CN113972014A - Pile pit water injection control system - Google Patents
Pile pit water injection control system Download PDFInfo
- Publication number
- CN113972014A CN113972014A CN202111205266.6A CN202111205266A CN113972014A CN 113972014 A CN113972014 A CN 113972014A CN 202111205266 A CN202111205266 A CN 202111205266A CN 113972014 A CN113972014 A CN 113972014A
- Authority
- CN
- China
- Prior art keywords
- control system
- condition
- water injection
- pit water
- signal
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Images
Classifications
-
- 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
-
- 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
- Y02E30/30—Nuclear fission reactors
Abstract
The application relates to a pile pit water injection control system. The pile pit water injection control system is used for controlling an actuating mechanism arranged on a pile 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 under the condition that the pit water filling condition is not met, and stopping outputting the normally-off signal to the execution mechanism under the condition that the pit water filling condition is met; the second control system is used for outputting a starting signal to the actuating mechanism under the condition that the water filling condition of the pile pit is met; the execution mechanism is started under the condition that the opening signal is received and the normally-off signal is not received. The invention adopts automatic control, breaks away from the requirement of manual operation, and realizes automatic control of pit filling water, thereby effectively reducing the operation time of the actuating mechanism and the load of operators.
Description
Technical Field
The application relates to the technical field of automatic control, in particular to a pile pit water injection control system.
Background
In the design of a pressurized water reactor nuclear power station, in order to limit the radioactive consequences of a serious accident and minimize the discharge amount of radioactive substances to the environment, serious accident suppression measures are provided, wherein one of the measures is melt retention, namely, high-radioactivity melt is retained in a pressure container when the serious accident occurs by ensuring the integrity of the pressure container, and the used method is water injection in a reactor pit; and the pressure vessel is in a high pressure state, and the misinjection can bring thermal shock, which can cause the pressure vessel to be rapidly disassembled, but high risk is generated. Therefore, it is necessary to prevent the pit from being erroneously filled with water.
In the traditional technology, manual control is adopted to complete pit water injection, and the isolation valve is electrically isolated to achieve the purpose of preventing water injection by mistake. The specific mode is that after the temperature of the reactor core outlet reaches the specified temperature, an operator takes an electric isolation ticket to reach an electric appliance room to execute electric isolation removing work and informs a master control room that the electric isolation is removed, and then the master control room operator manually executes an operation button for opening an isolation valve after confirming the water filling condition of the reactor pit, so that the water filling operation of the reactor pit is completed.
However, at present, aiming at preventing water injection error of the pile pit, the water injection of the pile pit is completed by adopting a manual control method, because of manual operation, much time is consumed for opening the isolation valve after original electrical isolation is removed, the environment after a serious accident is complicated, the load of related operators is large, the requirement of manual control on the operators is high, and the load of the operators is large.
Disclosure of Invention
In view of the above, it is necessary to provide a high-reliability automatic control system for pit filling.
A pile pit water injection control system is used for controlling an execution mechanism arranged on a pile 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 actuating mechanism under the condition that the pit water filling condition is not met, and stopping outputting the normally-off signal to the actuating mechanism under the condition that the pit water filling condition is met; the second control system is used for outputting a starting signal to the actuating mechanism under the condition that the water filling condition of the pile pit is met; the actuating mechanism is used for being opened under the condition that the opening signal is received and the normally-closed signal is not received.
In one embodiment, the second control system is further 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 when the pit water level reaches a preset water level value; and the second control system stops outputting the opening signal to the actuating mechanism after receiving the closing signal sent by the pile pit water level testing module.
In one embodiment, the first control system and the second control system are specifically configured to:
determining whether the reactor pit water injection condition is met or not according to the working state information of the reactor; the working state information comprises a reactor core outlet temperature value and a primary circuit pressure value; or the working state information comprises 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 primary circuit pressure value and the hydrogen concentration in the containment vessel;
or the working state information comprises the core outlet temperature value, the primary circuit pressure value, the radioactive dose in the containment and the hydrogen concentration in the containment.
In one embodiment, the pile pit water injection control system further comprises:
the signal acquisition card of the diversity, the signal acquisition card of the diversity is used for gathering the working condition information; the first control system and the second control system are used for acquiring the working state information from the diversified signal acquisition cards.
In one embodiment, the operating state information includes a plurality of information types; and the first control system and the second control system are used for determining that the filling water condition of the pile pit is met when the working state information of various information types meets the corresponding preset condition.
In one embodiment, the operating condition information includes a core exit 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 secondary maximum 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 secondary maximum value is larger than the preset temperature threshold value.
In one embodiment, a plurality of temperature sensors are arranged at the outlet of the reactor core; and 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 carrying out filtering processing on the plurality of reactor core outlet temperature values, and determining a second largest value from the plurality of reactor core outlet temperature values obtained after filtering processing.
In one embodiment, the operating condition information includes 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; 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 a first preset number condition.
In one embodiment, a plurality of pressure sensors are disposed in a circuit; and 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 operating state information includes a radioactive dose in the containment; the system comprises a first control system and a second control system, wherein 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; 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 a second preset number condition.
In one embodiment, a plurality of radioactive dose detection devices are arranged inside the containment; and the first control system and the second control system are used for acquiring the radioactive dose measured by each radioactive dose detection device.
In one embodiment, the operating condition information includes hydrogen concentration in 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 greater than a preset concentration threshold value; the first control system and the second control system are used for determining that the hydrogen concentration meets the corresponding preset condition when the number of the hydrogen concentrations larger than the preset concentration threshold value meets a third preset number condition.
In one embodiment, a plurality of hydrogen concentration detection devices are arranged inside the containment; and the first control system and the second control system are used for acquiring the hydrogen concentration detected by each hydrogen concentration detection device.
In one embodiment, the pit water injection control system comprises 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 actuating mechanisms are arranged on the pile pit water injection pipeline; and the pile pit water injection control system is used for controlling each actuating mechanism.
In one embodiment, the pit filling control system further comprises a diversified device driver card, the diversified device driver card is connected with the actuator, and the diversified device driver card is used for driving the actuator to open when the opening signal is received and the normally-off signal is not received.
According to the pile pit water injection control system, the first control system and the second control system are used for controlling the executing mechanism on the pile pit water injection pipeline, the requirement of manual operation is eliminated, and automatic control of pile pit water injection is realized, so that the operating 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 closing lock of the execution mechanism under the condition that the water filling condition of the pile pit is not met, and sends a releasing command to the closing lock of the valve under the condition that the water filling condition of the pile pit is met, so that high reliability of preventing mistaken water filling of the pile pit is achieved.
Drawings
Fig. 1 is a schematic structural diagram of a manually-controlled pit water injection system according to an embodiment of the present disclosure;
fig. 2 is a schematic structural diagram of a pit filling water control system according to an embodiment of the present disclosure;
fig. 3 is a schematic connection diagram of a heap 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 provided in the embodiment of the present application;
FIG. 6 is a schematic diagram of a core outlet temperature value obtaining process provided by 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 disclosure;
fig. 8 is a schematic diagram of an in-containment radioactive dose harvesting process provided by an embodiment of the present application;
FIG. 9 is a schematic diagram of an in-containment hydrogen concentration acquisition process provided by an embodiment of the present application;
FIG. 10 is a schematic diagram of a signal acquisition system provided in an embodiment of the present application;
FIG. 11 is a schematic diagram of a device driving system provided in an embodiment of the present application;
fig. 12 is a schematic view of an automatic control structure according to an embodiment of the present application.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the present application and are not intended to limit the present application.
In the design of a pressurized water reactor nuclear power station, In order to limit the radioactive consequences of a serious accident and minimize the discharge of radioactive substances to the environment, serious accident suppression measures are provided, wherein one measure is melt Retention (In-Vessel Retention), namely, high-radioactivity melt In the serious accident is retained In a pressure Vessel by ensuring the integrity of the pressure Vessel, and a corresponding measure is pit water injection.
Under the severe accident condition, in order to ensure the integrity of the pressure vessel, when the outlet temperature of the reactor core reaches a certain temperature value and the pressure value of a primary circuit is lower than a certain pressure value, the water injection function of the reactor pit is started, water is injected into the reactor pit, the inside of the containment is cooled, the decay heat of the molten material of the reactor core is taken away, the pressure vessel is prevented from being melted through, and therefore the radioactive material is retained in the pressure vessel.
The pressure vessel is subjected to thermal shock due to mis-injection in a high-pressure state, which may cause the pressure vessel to be rapidly disassembled, and high risk is generated. Therefore, it is necessary to prevent the fill-up of the pit from being mistakenly performed, and the fill-up of the pit needs to be completed within a limited time during the fill-up, so that the reliability of the fill-up control of the pit is extremely high.
In the related art, the isolation valve is electrically isolated by manual control, so that water is prevented from being injected by mistake, and an operator needs to complete manual water injection within a limited time under a serious accident. 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 includes a main control room and an electrical equipment room, a first manual control button 101 and a second manual control button 102 are arranged in the main control room, an electrical distribution board is arranged in the electrical equipment room, and a first electrical isolation switch 103, a second electrical isolation switch 104, a first isolation valve 105 and a second isolation valve 106 are arranged on the electrical distribution board; the first manual control button 101 is connected with the first electrical isolating switch 103 for controlling the first isolating valve 105, and the second manual control button 102 is connected with the second electrical isolating switch 104 for controlling the second isolating valve 106. When the temperature of the reactor core outlet reaches a specified temperature, a field operator takes an electric isolation work ticket for releasing the electric isolation to the isolation, then reaches the position of an electric equipment room, identifies a valve power supply loop drawer in the electric switch disc, releases the drawer locking by a key, pushes the drawer to a closed position, rotates a knob to a power-on position, closes a first electric isolation switch 103 and a second electric isolation switch 104, and then informs a master control room that the field electric isolation is released; and after receiving the message that the field electrical isolation is released and confirming the water filling condition of the reactor cavity, an operator in 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 water filling operation of the reactor pit is completed.
However, in practice, it is found that since the electrical distribution board and the control equipment of the main control room are located on different floors and rooms and are far away from each other, it takes much time to manually control the isolation valve to open after the original electrical isolation is removed, and the isolation valve is opened in a serious accident, and the environment after the serious accident is complex, the load of an operator is large, and the requirement on the operator is high. In view of this, the embodiment of the application provides a pit filling water control system, owing to cancelled electrical isolation, can effectively reduce valve operating time, adopts automatic control, reduces operator's load, improves nuclear power plant's safety level.
Referring to fig. 2, a schematic structural diagram of a pile pit water injection control system provided in an embodiment of the present application is shown, the pile pit water injection control system is used for controlling an actuator 201 disposed on a pile pit water injection pipeline 202, and the pile pit water injection control system includes a first control system and a second control system.
And the first control system is used for outputting a normally-off signal to the actuator 201 when the pit water filling condition is not met, and stopping outputting the normally-off signal to the actuator 201 when the pit water filling condition is met.
The first control system outputs a normally-closed signal to the execution mechanism under the condition that the pit water injection condition is not met, so that when the pit water injection control system does not meet the pit water injection condition and the execution mechanism cannot be started, the first control system plays a role in locking the execution mechanism, and when the pit water injection condition is met and the execution mechanism can be started, the first control system stops outputting the normally-closed signal, namely, the execution mechanism is unlocked.
The second control system is used for outputting a starting signal to the execution mechanism 201 under the condition that the pit water injection condition is met; the actuator 201 is configured to be turned on when receiving the turn-on signal and not receiving the normally-off signal.
The second control system sends an opening signal to the actuating mechanism when the conditions are met, namely the second control system is used for driving the actuating mechanism to open, and the second control system is different from the first control system in achieving the effect of locking the actuating mechanism.
An actuator 201, which may be a pump or a valve, etc.; can be in two kinds of states of opening or closing, the water pressure equipment that uses the large scale extensively in the nuclear power station, actuating mechanism are the key annex of nuclear power station safe operation, in this application embodiment, actuating mechanism 201 sets up on the water injection pipeline, opens when actuating mechanism 201, and pit water injection pipeline 202 can be to the pit water injection, and when actuating mechanism 201 closed, pit water injection pipeline 202 can't be to the pit water injection.
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 advantage is achieved, the starting time of equipment is shortened, and the load of an operator is effectively reduced; under the condition that the water filling condition of the pit is not met, a first control system in the pit water filling control system outputs a normally-off signal to the execution mechanism 201, under the condition that the first control system meets the pit water filling condition, the normally-off signal is stopped being output to the execution mechanism 201, and under the condition that a second control system meets the pit water filling condition, when 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 the dual combination of the first control system and the second control system, the possibility of preventing the pit from mistakenly filling water is effectively improved, and the high reliability of the pit water filling control system is ensured.
In the embodiment of the application, the second control system is further 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 when the pit water level reaches a preset water level value; and the second control system stops outputting the opening signal to the actuating mechanism after receiving the closing signal sent by the pile pit water level testing module.
For example, please refer to fig. 3, which shows a schematic connection diagram of a pit water level testing module provided in an embodiment of the present application, wherein the pit water level testing module is connected to a second control system for determining whether a water level of a pit reaches a preset water level value; when the water level of the pile pit meets the preset water level value condition, the pile pit water level testing module sends a closing signal to the second control system, and when 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 water injection operation of the pile pit is stopped.
In an optional embodiment of the present application, the first control system and the second control system are configured to determine whether a pit water filling condition is met according to the operating state information of the reactor; the working state information comprises a plurality of information types; and the first control system and the second control system are used for determining that the filling water condition of the pile pit is met when the working state information of various information types meets the corresponding preset condition.
For example, please refer to fig. 4, which shows a schematic structural diagram of a first control system provided in 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 the operating state information of the reactor, for example, in this embodiment of the present application, only two technical processing modules are used, that is, a technical processing first module 401 and a technical processing second module 402, and the first control system further includes a nand module 403.
The technical process one module 401 and the technical process two module 402 are both used for receiving and processing the operating state information of the reactor, wherein the types of the operating state information of the reactor received and processed by the technical process one module 401 and the technical process two 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 operating state information of the reactor, and judge whether the operating 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, a first technical processing module 401 and a second technical processing module 402 output a determination signal to a 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, a technical processing first module 401 and a technical processing second module 402 output a non-determination signal to a non-module 403; accordingly, if the nand module 403 receives the determination signals from both the first technical processing module 401 and the second technical processing module 402, it outputs a normally-off release signal.
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 process modules, and optionally, a corresponding number of technical process modules may be set according to the number of the operating state information of the reactor, for example, in the embodiment of the present application, only two technical process modules are adopted, that is, a technical process first module 501 and a technical process second module 502, and the first control system further includes a corresponding module 503.
The first technical processing module 501 and the second technical processing module 502 are both used for receiving and processing the operating state information of the reactor, wherein the operating 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 water filling condition of the pile pit. If the working state information of the reactor does not meet the pit water injection condition, a technical processing first module 501 and a technical processing second module 502 output a non-determination signal to an AND module 503; correspondingly, if the module 503 receives at least one non-determination signal from the first technical processing module 501 or the second technical processing module 502, a closing signal is output; if the working state information of the reactor meets the pit water injection condition, a technical processing first module 501 and a technical processing second module 502 output a determination signal to an AND module 503; correspondingly, if the signals received by the module 503 from the module 501 for first technical process or the module 502 for second technical process are both determination signals, the 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 pit water injection condition is met according to the working state information of the reactor; the working state information comprises a reactor core outlet temperature value and a primary circuit pressure value; or the working state information comprises 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 primary circuit pressure value and the hydrogen concentration in the containment vessel; or the working state information comprises the core outlet temperature value, the primary circuit pressure value, the radioactive dose in the containment and the hydrogen concentration in the containment.
In the embodiment of the application, the working state information comprises 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 secondary maximum 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 secondary 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; and 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 plurality of reactor core outlet temperature values and determining the second largest value from the plurality of reactor core outlet temperature values obtained after filtering.
For example, please refer to fig. 6, which shows a schematic diagram of a core outlet temperature value obtaining process provided by an embodiment of the present application; the reactor core temperature control system comprises a plurality of reactor core outlet temperature signals, a plurality of temperature sensors, a plurality of filters, a secondary maximum value calculation module, a high fixed value triggering module and a temperature condition triggering module; correspondingly, each temperature sensor correspondingly acquires the reactor core outlet temperature value of one reactor core outlet temperature signal, and each filter correspondingly filters the reactor core outlet temperature value acquired by one temperature sensor; the number of core outlet temperature signals may be determined according to the core outlet temperature given by the nuclear power plant, and in the embodiment of the present application, n core outlet temperature signals are used exemplarily.
In the process of obtaining the reactor core outlet temperature value, each temperature sensor obtains the corresponding reactor core outlet temperature value through the corresponding reactor core outlet temperature signal, the reactor core outlet temperature value obtained by each temperature sensor is subjected to effectiveness judgment of filtering processing through a filter, and the effective reactor core outlet temperature value after filtering processing is subjected to secondary maximum value calculation in the secondary maximum value calculation module 601, namely, the secondary maximum value is selected from the reactor core outlet temperatures after filtering processing; if the next maximum value is greater than the preset temperature threshold, the high fixed value triggering module 602 is triggered, and the temperature condition triggering module 603 is further triggered, that is, it is determined that the reactor core outlet temperature value meets the corresponding preset condition.
In the embodiment of the application, reliability of judging whether the reactor core outlet temperature signal meets the preset condition or not can be ensured by adopting secondary large 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 each loop pressure value is smaller than a preset pressure threshold value; 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 a first preset number condition.
Optionally, a plurality of pressure sensors are arranged in the loop; and 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 disclosure; the loop pressure value obtaining process comprises a plurality of loop pressure signals, a plurality of pressure sensors, a plurality of low constant value trigger modules, a 2-out-of-2 module and a pressure condition trigger module; correspondingly, each pressure sensor correspondingly acquires a loop pressure value, and each low-fixed-value trigger module corresponds to the corresponding loop pressure value acquired by each pressure sensor; illustratively, only two primary pressure signals, i.e., primary pressure signal one 701 and primary pressure signal two 702, are utilized in the present embodiment, along with two corresponding pressure sensors 703 and two low-constant trigger modules 704.
In the process of acquiring a loop pressure value, the pressure sensor 703 acquires a corresponding loop pressure value through a loop pressure signal i 701 and a loop pressure signal ii 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 value triggering module 704 detects whether the pressure value of each loop is smaller than the preset pressure threshold, and if the pressure value of each loop is smaller than the preset pressure threshold, the 2-out-of-2 module 705 is satisfied, so as to trigger the pressure condition triggering module 706, that is, it is determined that the pressure value of the loop satisfies the corresponding preset condition.
In this embodiment of the present application, optionally, the module 705 of 2 out of 2 may also adopt a logic that 2 out of 4 conforms to; in this embodiment, the reliability of determining whether the loop pressure signal satisfies the preset condition can be ensured by adopting the 2-out-of-2 logic.
In an embodiment of the application, the operating state information includes a radioactive dose in the containment; the system comprises a first control system and a second control system, wherein 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; 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 a second preset number condition.
Optionally, a plurality of radioactive dose detection devices are arranged inside the containment; and the first control system and the second control system are used for acquiring the radioactive dose measured by each radioactive dose detection device.
For example, please refer to fig. 8, which shows a schematic diagram of an in-containment radioactive dose acquisition process provided by an embodiment of the present application, the in-containment radioactive dose acquisition process includes a plurality of radioactive dose signals, a plurality of dose detection devices, a plurality of high-definite-value trigger modules, a 2-out-of-2 module, and a dose condition trigger module; correspondingly, each dose detection device correspondingly acquires a radioactive dose, and each high-fixed-value trigger module corresponds to the corresponding radioactive dose acquired by each dose detection device; illustratively, only two radioactive dose signals, namely a radioactive dose signal one 801 and a radioactive dose signal two 802, and correspondingly two dose detection devices 803 and two high-fixed-value trigger modules 804 are employed in the present embodiment.
In the radioactive dose obtaining process, the dose detection device 803 obtains corresponding radioactive doses through a first radioactive dose signal 801 and a second radioactive dose signal 802 given by a nuclear power plant, and transmits the corresponding radioactive doses to corresponding high-fixed-value trigger modules 804; the corresponding high-fixed-value triggering module 804 detects whether each radioactive dose is greater than a preset dose threshold, and if each radioactive dose is greater than the preset dose threshold, the 2-out-of-2 module 805 is triggered, so as to trigger the dose condition triggering module 806, that is, it is determined that the radioactive dose satisfies the corresponding preset condition.
In this embodiment of the application, optionally, the 2-out-of-2 module 805 may also adopt a 4-out-of-2 coincidence logic; in this embodiment, by adopting the 2-out-of-2 logic, the reliability of determining whether the radioactive dose satisfies the preset condition can be ensured.
In the embodiment of the application, the working state information comprises the concentration of hydrogen 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 greater than a preset concentration threshold value; the first control system and the second control system are used for determining that the hydrogen concentration meets the corresponding preset condition when the number of the hydrogen concentrations larger than the preset concentration threshold value meets a third preset number condition.
Optionally, a plurality of hydrogen concentration detection devices are arranged inside the containment; and the first control system and the second control system are used for acquiring the hydrogen concentration detected by each hydrogen concentration detection device.
For example, please refer to fig. 9, which shows a schematic diagram of an in-containment hydrogen concentration obtaining process provided in an embodiment of the present application, where the in-containment hydrogen concentration obtaining process includes a plurality of hydrogen concentration signals, a plurality of concentration detection devices, a plurality of high-fixed-value trigger modules, a 2-out-of-2 module, and a concentration condition trigger module; correspondingly, each concentration detection device correspondingly obtains one hydrogen concentration, and each high-fixed-value trigger module corresponds to the corresponding hydrogen concentration obtained by each concentration detection device; illustratively, only two hydrogen concentration signals, namely a hydrogen concentration signal one 901 and a hydrogen concentration signal two 902, are used in the embodiment of the present application, and two corresponding concentration detection devices 903 and two high constant value trigger modules 904 are used.
In the hydrogen concentration obtaining process, the concentration detection device 903 obtains corresponding hydrogen concentration through a first hydrogen concentration signal 901 and a second hydrogen concentration signal 902 given by a nuclear power plant and transmits the corresponding hydrogen concentration to a corresponding high-fixed-value trigger module 904; the corresponding high-fixed-value 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, the 2-out-of-2 module 905 is triggered, so as to trigger the concentration condition triggering module 906, that is, it is determined that the hydrogen concentration meets the corresponding preset condition.
In this embodiment of the present application, optionally, the module 905 for 2 out of 2 may also adopt a logic that 2 out of 4 conforms to; in this embodiment, by adopting the 2-out-of-2 logic, the reliability of determining whether the hydrogen concentration satisfies the preset condition can be ensured.
In the embodiment of the application, the reactor pit water injection control system comprises at least two first control systems, more first control systems are arranged, the reactor working state information acquired by the signal acquisition card can be accurately processed, so that the accuracy of signal processing is improved, and more first control systems and more second control systems are jointly controlled in a multi-platform mode, so that the reliability of equipment control is ensured.
In the embodiment of the application, the software programs installed in the first control systems and the software programs installed in the second control systems are different; the control platform of the first control system is different from the control platform of the second control system; optionally, when two or more first control systems are used, the first control systems may use different control platforms and install different software programs; different software programs are installed on the first control system and the second control system, so that the situation that when one software fails to work normally due to the fact that the corresponding control system cannot work normally due to the fact that one software has a sudden problem, the other control system which is provided with different software does not work normally is avoided, and the reliability of the pit water injection control system is guaranteed.
In the embodiment of the application, the first control system can be a Reactor Protection System (RPS) and a diversity driver system (KDS), and the second control system is a severe accident instrumentation and control system (KDA); the Reactor Protection System (RPS), the diversity driving system (KDS) and the serious accident instrumentation and control system (KDA) are three instrumentation and control systems using different technologies.
In the embodiment of the application, at least two actuating mechanisms are arranged on the pile pit water injection pipeline; the pit water injection control system is used for controlling each actuating mechanism; through setting up actuating mechanism more than two at least, for this step of heap pit water injection provides more guarantees, promoted whole heap pit water injection control system's reliability and accuracy.
In the embodiment of the application, the pit filling water control system further comprises a diversified signal acquisition card, wherein the diversified signal acquisition card is used for acquiring the working state information; the first control system and the second control system are used for acquiring working state information from the diversified signal acquisition cards.
For example, please refer to fig. 10, which shows a schematic diagram of a signal acquisition system provided in 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 a diversified signal acquisition card; the diversity signal acquisition card can be a plurality of signal acquisition cards of different types; correspondingly, when two or more diversified signal acquisition cards are used, the types of the used signal acquisition cards are different, so that the signal acquisition is easy to realize, and the reliability requirement of the system is ensured; optionally, a corresponding number of diverse signal acquisition cards may be set according to the number of the operating state information of the reactor.
In the embodiment of the application, the pit water injection control system further comprises a diversified device driver card, the diversified device driver card is connected with the execution mechanism, and the diversified device driver card is used for driving the execution mechanism to be opened when receiving the opening signal and not receiving the normally-off signal.
For example, please refer to fig. 11, which shows a schematic diagram of a device driving system provided in an embodiment of the present application; the first control system collects the working state information and judges whether the working state information meets the corresponding preset condition, and if the collected working state information does not meet the corresponding preset condition, the first control system sends a normally-off signal to the diversified device driver cards; the multiplicity of device driver cards may be a plurality of different types of device driver cards; if the acquired working state information meets the corresponding preset conditions, the first control system sends a normally-closed releasing signal to the diversified device driver cards; the second control system collects the working state information and judges whether the working state information meets the corresponding preset condition, if the collected working state information does not meet the corresponding preset condition, the second control system sends a closing signal to the diversified device driver cards, and if the collected working state information meets the corresponding preset condition, the second control system sends a starting signal to the diversified device driver cards; the diversified equipment driving cards drive the actuating mechanism to be started under the condition that the normally-closed releasing signal and the starting signal are received.
In the embodiment of the present application, as shown in fig. 12, it shows a schematic diagram of an automatic control structure provided in the embodiment of the present application; 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 two signal acquisition cards are different in type; 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 severe accident instrumentation and control system (KDA), and the RPS, the KDS and the KDA adopt different control platforms and are provided with different software programs for technical processing; two diverse device driver cards, i.e., a diverse device driver card 1 and a diverse device driver card 2, which are different in type; the diversity device driver card 1 is connected with the actuator 1 for driving the actuator 1 to be turned on when the condition is satisfied, and the diversity device driver card 2 is connected with the actuator 2 for driving the actuator 2 to be turned on when the condition is satisfied.
The diversity signal acquisition card 1 acquires a reactor core outlet temperature signal and transmits the acquired reactor core outlet temperature signal to RPS, KDS and 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 primary 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 primary loop pressure signal does not meet the corresponding preset condition, the NAND module outputs a normally-closed signal to the diversity equipment driving card 1 and the diversity equipment driving card 2; and if the reactor core outlet temperature signal and the primary loop pressure signal both meet corresponding preset conditions, the NAND module outputs a normally-closed removing 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 or not through a technical processing 1 module and transmits the processed result to a NAND module, and the KDS judges whether the received primary loop pressure signal meets the corresponding preset pressure condition or not through a 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 primary loop pressure signal does not meet the corresponding preset condition, the NAND module outputs a normally-closed signal to the diversity equipment driving card 1 and the diversity equipment driving card 2; and if the reactor core outlet temperature signal and the primary loop pressure signal both meet corresponding preset conditions, the NAND module outputs a normally-closed removing 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 a corresponding preset temperature condition or not through a technical processing 1 module and transmits the processed result to an AND module, and the KDA judges whether the received primary loop pressure signal meets a corresponding preset pressure condition or not through a 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 primary loop pressure signal does not meet the corresponding preset condition, the reactor core outlet temperature signal and the primary loop pressure signal output a closing signal to the diversity equipment driving card 1 and the diversity equipment driving card 2; and if the reactor core outlet temperature signal and the primary loop pressure signal both meet the corresponding preset conditions, outputting a starting signal to the diversity equipment driving card 1 and the diversity equipment driving card 2 with the module.
When the diversity equipment driving card 1 receives signals from the RPS and the KDS which are normally-off releasing signals and receives a signal from the KDA which is a starting signal, driving the execution mechanism 1 to be started, otherwise, not driving the execution mechanism 1 to be started; when the diversity device driver card 2 receives the signals from the RPS and the KDS, which are both normally-off releasing signals, and the signal from the KDA is a starting signal, the execution mechanism 2 is driven to be started, otherwise, the execution mechanism 2 is not driven to be started.
Correspondingly, each diversified device driver card correspondingly drives one actuating mechanism; correspondingly, when two or more diversified device driver cards are used, the types of the used device driver cards are different, so that the device is easily driven, and the reliability requirement of the system is ensured; alternatively, the number of the diversified device driver cards may be set correspondingly according to the number of the actuators.
The technical features of the above embodiments can be arbitrarily combined, and for the sake of brevity, all possible combinations of the technical features in the above embodiments are not described, but should be considered as the scope of the present specification as long as there is no contradiction between the combinations of the technical features.
The above examples only express several embodiments of the present application, and the description thereof is more specific and detailed, but not construed as limiting the scope of the invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the concept of the present application, which falls within the scope of protection of the present application. Therefore, the protection scope of the present patent shall be subject to the appended claims.
Claims (18)
1. The pile pit water injection control system is characterized by being used for controlling an execution mechanism arranged on a pile pit water injection pipeline and comprising a first control system and a second control system;
the first control system is used for outputting a normally-off signal to the actuating mechanism under the condition that the pit water filling condition is not met, and stopping outputting the normally-off signal to the actuating mechanism under the condition that the pit water filling condition is met;
the second control system is used for outputting a starting signal to the executing mechanism under the condition that the water filling condition of the pile pit is met; the actuating mechanism is used for starting under the condition that the starting signal is received and the normally-off signal is not received.
2. The pile pit water injection control system according to claim 1, wherein the second control system is further connected with a pile pit water level test module, and the pile pit water level test module is used for sending a closing signal to the second control system when the pile pit water level reaches a preset water level value; and the second control system stops outputting an opening signal to the actuating mechanism after receiving a closing signal sent by the pile pit water level testing module.
3. The pit water injection control system according to 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 reactor operating state information;
the working state information comprises a reactor core outlet temperature value and a primary circuit pressure value;
or the working state information comprises the core outlet temperature value, the primary circuit pressure value and radioactive dose in the containment;
or the working state information comprises the reactor core outlet temperature value, the primary circuit pressure value and the hydrogen concentration in the containment vessel;
or the working state information comprises the core outlet temperature value, the primary circuit pressure value, the radioactive dose in the containment and the hydrogen concentration in the containment.
4. The system according to claim 3, further comprising a diversity signal acquisition card for acquiring the operating state information; the first control system and the second control system are used for acquiring the working state information from the diversified signal acquisition cards.
5. The system according to claim 3, wherein the operating status information comprises a plurality of information types;
the first control system and the second control system are used for determining that the filling water condition of the pile pit is met when the working state information of various information types meets corresponding preset conditions.
6. The pit water injection control system according to claim 5, wherein the operating state information includes the core outlet temperature value;
the first control system and the second control system are used for acquiring a plurality of core outlet temperature values and determining a second largest value from the plurality of 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 secondary maximum value is larger than a preset temperature threshold value.
7. The pit water injection control system according to claim 6, wherein 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 core outlet temperature value measured by each temperature sensor.
8. The system of claim 6, wherein the first and second control systems are configured to filter the plurality of core outlet temperature values and determine the second largest value from the filtered plurality of core outlet temperature values.
9. The pile pit water injection control system according to claim 5, wherein the operating state information comprises a primary 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 each loop pressure value is smaller than a preset pressure threshold value;
the first control system and the second control system are configured to determine that the loop pressure value satisfies the corresponding preset condition when the number of the target loop pressure values smaller than the preset pressure threshold satisfies a first preset number condition.
10. The pile pit water injection control system according to claim 9, characterized in that a plurality of pressure sensors are arranged in a loop;
the first control system and the second control system are used for acquiring the pressure value of the primary circuit measured by each pressure sensor.
11. The pit injection control system of claim 5, wherein the operating condition information includes a radioactive dose in 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;
the first control system and the second control system are configured to determine that the radioactive dose satisfies the corresponding preset condition when the number of the radioactive doses larger than the preset dose threshold satisfies a second preset number condition.
12. The pit filling control system according to claim 11, wherein a plurality of radioactive dose detection devices are provided inside the containment;
the first control system and the second control system are configured to acquire the radioactive dose measured by each of the radioactive dose detection apparatuses.
13. The pit water injection control system according to claim 5, wherein the operating condition information includes a hydrogen concentration in 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 greater than a preset concentration threshold value;
the first control system and the second control system are used for determining that the hydrogen concentration meets the corresponding preset condition when the number of the hydrogen concentrations larger than the preset concentration threshold meets a third preset number condition.
14. The pit water injection control system according to 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 detected by each hydrogen concentration detection device.
15. The pit water injection control system according to 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 according to claim 15, wherein a software program installed in each of the first control systems and a software program installed in the second control system are different.
17. The pile pit water injection control system according to any one of claims 1 to 14, wherein at least two actuators are arranged on the pile pit water injection pipeline;
and the pile pit water injection control system is used for controlling each actuating mechanism.
18. The system according to any one of claims 1 to 14, further comprising a multiplicity of device driver cards, wherein the multiplicity of device driver cards are connected to the actuator, and the multiplicity of device driver cards are configured to drive the actuator to open when the open signal is received and the normally-off signal is not received.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111205266.6A CN113972014B (en) | 2021-10-15 | 2021-10-15 | Pile hole water injection control system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111205266.6A CN113972014B (en) | 2021-10-15 | 2021-10-15 | Pile hole water injection control system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN113972014A true CN113972014A (en) | 2022-01-25 |
| CN113972014B CN113972014B (en) | 2023-10-13 |
Family
ID=79587555
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202111205266.6A Active CN113972014B (en) | 2021-10-15 | 2021-10-15 | Pile hole water injection control system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN113972014B (en) |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN105741887A (en) * | 2014-12-11 | 2016-07-06 | 中广核工程有限公司 | Nuclear power plant passive reactor cavity water injection system and method |
| WO2017098624A1 (en) * | 2015-12-10 | 2017-06-15 | 三菱電機株式会社 | Semiconductor device driving circuit |
| CN211090086U (en) * | 2020-01-06 | 2020-07-24 | 黑龙江和润博致科技开发有限公司 | Wisdom lighting control system |
-
2021
- 2021-10-15 CN CN202111205266.6A patent/CN113972014B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN105741887A (en) * | 2014-12-11 | 2016-07-06 | 中广核工程有限公司 | Nuclear power plant passive reactor cavity water injection system and method |
| WO2017098624A1 (en) * | 2015-12-10 | 2017-06-15 | 三菱電機株式会社 | Semiconductor device driving circuit |
| CN211090086U (en) * | 2020-01-06 | 2020-07-24 | 黑龙江和润博致科技开发有限公司 | Wisdom lighting control system |
Also Published As
| Publication number | Publication date |
|---|---|
| CN113972014B (en) | 2023-10-13 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US5621776A (en) | Fault-tolerant reactor protection system | |
| US5586156A (en) | Reactor protection system with automatic self-testing and diagnostic | |
| CN107884672B (en) | Periodic test method for nuclear power plant reactor protection system connection loop | |
| EP0781451B1 (en) | Reactor protection system | |
| CN107484430A (en) | A kind of security system and its operating method for nuclear power plant | |
| CN108711459B (en) | Diversified protection device for fast reactor | |
| DE3402555A1 (en) | ARRANGEMENT AND METHOD FOR CONTROLLING THE REACTIVITY OF A CORE REACTOR, IN PARTICULAR A BOILING WATER REACTOR | |
| ES2904315T3 (en) | Assembly consisting of an emergency release system | |
| CN113972014A (en) | Pile pit water injection control system | |
| CN113688521B (en) | High-reliability reactor protection system test permission function design method and system | |
| KR101608646B1 (en) | Operating system for plant protection system of nuclear power plant and Method of operating using the same | |
| EP0356259A2 (en) | Check valve test method for control rod drive | |
| US4282061A (en) | System for preventing erroneous operation of control rods | |
| CN113593739A (en) | Control method for dealing with water supply flow loss accident of nuclear power plant | |
| CN114188046A (en) | Zero-power reactor starting control method and device | |
| JP2922374B2 (en) | Nuclear power plant accident response support system | |
| CN110970141A (en) | Diversity protection system and method for marine nuclear power platform | |
| JPH08211184A (en) | Reactor containment and its combustible gas concentration controlling method | |
| CN112037949B (en) | Method for executing cap buckling after loading in AP1000 containment overall leakage rate test | |
| JPS62161086A (en) | Automatic decompression system | |
| CN115727313A (en) | Test method for detecting low water level of boiler drum | |
| JPH02272394A (en) | Boric acid water charging device | |
| JPS60166890A (en) | Inhibiting device for reactivity of reactor | |
| JPS62228979A (en) | Inspection device for nuclear reactor protective system | |
| JPH08233990A (en) | Reactor safety system and its functioning state indication method |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |