;
FIG. 3 is a schematic connection diagram of a pit water level test module according to an embodiment of the present application;
fig. 4 is a schematic structural diagram of a first control system according to an embodiment of the present application;
fig. 5 is a schematic structural diagram of a second control system according to an embodiment of the present application;
FIG. 6 is a schematic diagram of a process for obtaining an outlet core temperature value according to an embodiment of the present application;
FIG. 7 is a schematic diagram of a loop pressure value obtaining process according to an embodiment of the present application;
FIG. 8 is a schematic illustration of a radioactive dose acquisition process within a containment vessel provided in an embodiment of the present application;
FIG. 9 is a schematic diagram of a process for obtaining hydrogen concentration in a containment vessel according to an embodiment of the present application;
FIG. 10 is a schematic diagram of a signal acquisition system according to an embodiment of the present application;
FIG. 11 is a schematic diagram of a device driving system according to an embodiment of the present application;
fig. 12 is a schematic diagram of an automatic control structure according to an embodiment of the present application.
Detailed Description
The present application will be described in further detail with reference to the drawings and examples, in order to make the objects, technical solutions and advantages of the present application more apparent. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the application.
In the design of pressurized water reactor nuclear power plants, to limit the radioactive consequences of serious accidents, to minimize the discharge of radioactive substances to the environment, serious accident suppression measures are provided, one of which is melt Retention (In-Vessel recovery), i.e. by ensuring the integrity of the pressure Vessel, high-radioactivity melt In serious accidents is retained In the pressure Vessel, and the corresponding measure is pit water injection.
Under severe accident conditions, in order to ensure the integrity of the pressure vessel, when the temperature of the outlet of the reactor core reaches a certain temperature value and the pressure value of a loop is lower than a certain pressure value, a pit water injection function is started, water is injected into the pit, the inside of the containment vessel is cooled, decay heat of reactor core melt is taken away, the pressure vessel is prevented from being penetrated by melting, and radioactive substances are retained in the pressure vessel.
The pressure vessel is in the high pressure state and the water is injected by mistake and can bring thermal shock, possibly lead to the pressure vessel to disintegrate fast, but rather produce high risk. Therefore, it is necessary to prevent false water injection of the pit and to complete water injection within a limited time during water injection, and thus, the reliability of pit water injection control is extremely high.
In the related art, the isolation valve is electrically isolated by adopting manual control, so that false water injection is prevented, and operators need to finish manual water injection within a limited time under serious accidents. Referring to fig. 1, a schematic structural diagram of a manual control pit water injection system is shown, the manual control pit water injection system comprises a main control room and an electric device room, a first manual control button 101 and a second manual control button 102 are arranged in the main control room, an electric distribution board is arranged between the electric devices, and an electric isolating switch 103, an electric isolating switch 104, an isolating valve 105 and an isolating valve 106 are arranged on the electric distribution board; the first manual control button 101 is connected with the first electric isolating switch 103 and used for controlling the first isolating valve 105, and the second manual control button 102 is connected with the second electric isolating switch 104 and used for controlling the second isolating valve 106. When the temperature of the outlet of the reactor core reaches a specified temperature, a field operator arrives at an isolation office to remove an electrical isolation work ticket, then reaches an electrical equipment room to reach a position of an electrical switch board, identifies a valve power supply loop drawer in the electrical switch board, removes the drawer lock by a key, pushes the drawer to a closed position, rotates a knob to an electrified position, closes a first electrical isolation switch 103 and a second electrical isolation switch 104, and then informs a master control room operator that the field electrical isolation is removed; after receiving the message that the on-site electrical isolation is released and confirming the reactor cavity water injection condition, the operator of the main control room presses the first manual control button 101 and the second manual control button 102, so that the first isolation valve 105 and the second isolation valve 106 are opened, and the reactor pit water injection operation is completed.
However, in practice, it is found that, because the electric switchboard and the control equipment of the main control room are located on different floors and rooms, the distance is long, and a lot of time is consumed for manually controlling to release the original electric isolation and then opening the isolation valve under serious accidents, and the environment after serious accidents is complex, so that the load of operators is large and the requirements on operators are high. In view of the above, the embodiment of the application provides a pit water injection control system, which can effectively reduce the valve operation time due to the elimination of electrical isolation, reduces the load of operators by adopting automatic control, and improves the safety level of a nuclear power plant.
Referring to fig. 2, a schematic structural diagram of a pit water injection control system according to an embodiment of the present application is shown, where the pit water injection control system is used for controlling an actuator 201 disposed on a pit water injection pipeline 202, and the pit water injection control system includes a first control system and a second control system.
The first control system is configured to output a normally-off signal to the actuator 201 when the pit water injection condition is not satisfied, and to stop outputting the normally-off signal to the actuator 201 when the pit water injection condition is satisfied.
Under the condition that the pit water injection condition is not met, the first control system outputs a normally-off signal to the executing mechanism, so that when the pit water injection control system does not meet the pit water injection condition, the executing mechanism cannot be started, the first control system plays a role of locking the executing mechanism, and when the pit water injection condition is met, the executing mechanism can be started, the first control system stops outputting the normally-off signal, namely, the executing mechanism is unlocked.
A second control system, configured to output an opening signal to the actuator 201 when the pit water injection condition is satisfied; the actuator 201 is configured to be turned on when an on signal is received and a normally off signal is not received.
And when the second control system meets the condition, sending an opening signal to the executing mechanism, namely, the second control system is used for driving the executing mechanism to be opened, and the second control system is different from the first control system in realizing the function of locking the executing mechanism.
The actuator 201 may be a pump or a valve; the hydraulic device can be in an on state or an off state, a large number of wide hydraulic devices are used in the nuclear power station, the actuating mechanism is a key accessory for safe operation of the nuclear power station, in the embodiment of the application, the actuating mechanism 201 is arranged on the water injection pipeline, when the actuating mechanism 201 is opened, the pit water injection pipeline 202 can inject water into the pit, and when the actuating mechanism 201 is closed, the pit water injection pipeline 202 cannot inject water into the pit.
In the embodiment of the application, the first control system and the second control system are automatic control systems, manual operation is not needed, certain cost advantages are realized, the equipment starting time is shortened, and the load of an operator is effectively reduced; when the first control system in the pit water injection control system does not meet the pit water injection condition, a normally-off signal is output to the execution mechanism 201, and when the first control system meets the pit water injection condition, the normally-off signal is stopped to be output to the execution mechanism 201, and when the second control system meets the pit water injection condition, an opening signal is output to the execution mechanism 201, the execution mechanism 201 can be opened, so that the execution mechanism 201 is controlled to be opened or closed through double combination of the first control system and the second control system, the possibility of preventing false pit water injection is effectively improved, and the high reliability of the pit water injection control system is ensured.
In the embodiment of the application, the second control system is also connected with a pit water level testing module, and the pit water level testing module is used for sending a closing signal to the second control system under the condition that the pit water level reaches a preset water level value; and after receiving the closing signal sent by the pit water level testing module, the second control system stops outputting the opening signal to the executing mechanism.
For example, please refer to fig. 3, which illustrates a connection schematic diagram of a pit water level testing module provided by an embodiment of the present application, where the pit water level testing module is connected to a second control system and is used for determining whether the water level of the pit reaches a preset water level value; when the water level of the pit meets the preset water level value condition, the pit water level testing module sends a closing signal to the second control system, and after the second control system receives the closing signal, the second control system stops outputting an opening signal to the executing mechanism, so that the executing mechanism is controlled to be closed, and the pit water injection operation is stopped.
In an alternative embodiment of the application, the first control system and the second control system are used for determining whether the pit water injection condition is met according to the working state information of the reactor; the operating state information includes a plurality of information types; the first control system and the second control system are used for determining that the pit water injection condition is met when the working state information of various information types meets the corresponding preset conditions.
For example, please refer to fig. 4, which illustrates a schematic structural diagram of a first control system according to an embodiment of the present application; the first control system includes a plurality of technical processing modules, optionally, a corresponding number of technical processing modules may be set according to the number of operating status information of the reactor, and in an exemplary embodiment, only two technical processing modules, that is, a first technical processing module 401 and a second technical processing module 402 are adopted in the embodiment of the present application, and the first control system further includes a nand module 403.
The first technical process module 401 and the second technical process module 402 are used for receiving and processing the working state information of the reactor, wherein the types of the working state information of the reactor received and processed by the first technical process module 401 and the second technical process module 402 are different.
In the first control system, the first technical processing module 401 and the second technical processing module 402 receive and process the working state information of the reactor, and judge whether the working state information of the reactor meets the pit water injection condition. If the working state information of the reactor does not meet the pit water injection condition, the first technical processing module 401 and the second technical processing module 402 output a determination signal to the NAND module 403; correspondingly, if the nand module 403 receives at least one determination signal from the first technical process module 401 or the second technical process module 402, a normally-off signal is output; if the working state information of the reactor meets the pit water injection condition, the first technical processing module 401 and the second technical processing module 402 output an uncertain signal to the NAND module 403; accordingly, if the signals received by the nand module 403 from the first technical process module 401 and the second technical process module 402 are both determination signals, a release normal-off signal is output.
For another example, please refer to fig. 5, which shows a schematic structural diagram of a second control system provided in an embodiment of the present application, where the second control system includes a plurality of technical processing modules, and optionally, a corresponding number of technical processing modules may be set according to the number of operating status information of the reactor.
The first technical processing module 501 and the second technical processing module 502 are used for receiving and processing the working state information of the reactor, wherein the working state information of the reactor received and processed by the first technical processing module 501 and the second technical processing module 502 are different.
In the second control system, the first technical processing module 501 and the second technical processing module 502 receive and process the working state information of the reactor, and judge whether the working state information of the reactor meets the pit water injection condition. If the working state information of the reactor does not meet the pit water injection condition, the first technical processing module 501 and the second technical processing module 502 output non-determination signals to the AND module 503; correspondingly, if the AND module 503 receives at least one non-deterministic signal from the first technical process module 501 or the second technical process module 502, a shutdown signal is output; if the working state information of the reactor meets the pit water injection condition, the first technical processing module 501 and the second technical processing module 502 output a determination signal to the AND module 503; correspondingly, if the signals received by the AND module 503 from the first technical processing module 501 or the second technical processing module 502 are both determination signals, an on signal is output.
In the embodiment of the application, the first control system and the second control system are specifically used for determining whether the water injection condition of the pit is met according to the working state information of the reactor; wherein, the working state information comprises a reactor core outlet temperature value and a loop pressure value; or the operating state information includes the core outlet temperature value, the primary circuit pressure value and the radioactive dose in the containment; or the working state information comprises a reactor core outlet temperature value, a loop pressure value and the hydrogen concentration in the containment; or the operating state information includes the core outlet temperature value, the one-circuit pressure value, the radioactive dose in the containment vessel, and the hydrogen concentration in the containment vessel.
In the embodiment of the application, the working state information comprises a reactor core outlet temperature value; the first control system and the second control system are used for acquiring a plurality of reactor core outlet temperature values and determining a next-largest value from the plurality of reactor core outlet temperature values; the first control system and the second control system are used for determining that the reactor core outlet temperature value meets the corresponding preset condition under the condition that the next maximum value is larger than the preset temperature threshold value.
Optionally, a plurality of temperature sensors are arranged at the outlet of the reactor core; the first control system and the second control system are used for acquiring the reactor core outlet temperature values measured by the temperature sensors, filtering the reactor core outlet temperature values, and determining a next-largest value from the reactor core outlet temperature values obtained after the filtering.
For example, please refer to fig. 6, which illustrates a schematic diagram of a core outlet temperature value obtaining process according to an embodiment of the present application; the system comprises a plurality of reactor core outlet temperature signals, a plurality of temperature sensors, a plurality of filters, a next-to-maximum value calculation module, a high-definite value trigger module and a temperature condition trigger module; correspondingly, each temperature sensor correspondingly acquires a reactor core outlet temperature value of a reactor core outlet temperature signal, and each filter correspondingly carries out filtering treatment on the reactor core outlet temperature value acquired by one temperature sensor; the number of core outlet temperature signals can be determined according to the core outlet temperature given by the nuclear power plant, and n core outlet temperature signals are used in an exemplary embodiment of the application.
In the process of obtaining the core outlet temperature value, each temperature sensor obtains a corresponding core outlet temperature value through a corresponding core outlet temperature signal, the core outlet temperature value obtained by each temperature sensor is subjected to effectiveness judgment of filtering treatment through a filter, and the effective core outlet temperature value after the filtering treatment is subjected to next-maximum value calculation in a next-maximum value calculation module 601, namely, a next-maximum value is selected from the core outlet temperature after the filtering treatment; if the next maximum value is greater than the preset temperature threshold, the high-value triggering module 602 is triggered, and then the temperature condition triggering module 603 is triggered, that is, it is determined that the core outlet temperature value meets the corresponding preset condition.
In the embodiment of the application, the reliability of judging whether the reactor core outlet temperature signal meets the preset condition can be ensured by adopting the secondary maximum value processing.
In the embodiment of the application, the working state information comprises a loop pressure value; the first control system and the second control system are used for acquiring a plurality of loop pressure values and detecting whether the loop pressure values are smaller than a preset pressure threshold value or not; the first control system and the second control system are used for determining that the loop pressure value meets the corresponding preset condition when the number of the target loop pressure values smaller than the preset pressure threshold value meets the first preset number condition.
Optionally, a plurality of pressure sensors are arranged in the loop; the first control system and the second control system are used for acquiring a loop pressure value measured by each pressure sensor.
For example, please refer to fig. 7, which illustrates a schematic diagram of a loop pressure value obtaining process according to an embodiment of the present application; the loop pressure value acquisition process comprises a plurality of loop pressure signals, a plurality of pressure sensors, a plurality of low-constant value triggering modules, a 2-out-of-2 module and a pressure condition triggering module; correspondingly, each pressure sensor correspondingly acquires a loop pressure value, and each low constant value triggering module correspondingly acquires a corresponding loop pressure value; illustratively, only two primary circuit pressure signals, namely primary circuit pressure signal one 701 and primary circuit pressure signal two 702, are utilized in embodiments of the present application, as well as two corresponding pressure sensors 703 and two low-set triggering modules 704.
In the process of acquiring the loop pressure value, the pressure sensor 703 acquires a corresponding loop pressure value through a loop pressure signal one 701 and a loop pressure signal two 702 given by the nuclear power plant and transmits the corresponding loop pressure value to the corresponding low constant value triggering module 704; the corresponding low constant triggering module 704 detects whether each loop pressure value is smaller than a preset pressure threshold, and if each loop pressure value is smaller than the preset pressure threshold, the 2-out-of-2 module 705 is satisfied, so that the pressure condition triggering module 706 is triggered, that is, it is determined that the loop pressure value satisfies the corresponding preset condition.
In the embodiment of the present application, optionally, the 2-out-of-2 module 705 may also adopt a 4-out-of-2 coincidence logic; in this embodiment, by adopting the 2-out-of-2 logic, reliability in determining whether the loop pressure signal satisfies the preset condition can be ensured.
In an embodiment of the application, the working state information includes a radiation dose within the containment vessel; the first control system and the second control system are used for acquiring a plurality of radioactive doses and detecting whether each radioactive dose is larger than a preset dose threshold value or not; the first control system and the second control system are used for determining that the radioactive dose meets the corresponding preset condition when the number of the radioactive doses larger than the preset dose threshold meets the second preset number condition.
Optionally, a plurality of radioactive dose detection devices are arranged inside the containment; the first control system and the second control system are used for acquiring the radioactive doses measured by the radioactive dose detection devices.
For example, please refer to fig. 8, which illustrates a schematic diagram of a radioactive dose acquisition process in a containment according to an embodiment of the present application, wherein the radioactive dose acquisition process in the containment includes a plurality of radioactive dose signals, a plurality of dose detection devices, a plurality of high-value triggering modules, a 2-out-of-2 module, and a dose condition triggering module; correspondingly, each dose detection device correspondingly acquires a radioactive dose, and each high-value triggering module corresponds to the corresponding radioactive dose acquired by each dose detection device; illustratively, only two radiation dose signals, namely, a first radiation dose signal 801 and a second radiation dose signal 802, are used in the present embodiment, and two dose detection devices 803 and two high-value triggering modules 804 are used.
In the process of acquiring the radioactive dose, the dose detection device 803 acquires the corresponding radioactive dose through a first radioactive dose signal 801 and a second radioactive dose signal 802 given by the nuclear power plant and transmits the corresponding radioactive dose to a corresponding high-fixed-value trigger module 804; the corresponding high-value triggering module 804 detects whether each of the radioactive doses is greater than a preset dose threshold, and if each of the radioactive doses is greater than the preset dose threshold, triggers the 2-out-of-2 module 805, thereby triggering the dose condition triggering module 806, i.e., determining that the radioactive dose satisfies the corresponding preset condition.
In the embodiment of the present application, optionally, the 2-out-of-2 module 805 may also adopt a 2-out-of-4 coincidence logic; in this embodiment, by adopting the 2-out-of-2 logic, reliability in determining whether the radiation dose satisfies the preset condition can be ensured.
In the embodiment of the application, the working state information comprises the hydrogen concentration in the containment; the first control system and the second control system are used for acquiring a plurality of hydrogen concentrations and detecting whether each hydrogen concentration is larger than a preset concentration threshold value or not; the first control system and the second control system are used for determining that the hydrogen concentration meets the corresponding preset conditions when the quantity of the hydrogen concentration larger than the preset concentration threshold meets the third preset quantity condition.
Optionally, a plurality of hydrogen concentration detection devices are arranged inside the containment; the first control system and the second control system are used for acquiring the hydrogen concentration measured by each hydrogen concentration detection device.
For example, please refer to fig. 9, which illustrates a schematic diagram of a hydrogen concentration obtaining process in a containment provided by an embodiment of the present application, where the hydrogen concentration obtaining process in the containment includes a plurality of hydrogen concentration signals, a plurality of concentration detection devices, a plurality of high-value triggering modules, a 2-taking-2 module, and a concentration condition triggering module; correspondingly, each concentration detection device correspondingly acquires a hydrogen concentration, and each high constant value triggering module corresponds to the corresponding hydrogen concentration acquired by each concentration detection device; for example, in the embodiment of the present application, only two hydrogen concentration signals, namely, a first hydrogen concentration signal 901 and a second hydrogen concentration signal 902, and two corresponding concentration detection devices 903 and two high-constant triggering modules 904 are used.
In the hydrogen concentration acquisition process, the concentration detection device 903 acquires the corresponding hydrogen concentration through a first hydrogen concentration signal 901 and a second hydrogen concentration signal 902 given by the nuclear power plant and transmits the corresponding hydrogen concentration to a corresponding high constant value triggering module 904; the corresponding high-constant triggering module 904 detects whether each hydrogen concentration is greater than a preset concentration threshold, and if each hydrogen concentration is greater than the preset concentration threshold, triggers the 2-out-of-2 module 905, thereby triggering the concentration condition triggering module 906, i.e. determining that the hydrogen concentration meets the corresponding preset condition.
In the embodiment of the present application, optionally, the 2-out-of-2 module 905 may also adopt a 2-out-of-4 coincidence logic; in this embodiment, by adopting the 2-out-of-2 logic, reliability in determining whether the hydrogen concentration satisfies the preset condition can be ensured.
In the embodiment of the application, the water injection control system for the reactor pit comprises at least two first control systems, and a larger number of first control systems can be arranged to process the reactor working state information acquired by the signal acquisition card more accurately so as to improve the accuracy of signal processing, and the larger number of first control systems and the second control systems are controlled in a multi-platform combined manner so as to ensure the reliability of equipment control.
In the embodiment of the application, the software programs installed in each first control system and the software programs installed in the second control system are different; the control platform of the first control system is different from the control platform of the second control system; alternatively, when two or more first control systems are used, the first control systems may use different control platforms and install different software programs; by installing different software programs in the first control system and the second control system, when one of the software has burst problems, the corresponding control system cannot work normally, the other control system with different software is not affected to work normally, and the reliability of the pit water injection control system is ensured.
In the embodiment of the application, the first control system can be a Reactor Protection System (RPS) and a diversity driving system (KDS), and the second control system is a serious accident instrumentation and control system (KDA); the Reactor Protection System (RPS), the diversity drive system (KDS) and the severe accident instrumentation system (KDA) are three instrumentation systems using different technologies.
In the embodiment of the application, at least two executing mechanisms are arranged on the water injection pipeline of the pile pit; the pit water injection control system is used for controlling each executing mechanism; by arranging at least more than two execution mechanisms, more guarantees are provided for the step of pit water injection, and the reliability and accuracy of the whole pit water injection control system are improved.
In the embodiment of the application, the pit water injection control system further comprises a plurality of signal acquisition cards, wherein the plurality of signal acquisition cards are used for acquiring working state information; the first control system and the second control system are used for acquiring working state information from various signal acquisition cards.
For example, please refer to fig. 10, which illustrates a schematic diagram of a signal acquisition system according to an embodiment of the present application; in the signal acquisition system, the working state information of the reactor is transmitted to a first control system and a second control system through various signal acquisition cards; the diversity signal acquisition card can be a plurality of different types of signal acquisition cards; correspondingly, when two or more signal acquisition cards with diversity are used, the types of the used signal acquisition cards are different, so that the acquisition of signals is easy to realize, and the reliability requirement of a system is ensured; alternatively, a corresponding number of signal acquisition cards may be set according to the number of operating state information of the reactor.
In the embodiment of the application, the pit water injection control system further comprises a plurality of equipment driving cards, wherein the plurality of equipment driving cards are connected with the executing mechanism, and the plurality of equipment driving cards are used for driving the executing mechanism to be started under the condition that the starting signal is received and the normal closing signal is not received.
For example, please refer to fig. 11, which illustrates a schematic diagram of a device driving system according to an embodiment of the present application; the first control system acquires the working state information and judges whether the working state information meets the corresponding preset conditions, and if the acquired working state information does not meet the corresponding preset conditions, the first control system sends normally-off signals to the device driver cards of the diversity; the plurality of device driver cards may be a plurality of different types of device driver cards; if the collected working state information meets the corresponding preset conditions, the first control system sends a normal-closing releasing signal to the device driving cards with diversity; the second control system collects the working state information and judges whether the working state information meets the corresponding preset conditions, if the collected working state information does not meet the corresponding preset conditions, the second control system sends closing signals to the diversified device driver cards, and if the collected working state information meets the corresponding preset conditions, the second control system sends opening signals to the diversified device driver cards; the device driver card drives the executing mechanism to be started under the condition that the device driver card receives a normal-closing releasing signal and a starting signal.
In the embodiment of the present application, as shown in fig. 12, a schematic diagram of an automatic control structure provided in the embodiment of the present application is shown; the automatic control system comprises two diversity signal acquisition cards, namely a diversity signal acquisition card 1 and a diversity signal acquisition card 2, wherein the types of the two signal acquisition cards are different; the system also comprises two first control systems and a second control system, wherein one first control system is a Reactor Protection System (RPS), the other first control system is a diversity drive system (KDS), the second control system is a serious accident instrument control system (KDA), and the technical processes of the RPS, the KDS and the KDA all adopt different control platforms and install different software programs; the device also comprises two diversity device driving cards, namely a diversity device driving card 1 and a diversity device driving card 2, wherein the types of the two device driving cards are different; the diversity equipment driving card 1 is connected with the executing mechanism 1 and used for driving the executing mechanism 1 to be opened when the condition is met, and the diversity equipment driving card 2 is connected with the executing mechanism 2 and used for driving the executing mechanism 2 to be opened when the condition is met.
The diversity signal acquisition card 1 acquires a reactor core outlet temperature signal and transmits the acquired reactor core outlet temperature signal to the RPS, the KDS and the KDA; the diversity signal acquisition card 2 acquires a loop pressure signal and transmits the acquired loop pressure signal to the RPS, the KDS and the KDA.
The RPS judges whether the received reactor core outlet temperature signal meets the corresponding preset temperature condition through the technical processing 1 module, and transmits the processed result to the NAND module, and the RPS judges whether the received loop pressure signal meets the corresponding preset pressure condition through the technical processing 2 module, and transmits the processed result to the NAND module; if at least one of the reactor core outlet temperature signal and the loop pressure signal does not meet the corresponding preset condition, outputting a normal-related signal to the diversity equipment driving card 1 and the diversity equipment driving card 2 by the NAND module; if the reactor core outlet temperature signal and the loop pressure signal meet the corresponding preset conditions, the NAND module outputs a normal-off release signal to the diversity equipment driving card 1 and the diversity equipment driving card 2.
The KDS judges whether the received reactor core outlet temperature signal meets the corresponding preset temperature condition through the technical processing 1 module, and transmits the processed result to the NAND module, and judges whether the received loop pressure signal meets the corresponding preset pressure condition through the technical processing 2 module, and transmits the processed result to the NAND module; if at least one of the reactor core outlet temperature signal and the loop pressure signal does not meet the corresponding preset condition, outputting a normal-related signal to the diversity equipment driving card 1 and the diversity equipment driving card 2 by the NAND module; if the reactor core outlet temperature signal and the loop pressure signal meet the corresponding preset conditions, the NAND module outputs a normal-off release signal to the diversity equipment driving card 1 and the diversity equipment driving card 2.
The KDA judges whether the received reactor core outlet temperature signal meets the corresponding preset temperature condition through the technical processing 1 module, and transmits the processed result to the AND module, and judges whether the received loop pressure signal meets the corresponding preset pressure condition through the technical processing 2 module, and transmits the processed result to the AND module; if at least one of the reactor core outlet temperature signal and the loop pressure signal does not meet the corresponding preset condition, outputting a closing signal to the diversity equipment driving card 1 and the diversity equipment driving card 2 by the AND module; if the reactor core outlet temperature signal and the loop pressure signal meet the corresponding preset conditions, the AND module outputs an opening signal to the diversity equipment driving card 1 and the diversity equipment driving card 2.
The method comprises the steps that when signals from the RPS and the KDS are received as normal off releasing signals and signals from the KDA are received as on signals, the actuating mechanism 1 is driven to be started by the diversified equipment driving card 1, and otherwise, the actuating mechanism 1 is not driven to be started; the diversity device driver card 2 drives the executing mechanism 2 to be started when the signals from the RPS and the KDS are both normal off releasing signals and the signal from the KDA is a starting signal, otherwise, does not drive the executing mechanism 2 to be started.
Correspondingly, each diversified device driving card correspondingly drives an executing mechanism; correspondingly, when two or more device driving cards with diversity are used, the types of the used device driving cards are different, so that the driving of the devices is easy to realize, and the reliability requirement of a system is ensured; alternatively, the number of device driver cards of the diversity may be set correspondingly according to the number of actuators.
The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The foregoing examples illustrate only a few embodiments of the application, which are described in detail and are not to be construed as limiting the scope of the application. It should be noted that it will be apparent to those skilled in the art that several variations and modifications can be made without departing from the spirit of the application, which are all within the scope of the application. Accordingly, the scope of protection of the present application is to be determined by the appended claims.
Claims (18)
1. The pit water injection control system is characterized by being used for controlling an executing mechanism arranged on a pit water injection pipeline and comprises a first control system and a second control system;
the first control system is used for outputting a normally-off signal to the executing mechanism when the pit water injection condition is not met, and stopping outputting the normally-off signal to the executing mechanism when the pit water injection condition is met;
the second control system is used for outputting an opening signal to the executing mechanism under the condition that the pit water injection condition is met; the actuating mechanism is used for being started under the condition that the starting signal is received and the normally-closed signal is not received.
2. The pit water injection control system of claim 1, wherein the second control system is further connected to a pit water level test module, the pit water level test module configured to send a shutdown signal to the second control system if the pit water level reaches a preset water level value; and after receiving the closing signal sent by the pit water level testing module, the second control system stops outputting an opening signal to the executing mechanism.
3. The pit water injection control system of claim 1, wherein the first control system and the second control system are configured to determine whether the pit water injection condition is satisfied according to operational state information of a reactor;
wherein, the working state information comprises a reactor core outlet temperature value and a loop pressure value;
or the operating state information includes the core outlet temperature value, the primary circuit pressure value, and the radiation dose within the containment vessel;
or the operating state information comprises the reactor core outlet temperature value, the primary circuit pressure value and the hydrogen concentration in the containment;
or the operating condition information includes the core outlet temperature value, the primary circuit pressure value, the radioactive dose within the containment vessel, and the hydrogen concentration within the containment vessel.
4. The pit water injection control system of claim 3, further comprising a diversity of signal acquisition cards for acquiring the operational status information; the first control system and the second control system are used for acquiring the working state information from the signal acquisition cards with the diversity.
5. A pit water injection control system according to claim 3, wherein the operating status information includes a plurality of information types;
the first control system and the second control system are used for determining that the pit water injection condition is met when the working state information of various information types meets the corresponding preset conditions.
6. The pit water injection control system of claim 5, wherein the operational status information comprises the core outlet temperature value;
the first control system and the second control system are used for acquiring a plurality of reactor core outlet temperature values and determining a next-largest value from the reactor core outlet temperature values;
the first control system and the second control system are used for determining that the reactor core outlet temperature value meets the corresponding preset condition under the condition that the next largest value is larger than a preset temperature threshold value.
7. The pit water injection control system of claim 6, wherein a plurality of temperature sensors are disposed at the core outlet;
the first control system and the second control system are used for acquiring the reactor core outlet temperature value measured by each temperature sensor.
8. The pit water injection control system of claim 6, wherein the first control system and the second control system are configured to filter a plurality of the core outlet temperature values and determine the next largest value from the plurality of core outlet temperature values obtained after the filtering.
9. The pit fill control system of claim 5, wherein said operating status information comprises a loop pressure value;
the first control system and the second control system are used for acquiring a plurality of loop pressure values and detecting whether each loop pressure value is smaller than a preset pressure threshold value or not;
the first control system and the second control system are configured to determine that the first loop pressure value meets the corresponding preset condition when the number of the first loop pressure values smaller than the preset pressure threshold meets a first preset number condition.
10. The pit water injection control system of claim 9, wherein a plurality of pressure sensors are provided in a circuit;
the first control system and the second control system are used for acquiring the loop pressure value measured by each pressure sensor.
11. The pit water injection control system of claim 5, wherein the operational status information includes a radiation dose within the containment;
the first control system and the second control system are used for acquiring a plurality of radioactive doses and detecting whether each radioactive dose is larger than a preset dose threshold value or not;
the first control system and the second control system are configured to determine that the radiation dose satisfies the corresponding preset condition when the number of the radiation doses greater than the preset dose threshold satisfies a second preset number condition.
12. The pit waterflooding control system of claim 11, wherein a plurality of radiation dose detection devices are disposed within the containment vessel;
the first control system and the second control system are used for acquiring the radioactive doses measured by the radioactive dose detection devices.
13. The pit water injection control system of claim 5, wherein the operating status information includes a hydrogen concentration within the containment;
the first control system and the second control system are used for acquiring a plurality of hydrogen concentrations and detecting whether each hydrogen concentration is larger than a preset concentration threshold value or not;
The first control system and the second control system are configured to determine that the hydrogen concentration satisfies the corresponding preset condition when the number of the hydrogen concentrations greater than the preset concentration threshold satisfies a third preset number condition.
14. The pit water injection control system of claim 13, wherein a plurality of hydrogen concentration detection devices are provided inside the containment vessel;
the first control system and the second control system are used for acquiring the hydrogen concentration measured by each hydrogen concentration detection device.
15. The pit water injection control system of any one of claims 1 to 14, wherein the pit water injection control system comprises at least two of the first control systems.
16. The pit water injection control system of claim 15, wherein the software program installed in each of the first control systems and the software program installed in the second control system are different.
17. The pit water injection control system of any one of claims 1 to 14, wherein at least two actuators are provided on the pit water injection pipe;
and the pit water injection control system is used for controlling each executing mechanism.
18. The pit water injection control system of any one of claims 1 to 14, further comprising a plurality of device driver cards connected to the actuator, the plurality of device driver cards configured to actuate the actuator when the on signal is received and the normally off signal is not received.
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| SU525371A1 (en) * | 1975-01-03 | 1983-05-15 | Предприятие П/Я В-2502 | Device for protecting against exceeding nuclear reactor period |
| JPH07270593A (en) * | 1994-03-30 | 1995-10-20 | Toshiba Corp | Automatic output controller for reactor |
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