CN114038598B - Control device system and method for passive nuclear power plant - Google Patents
Control device system and method for passive nuclear power plant Download PDFInfo
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- CN114038598B CN114038598B CN202111298226.0A CN202111298226A CN114038598B CN 114038598 B CN114038598 B CN 114038598B CN 202111298226 A CN202111298226 A CN 202111298226A CN 114038598 B CN114038598 B CN 114038598B
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- 238000000034 method Methods 0.000 title claims abstract description 42
- 238000001514 detection method Methods 0.000 claims abstract description 31
- 230000001934 delay Effects 0.000 claims description 2
- 238000010586 diagram Methods 0.000 description 4
- 230000009286 beneficial effect Effects 0.000 description 3
- 230000001105 regulatory effect Effects 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 230000001960 triggered effect Effects 0.000 description 2
- 238000010977 unit operation Methods 0.000 description 2
- 230000001276 controlling effect Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 239000002918 waste heat Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/12—Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
- G21D3/14—Varying flow of coolant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides a control device system and a control method of a passive nuclear power plant, wherein the control device system comprises a rapid power reduction system and an emergency shutdown system which are arranged in parallel, the rapid power reduction system comprises main pumps, rotating speed sensing devices (1) and flow sensing devices (2) which are sequentially connected on a unit loop, and the number of the rotating speed sensing devices (1) connected with each main pump is at least 2; the emergency shutdown system comprises a power detection device and a control rod group which are connected in sequence; the unit loop comprises a first loop and a second loop which are parallel; 2 main pumps are arranged on the first loop and the second loop in parallel; the method reduces the frequency of triggering reactor shutdown caused by shutdown of one main pump, ensures that the reactor does not shutdown when 1 main pump fails as much as possible, maintains low-power operation of the unit, and greatly improves the operation economy of the unit.
Description
Technical Field
The invention relates to the technical field of nuclear power plants, in particular to a control device system and method of a passive nuclear power plant.
Background
In a passive nuclear power plant, one unit is provided with two loops, each loop is provided with two main pumps, namely, each unit is provided with four main pumps in total. When the flow of coolant in one or both loops is low, the core may deviate from nucleate boiling to trigger reactor shutdown; when any of the main pumps fails, a low flow of coolant in the loop will trigger reactor shutdown to avoid core deviation from nucleate boiling.
However, a failure of one main pump triggers a reactor shutdown, which results in an unplanned reactor shutdown and severely affects unit operation economy.
CN103426483a discloses a control method of main pump tripping logic for two loops, when two or more than two detected rotation speed signals in independent channels reach low constant value, and the power of the reactor is above P7, the reactor is scram, and the auxiliary water feeding pump is started; when one or more than one of the independent channels IP and IIIP is/are monitored to reach a low constant value, and when two or more than two of the independent channels are monitored to reach a low constant value, the primary pump is tripped, wherein the power of the primary pump is above P7; when one or more of the independent channels IIP, IVP is monitored to reach a low constant value, and when two or more of the independent channels are monitored to reach a low constant value, and the power is above P7, the No. two main pump trips. The invention has the advantages that when one main pump is stopped for self reasons, the normal operation of the other main pump is not influenced, the forced circulation of a single loop can be maintained, the invention is beneficial to the waste heat discharge of the reactor, and the reliable and safe operation of the nuclear power plant is more beneficial. However, the problem that the shutdown of one main pump of the nuclear power plant does not affect the reactor shutdown is not solved.
Therefore, it is of great importance to develop a control device system and method for a passive nuclear power plant in which the reactor can be shut down as little as possible after an unexpected shut down of one main pump.
Disclosure of Invention
In view of the problems existing in the prior art, the invention provides a control device system and a control method of a passive nuclear power plant, wherein the control device system can reduce the power of a reactor to below 50% by combining an emergency shutdown system after one main pump is shut down, so that the frequency of triggering the reactor shutdown by shutting down one main pump is reduced.
To achieve the purpose, the invention adopts the following technical scheme:
in a first aspect, the invention provides a control device system of a passive nuclear power plant, the control device system comprises a rapid power reduction system and an emergency shutdown system which are arranged in parallel, the rapid power reduction system comprises main pumps, rotating speed sensing devices and flow sensing devices which are sequentially connected to a unit loop, and the number of the rotating speed sensing devices connected with each main pump is at least 2; the emergency shutdown system comprises a power detection device and a control rod group which are connected in sequence; the unit loop comprises a first loop and a second loop which are parallel; and 2 main pumps are arranged on the first loop and the second loop in parallel.
According to the control device system of the passive nuclear power plant, at least two rotating speed sensing devices are connected with each main pump, so that response logic of a unit loop to the shutdown of the main pumps is changed, the emergency shutdown system is further matched for regulating and controlling the power of a reactor, the power of the reactor is reduced to be lower than 50%, low-power operation is performed, the shutdown of the pump is guaranteed without shutdown, and the frequency of triggering the shutdown of the reactor due to shutdown of one main pump of the nuclear power plant is greatly reduced.
Preferably, the rotation speed sensing means is provided at the bottom of the main pump.
Preferably, the first loop and the second loop are respectively provided with 4 flow sensing devices in parallel.
Preferably, the rapid power reduction system comprises a rotating speed signal comparison device, a first logic judgment device, a second logic judgment device, a third logic judgment device and a first delay control device which are sequentially connected with the rotating speed sensing device.
Preferably, the emergency shutdown system comprises a flow signal comparison device, a fourth logic judgment device, a fifth logic judgment device, a sixth logic judgment device, a seventh logic judgment device and a second delay control device.
Preferably, the flow signal comparing device, the fourth logic judging device, the fifth logic judging device and the seventh logic judging device are connected in sequence.
Preferably, the fifth logic determination device and the sixth logic determination device are arranged in parallel.
Preferably, the fourth logic judgment device, the second delay control device and the sixth logic judgment device are connected in sequence.
Preferably, the control device system comprises a first power comparing device and a second power comparing device respectively connected with the power detecting device.
In a second aspect, the present invention provides a control method of an passive nuclear power plant, the control method being performed by using the control device system of the passive nuclear power plant according to the first aspect.
According to the control method of the passive nuclear power plant, the low-rotation-speed signal of the main pump output by the rotation speed sensing device and the low-flow signal of the loop output by the flow sensing device are judged and analyzed, and the emergency shutdown system is combined to reduce the power of the reactor, so that after the main pump is shut down, the steam turbine is shut down, the reactor is not shut down, and the unit operates at low power, so that the number of times of unplanned shutdown of the reactor is greatly reduced. The control method also comprises a shutdown logic for ensuring the safety of the nuclear power plant, and improves the running economy of the unit to the greatest extent on the premise of safe running of the nuclear power plant.
Preferably, the control logic of the control method comprises:
At least 2 of the rotating speed sensing devices connected with each main pump output a main pump low rotating speed signal, and meanwhile, the power detection device of the emergency shutdown system detects that the power of the reactor is less than 50%, so that the emergency shutdown system does not act;
At least 2 rotating speed sensing devices connected with each main pump output a main pump low rotating speed signal, meanwhile, a power detection device of the emergency shutdown system detects that the power of the reactor is greater than 50%, the rapid power reduction system sends an instruction to the emergency shutdown system, the emergency shutdown system releases a control rod group to regulate the power of the reactor, and after the control rod group is regulated, the power detection device detects that the power of the reactor is less than 50%, and the emergency shutdown system does not act; the power detection device detects that the power of the reactor is still greater than 50%, and the emergency shutdown system triggers the reactor to shut down;
after at least 2 of the rotating speed sensing devices connected with each main pump output a main pump low rotating speed signal, a flow sensing device on a unit loop outputs a loop low flow signal;
When any unit loop outputs a loop low-flow signal and the power detection device detects that the power of the reactor is greater than 50%, the emergency shutdown system triggers the reactor to shut down;
When the first loop and the second loop output a loop low flow signal at the same time, the reactor is shut down.
The emergency shutdown system disclosed by the invention is used for regulating the power of the reactor by releasing the control rod group, mainly releasing part of the control rods in the control rod group, so that the power of the reactor is reduced to below 50% as much as possible, and the number of the released control rods is about 0.06% of the number of the control rods in the control rod group generally, but not all the control rods are released, so that the reactor is shutdown.
The power of the reactor according to the invention is greater than 50%, for example 51%, 53%, 55%, 60%, or 70%, and the power of the reactor is less than 50%, for example 49%, 45%, 40%, or 30%.
Preferably, the emergency shutdown system releases the control rod group to adjust the power of the reactor, and after the power detection device detects that the power of the reactor is less than 50%, the emergency shutdown system delays for 5-8 seconds to trigger the shutdown of the steam turbine.
The delay of 5-8 s in the invention triggers the shutdown of the steam turbine, for example, 5s, 5.5s, 6s, 7s, 7.5s or 8s, preferably 5s or 8s. According to the control method, one main pump is stopped but the reactor is not stopped, but the steam turbine is still in full-load operation after one main pump is stopped, so that the reactor is excessively cooled, and after the power detection device detects that the power of the reactor is less than 50%, the stopping of the steam turbine is triggered by delaying for 5-8 s. The reactor runs with less than 50% of power to generate heat, and the heat is firstly transmitted to a steam generator of the nuclear power plant by a main pump, and the steam generated by the steam generator does not enter a steam turbine, directly enters a condenser through a steam side discharge system to be condensed and/or is discharged through a steam release system.
Preferably, the main pump low rotation speed signal is that the percentage rotation speed of the main pump is 85% -95%, for example, 85%, 86%, 88%, 90%, 92% or 95%.
Preferably, the loop low flow signal is a loop with a percentage flow of 85% -95%, for example 85%, 86%, 88%, 90%, 92% or 95%.
Preferably, the rotation speed signal comparing device compares the detected rotation speed value of the main pump with the total rotation speed value of the main pump, judges whether the rotation speed of the main pump is reduced to 85% -95% of the total rotation speed, if yes, outputs 1, otherwise outputs 0.
The rotating speed signal comparison device judges that the detected rotating speed value of the main pump is reduced to a certain fixed value between 85% and 95% of the total rotating speed value of the main pump, if yes, 1 is output, and if not, 0 is output; and the output is 1 when the rotation speed is not reduced to the range of 85% -95% of the total rotation speed of the main pump.
Preferably, the flow signal comparison device compares the detected loop flow value with the loop full flow value, judges whether the flow of the loop is reduced to 85% -95% of the loop full flow value, outputs 1 if yes, and outputs 0 if not.
The flow signal comparison device judges that the detected loop flow value is reduced to a certain constant value between 85% and 95% of the loop total flow value, if yes, outputting 1, otherwise outputting 0; instead of decreasing to between 85% and 95% of the loop full flow value, output 1.
Preferably, the first logic judgment device, the third logic judgment device, the fifth logic judgment device and the sixth logic judgment device receive two 1 signals, and output 1, otherwise output 0.
Preferably, the second logic judging device receives more than one 1 signal, outputs 1, otherwise outputs 0.
Preferably, the fourth logic judging device receives more than two 1 signals, outputs 1, otherwise outputs 0.
Preferably, the seventh logic judging device receives more than one 1 signal, outputs 1, otherwise outputs 0.
As a preferred technical solution of the present invention, the control logic of the control method includes:
At least 2 rotating speed sensing devices connected with each main pump output a main pump low rotating speed signal, a rotating speed signal comparison device compares the rotating speed value of the main pump with the total rotating speed value of the main pump at the moment, and judges whether the rotating speed of the main pump is reduced to 85% -95% of the total rotating speed, if so, the rotating speed is output 1; the first logic judging device receives the two 1 signals output by the rotating speed signal comparing device and outputs 1; the second logic judgment device receives a1 signal output by the first logic judgment device, and outputs 0; meanwhile, the power detection device of the emergency shutdown system detects the power of the reactor, a 0 signal of which the power of the reactor is less than 50% is obtained after comparison by the first power comparison device, and then the third logic judgment device outputs the 0 signal, so that the emergency shutdown system does not act;
at least 2 rotating speed sensing devices connected with each main pump output a main pump low rotating speed signal, a rotating speed signal comparison device compares the rotating speed value of the main pump with the total rotating speed value of the main pump at the moment, and judges whether the rotating speed of the main pump is reduced to 85% -95% of the total rotating speed, if so, the rotating speed is output 1; the first logic judging device receives the two 1 signals output by the rotating speed signal comparing device and outputs 1; the second logic judgment device receives a1 signal output by the first logic judgment device, and outputs 0; meanwhile, the power detection device of the emergency shutdown system detects the power of the reactor, a1 signal with the power of the reactor being more than 50% is obtained after comparison by the first power comparison device, the third logic judgment device outputs the 1 signal, the rapid power reduction system sends an instruction to the emergency shutdown system, the emergency shutdown system releases the control rod group to adjust the power of the reactor, after adjustment, the power detection device detects the power of the reactor, a 0 signal with the power of the reactor being less than 50% is obtained after comparison by the first power comparison device, the first delay control device acts, the delay is 5-8 seconds, the turbine is triggered to stop, and the emergency shutdown system does not act; the power detection device detects the power of the reactor, a signal 1 with the power of the reactor being more than 50% is obtained after the power detection device is compared with the power of the reactor by the first power comparison device, and then the seventh logic judgment device outputs the signal 1, and the emergency shutdown system triggers the reactor shutdown;
After at least 2 of the rotating speed sensing devices connected with each main pump output a main pump low rotating speed signal, a flow sensing device on a unit loop outputs a loop low flow signal; the flow signal comparison device compares the detected loop flow value with the loop full flow value, judges whether the flow of the loop is reduced to 85% -95% of the loop full flow value, and outputs 1 if the flow is reduced to 85% -95% of the loop full flow value;
When any unit loop outputs a loop low-flow signal, the fourth logic judging device receives more than two 1 signals output by the flow signal comparing device and outputs 1, and the fifth logic judging device receives one 1 signal output by the fourth logic judging device and outputs 1; the second delay control device acts, meanwhile, the power detection device detects the power of the reactor, a1 signal with the power of the reactor being more than 50% is obtained after the power detection device is compared with the power of the reactor by the second power comparison device, then the sixth logic judgment device outputs the 1 signal, the seventh logic judgment device outputs 1 after receiving the fifth logic judgment device or more than one 1 signal output by the sixth logic judgment device, and the emergency shutdown system triggers the reactor shutdown;
When the first loop and the second loop output loop low-flow signals at the same time, the fourth logic judging device receives more than two 1 signals output by the flow signal comparing device, 1 is output, the fifth logic judging device receives the two 1 signals output by the fourth logic judging device, 1 is output, the seventh logic judging device receives more than one 1 signal output by the fifth logic judging device, 1 is output, and the emergency shutdown system triggers the reactor shutdown.
The numerical ranges recited herein include not only the recited point values, but also any point values between the recited numerical ranges that are not recited, and are limited to, and for the sake of brevity, the invention is not intended to be exhaustive of the specific point values that the recited range includes.
Compared with the prior art, the invention has at least the following beneficial effects:
(1) The control device system of the passive nuclear power plant reduces the frequency of triggering the reactor shutdown caused by shutdown of one main pump, and achieves the purpose of reducing the number of unplanned shutdown times;
(2) According to the control method of the passive nuclear power plant, provided by the invention, the low-power operation of the unit is maintained under the condition that one main pump is stopped, if the fault can be rapidly eliminated, the unit can be rapidly increased in power, the restarting time after the shutdown is saved, and the running economy of the unit is improved.
Drawings
FIG. 1 is a control logic diagram of the emergency shutdown system operation and turbine shutdown in the control method of the passive nuclear power plant provided by the invention.
FIG. 2 is a control logic diagram of an emergency shutdown system triggering reactor shutdown in a control method of a passive nuclear power plant provided by the invention.
In the figure: 1-a rotation speed sensing device; 2-a flow sensing device; 3-a rotation speed signal comparison device; 4-a first logic judgment device; 5-a second logic judgment device; 6-a third logic judgment device; 7-a flow signal comparison device; 8-fourth logic judgment means; 9-fifth logic judgment means; 10-sixth logic judgment means; 11-seventh logic judgment means; 12-a second delay control device; 13-a first power comparison means; 14-a first delay control device; 15-second power comparison means.
Detailed Description
The technical scheme of the invention is further described below by the specific embodiments with reference to the accompanying drawings.
The present invention will be described in further detail below. The following examples are merely illustrative of the present invention and are not intended to represent or limit the scope of the invention as defined in the claims.
As a specific embodiment of the present invention, a control device system of a passive nuclear power plant is provided, where the control device system includes a rapid power reduction system and an emergency shutdown system that are arranged in parallel, the rapid power reduction system includes a main pump, a rotation speed sensing device 1 and a flow sensing device 2 that are sequentially connected to a unit loop, and the number of rotation speed sensing devices 1 connected to each main pump is at least 2; the emergency shutdown system comprises a power detection device and a control rod group which are connected in sequence; the unit loop comprises a first loop and a second loop which are parallel; and 2 main pumps are arranged on the first loop and the second loop in parallel. And 4 flow sensing devices 2 are arranged on the first loop and the second loop in parallel.
The rapid power reduction system comprises a rotating speed signal comparison device 3, a first logic judgment device 4, a second logic judgment device 5, a third logic judgment device 6 and a first delay control device 14 which are sequentially connected with a rotating speed sensing device 1.
The emergency shutdown system comprises a flow signal comparison device 7, a fourth logic judgment device 8, a fifth logic judgment device 9, a sixth logic judgment device 10, a seventh logic judgment device 11 and a second delay control device 12;
The flow signal comparison device 7, the fourth logic judgment device 8, the fifth logic judgment device 9 and the seventh logic judgment device 11 are connected in sequence; the fifth logic judgment device 9 and the sixth logic judgment device 10 are arranged in parallel; the fourth logic judgment device 8, the second delay control device 12 and the sixth logic judgment device 10 are connected in sequence.
The control device system comprises a first power comparing device 13 and a second power comparing device 15, which are respectively connected to the power detecting device.
As a specific embodiment of the present invention, there is provided a control method of a passive nuclear power plant, which is performed using the control device system of the passive nuclear power plant described above. Fig. 1 is a control logic diagram of an emergency shutdown system action and a steam turbine shutdown in the control method of the passive nuclear power plant provided by the invention, and fig. 2 is a control logic diagram of an emergency shutdown system triggering reactor shutdown in the control method of the passive nuclear power plant provided by the invention.
Specifically, the control logic of the control method includes:
At least 2 of the rotating speed sensing devices 1 connected with each main pump output a main pump low rotating speed signal, the rotating speed signal comparison device 3 compares the rotating speed value of the main pump with the total rotating speed value of the main pump at the moment, and judges whether the rotating speed of the main pump is reduced to 85% -95% of the total rotating speed, if so, the rotating speed is output 1; the first logic judging device 4 receives the two 1 signals output by the rotating speed signal comparing device 3 and outputs 1; the second logic judgment device 5 receives the 1 signal output by the first logic judgment device 4 and outputs 0; meanwhile, the power detection device of the emergency shutdown system detects the power of the reactor, a 0 signal of which the power of the reactor is less than 50% is obtained after the power detection device is compared by the first power comparison device 13, and then the third logic judgment device 6 outputs the 0 signal, so that the emergency shutdown system does not act;
at least 2 of the rotating speed sensing devices 1 connected with each main pump output a main pump low rotating speed signal, the rotating speed signal comparison device 3 compares the rotating speed value of the main pump with the total rotating speed value of the main pump at the moment, and judges whether the rotating speed of the main pump is reduced to 85% -95% of the total rotating speed, if so, the rotating speed is output 1; the first logic judging device 4 receives the two 1 signals output by the rotating speed signal comparing device 3 and outputs 1; the second logic judgment device 5 receives the 1 signal output by the first logic judgment device 4 and outputs 0; meanwhile, the power detection device of the emergency shutdown system detects the power of the reactor, a 1 signal with the power of the reactor being more than 50% is obtained after the power is compared by the first power comparison device 13, the third logic judgment device 6 outputs the 1 signal, the rapid power reduction system sends an instruction to the emergency shutdown system, the emergency shutdown system releases a control rod group to adjust the power of the reactor, after the adjustment, the power detection device detects the power of the reactor, a 0 signal with the power of the reactor being less than 50% is obtained after the power is compared by the first power comparison device 13, the first delay control device 14 acts, the delay is 5-8 seconds to trigger the turbine to stop, and the emergency shutdown system does not act; the power detection device detects the power of the reactor, a signal 1 with the power of the reactor being more than 50% is obtained after the power is compared by the first power comparison device 13, the signal 1 is output by the seventh logic judgment device 11, and the emergency shutdown system triggers the reactor shutdown;
After at least 2 of the rotating speed sensing devices 1 connected with each main pump output a main pump low rotating speed signal, the flow sensing devices 2 on the unit loop output a loop low flow signal; the flow signal comparison device 7 compares the detected loop flow value with the loop full flow value, judges whether the flow of the loop is reduced to 85% -95% of the loop full flow value, and outputs 1 if the flow is reduced to 85% -95% of the loop full flow value;
when any unit loop outputs a loop low-flow signal, the fourth logic judging device 8 receives more than two 1 signals output by the flow signal comparing device, 1 is output, the fifth logic judging device 9 receives one 1 signal output by the fourth logic judging device 8, 1 is output, the second delay control device 12 acts, meanwhile, the power detecting device detects the power of the reactor, the power detecting device 15 compares the power to obtain a 1 signal with the power of the reactor being more than 50%, the sixth logic judging device 10 outputs a 1 signal, the seventh logic judging device 11 receives more than one 1 signal output by the fifth logic judging device 9 or the sixth logic judging device 10, 1 is output, and the emergency shutdown system triggers the reactor shutdown;
When the first loop and the second loop output the low-flow signal of the loop at the same time, the fourth logic judging device 8 receives more than two 1 signals output by the flow signal comparing device 2, then outputs 1, the fifth logic judging device 9 receives the two 1 signals output by the fourth logic judging device 8, then outputs 1, the seventh logic judging device 11 receives more than one 1 signal output by the fifth logic judging device 9, then outputs 1, and the emergency shutdown system triggers the reactor shutdown.
In summary, the control device system and the control method for the passive nuclear power plant provided by the invention reduce the frequency of triggering the reactor shutdown caused by shutdown of one main pump, achieve the purpose of reducing the unplanned shutdown times, and further improve the unit operation economy.
The applicant declares that the above is only a specific embodiment of the present invention, but the scope of the present invention is not limited thereto, and it should be apparent to those skilled in the art that any changes or substitutions that are easily conceivable within the technical scope of the present invention disclosed by the present invention fall within the scope of the present invention and the disclosure.
Claims (17)
1. A control method of a passive nuclear power plant, characterized in that control logic of the control method comprises:
At least 2 of the rotating speed sensing devices (1) connected with each main pump output a main pump low rotating speed signal, and meanwhile, the power detection device of the emergency shutdown system detects that the power of the reactor is less than 50%, so that the emergency shutdown system does not act;
At least 2 of the rotating speed sensing devices (1) connected with each main pump output a main pump low rotating speed signal, meanwhile, the power detection device of the emergency shutdown system detects that the power of the reactor is greater than 50%, the rapid power reduction system sends an instruction to the emergency shutdown system, the emergency shutdown system releases a control rod group to adjust the power of the reactor, and after the control rod group is adjusted, the power detection device detects that the power of the reactor is less than 50%, and the emergency shutdown system does not act; the power detection device detects that the power of the reactor is still greater than 50%, and the emergency shutdown system triggers the reactor to shut down;
after at least 2 of the rotating speed sensing devices (1) connected with each main pump output a main pump low rotating speed signal, the flow sensing devices (2) on the unit loop output a loop low flow signal;
When any unit loop outputs a loop low-flow signal and the power detection device detects that the power of the reactor is greater than 50%, the emergency shutdown system triggers the reactor to shut down;
when the first loop and the second loop output loop low flow signals at the same time, the reactor is shut down;
The control method is carried out by adopting a control device system of the passive nuclear power plant;
The control device system comprises a rapid power reduction system and an emergency shutdown system which are arranged in parallel, wherein the rapid power reduction system comprises main pumps, rotating speed sensing devices (1) and flow sensing devices (2) which are sequentially connected to a unit loop, and the number of the rotating speed sensing devices (1) connected with each main pump is at least 2; the emergency shutdown system comprises a power detection device and a control rod group which are connected in sequence; the unit loop comprises a first loop and a second loop which are parallel; and 2 main pumps are arranged on the first loop and the second loop in parallel.
2. Control method according to claim 1, characterized in that 4 flow sensing devices (2) are arranged in parallel on both the first loop and the second loop.
3. The control method according to claim 1, characterized in that the rapid power reduction system comprises a rotational speed signal comparison device (3), a first logic judgment device (4), a second logic judgment device (5), a third logic judgment device (6) and a first delay control device (14) which are sequentially connected with the rotational speed sensing device (1).
4. The control method according to claim 1, characterized in that the emergency shutdown system comprises a flow signal comparison means (7), a fourth logic determination means (8), a fifth logic determination means (9), a sixth logic determination means (10), a seventh logic determination means (11) and a second delay control means (12).
5. The control method according to claim 4, wherein the flow signal comparing means (7), the fourth logic judging means (8), the fifth logic judging means (9), and the seventh logic judging means (11) are connected in this order.
6. The control method according to claim 5, characterized in that the fifth logic determination means (9) and the sixth logic determination means (10) are arranged in parallel.
7. The control method according to claim 4, wherein the fourth logic judgment means (8), the second delay control means (12), and the sixth logic judgment means (10) are connected in this order.
8. A control method according to claim 1, characterized in that the control device system comprises a first power comparison device (13) and a second power comparison device (15) connected to the power detection device, respectively.
9. The control method according to claim 1, wherein the emergency shutdown system releases the control rod group to adjust the power of the reactor, and after the power detection device detects that the power of the reactor is less than 50%, the power detection device delays for 5-8 seconds to trigger the shutdown of the steam turbine.
10. The control method according to claim 1, wherein the main pump low rotation speed signal is a percentage rotation speed of the main pump of 85% to 95%.
11. The control method of claim 1, wherein the loop low flow signal is a percentage flow of 85% -95% of the loop.
12. A control method according to claim 3, characterized in that the rotation speed signal comparing means (3) compares the detected rotation speed value of the main pump with the total rotation speed value of the main pump, determines whether the rotation speed of the main pump is reduced to 85% -95% of the total rotation speed, and outputs 1 if yes, and outputs 0 if not.
13. The control method according to claim 4, wherein the flow signal comparing means (7) compares the detected loop flow value with the loop full flow value to determine whether the loop flow is reduced to 85% -95% of the loop full flow value, and outputs 1 if yes, and outputs 0 if not.
14. A control method according to claim 3, characterized in that the first logic determination means (4), the third logic determination means (6), the fifth logic determination means (9) and the sixth logic determination means (10) receive two 1 signals and output 1, otherwise output 0.
15. A control method according to claim 3, characterized in that the second logic determination means (5) receives more than one 1 signal and outputs 1, otherwise outputs 0.
16. The control method according to claim 4, wherein the fourth logic judgment means (8) outputs 1 upon receipt of two or more 1 signals, and outputs 0 otherwise.
17. The control method according to claim 4, wherein the seventh logic judging means (11) outputs 1 when receiving one or more 1 signals, and outputs 0 otherwise.
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