CN115100914B - Method, system and computer equipment for simulating primary circuit water pressure test of nuclear power station - Google Patents
Method, system and computer equipment for simulating primary circuit water pressure test of nuclear power station Download PDFInfo
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 167
- 238000012360 testing method Methods 0.000 title claims abstract description 151
- 238000000034 method Methods 0.000 title claims abstract description 43
- 239000002918 waste heat Substances 0.000 claims abstract description 77
- 238000004088 simulation Methods 0.000 claims abstract description 51
- 238000007599 discharging Methods 0.000 claims abstract description 22
- 238000012937 correction Methods 0.000 claims abstract description 21
- 238000005056 compaction Methods 0.000 claims abstract description 18
- 230000002706 hydrostatic effect Effects 0.000 claims description 32
- 230000009471 action Effects 0.000 claims description 20
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The application relates to the technical field of industrial safety of nuclear power plants, and discloses a method, a system and computer equipment for simulating a primary circuit water pressure test of a nuclear power plant, wherein the method comprises the following steps: receiving a correction instruction, correcting the simulated hydraulic test pump, and adjusting the flow of the corrected simulated hydraulic test pump to a preset minimum flow; receiving an initial state adjustment instruction, and discharging the simulated core waste heat until the simulated core waste heat is smaller than a preset waste heat threshold; and receiving an operation instruction, and simulating a state of the primary circuit in the full-range simulator of the nuclear power station during the compaction based on the operation instruction. According to the full-range simulation machine, the functions of the existing full-range simulation machine are expanded through correction of the simulated water pressure test pump and adjustment of the simulated core waste heat, and smooth implementation of the primary circuit water pressure test on the full-range simulation machine can be achieved.
Description
Technical Field
The invention relates to the technical field of industrial safety of nuclear power stations, in particular to a method, a system and computer equipment for simulating primary circuit water pressure test of a nuclear power station.
Background
The pressurized water reactor nuclear power station mainly comprises a pressurized water reactor, a primary loop system and a secondary loop system. A circuit system mainly comprises a pressure vessel and a pipeline connected with the pressure vessel. In order to verify whether the pressure bearing capacity of the pressure vessel of the primary circuit and its associated piping meets design requirements, a primary circuit water pressure test must be conducted in a newly built nuclear power plant, and a periodic retest (typically once every 10 years) must be conducted in the nuclear power plant in use. The primary loop water pressure test is an oversized, high-risk and high-difficulty debugging project of the pressurized water reactor nuclear motor unit.
The cycle span of the primary circuit water pressure test is ten years, the running operation experience is difficult to inherit, meanwhile, the primary circuit pressure in the actual test process is changed greatly, and the serious consequences of pressure runaway can be caused by a little running operation error, so that the proper simulator exercise is very necessary for operators through the full-range simulator before the test. However, the existing full-range simulator cannot meet the requirements of the primary hydraulic test of the primary reactor core and the hydraulic test pump, and cannot perform the primary hydraulic test simulation.
In view of the above technical problems, no effective solution has been proposed at present.
Disclosure of Invention
Based on the defects of the prior art, the invention provides a method, a system and computer equipment for simulating a primary circuit water pressure test of a nuclear power plant, so as to realize that the primary circuit water pressure test is simulated on a full-range simulator of the nuclear power plant.
In a first aspect, the present application proposes a method for simulating a primary circuit hydraulic pressure test of a nuclear power plant, which is applied to a full-range simulator of the nuclear power plant, where the full-range simulator of the nuclear power plant is used for simulating the operation of the nuclear power plant, and the method includes:
receiving a correction instruction, correcting the simulated hydraulic test pump, and adjusting the flow of the corrected simulated hydraulic test pump to a preset minimum flow;
receiving an initial state adjustment instruction, and discharging the simulated core waste heat until the simulated core waste heat is smaller than a preset waste heat threshold;
and receiving an operation instruction, and simulating a state of the primary circuit in the full-range simulator of the nuclear power station during the compaction based on the operation instruction.
In an embodiment, receiving the initial state adjustment command, and discharging the simulated core waste heat until the simulated core waste heat is less than a preset waste heat threshold value includes:
receiving the initial state adjustment instruction, and adjusting the total reactor core decay heat to be the lower limit value of the full-range simulator so as to reduce the fission product decay heat;
and operating the simulated RRA system to discharge the simulated core waste heat until the simulated core waste heat is smaller than the preset waste heat threshold.
In an embodiment, the receiving the operation instruction, based on the operation instruction, the simulating the state of the loop in the full-range simulator of the nuclear power plant during the compaction includes:
receiving the operation instruction, and adjusting and simulating the initial temperature of a loop to reach the target temperature;
pressurizing the simulation primary loop until the simulation primary loop water pressure reaches a test water pressure target value;
when the simulated primary circuit water pressure reaches the test water pressure target value, adjusting the flow of the corrected simulated water pressure test pump to the preset minimum flow, and stabilizing the simulated primary circuit water pressure to the test water pressure target value;
and reducing the pressure of the analog primary circuit until the analog primary circuit water pressure reaches a first water pressure target value.
In one embodiment, said pressurizing said simulated primary circuit until said simulated primary circuit water pressure reaches a test water pressure target value comprises:
pressurizing the simulated primary circuit by using a simulated RCV system until the simulated primary circuit water pressure reaches a second water pressure target value;
and pressurizing the simulated primary loop by using the corrected simulated hydrostatic test pump until the simulated primary loop hydraulic pressure reaches the test hydraulic pressure target value.
In one embodiment, said depressurizing said analog first circuit until said analog first circuit water pressure reaches a first water pressure target value comprises:
stopping the corrected simulated hydraulic test pump, and naturally reducing the pressure of the simulated primary loop to the second hydraulic target value;
operating the simulated RCV system to depressurize the simulated primary circuit until the simulated primary circuit water pressure reaches the first water pressure target value.
In an embodiment, the method further comprises:
receiving a fault simulation instruction and simulating a fault scene;
and receiving a fault handling instruction, and handling the simulated fault scene.
In an embodiment, the method further comprises:
and performing an overpressure protection action based on the overpressure protection logic and the simulated primary circuit water pressure, wherein the overpressure protection logic is used for indicating the simulated primary circuit water pressure alarm value and the overpressure protection action corresponding to the water pressure alarm value.
In an embodiment, the method further comprises:
and acquiring a state and an overpressure protection action during primary circuit water compaction in the full-range simulator of the nuclear power station, generating a simulation picture and displaying the simulation picture.
In a second aspect, the present application provides a system for simulating a primary circuit hydraulic test of a nuclear power plant, the system being applied to a full-range simulator of the nuclear power plant, the full-range simulator being used for simulating operation of the nuclear power plant, the system comprising:
test pump correction module: the device is used for receiving a correction instruction, correcting the simulated hydrostatic test pump, and adjusting the flow of the corrected simulated hydrostatic test pump to a preset minimum flow;
the initial state adjustment module: the device is used for receiving the initial state adjustment instruction, and discharging the simulated reactor core waste heat until the simulated reactor core waste heat is smaller than a preset waste heat threshold;
and an operation module: and the system is used for receiving an operation instruction, and simulating a state of the primary circuit in the full-range simulator of the nuclear power station during water compaction based on the operation instruction.
In a third aspect, the present application provides a computer device comprising a memory, a processor and a computer program stored on the memory and executable on the processor, the processor implementing the simulated nuclear power plant first-circuit hydraulic test method according to the first aspect when executing the computer program.
Compared with the background art, the method, the system and the computer equipment for simulating the primary circuit water pressure test of the nuclear power station are applied to a full-range simulator of the nuclear power station, the full-range simulator of the nuclear power station is used for simulating the operation of the nuclear power station, and the method comprises the following steps: receiving a correction instruction, correcting the simulated hydraulic test pump, and adjusting the flow of the corrected simulated hydraulic test pump to a preset minimum flow; receiving an initial state adjustment instruction, and discharging the simulated core waste heat until the simulated core waste heat is smaller than a preset waste heat threshold; and receiving an operation instruction, and simulating a state of the primary circuit in the full-range simulator of the nuclear power station during the compaction based on the operation instruction. According to the full-range simulation machine, the functions of the existing full-range simulation machine are expanded through correction of the simulated water pressure test pump and adjustment of the simulated core waste heat, and smooth implementation of the primary circuit water pressure test on the full-range simulation machine can be achieved.
The details of one or more embodiments of the application are set forth in the accompanying drawings and the description below to provide a more thorough understanding of the other features, objects, and advantages of the application.
Drawings
The accompanying drawings, which are included to provide a further understanding of the application and are incorporated in and constitute a part of this application, illustrate embodiments of the application and together with the description serve to explain the application and do not constitute an undue limitation to the application. In the drawings:
FIG. 1 is a schematic structural diagram of an application environment for a simulated nuclear power plant primary circuit water pressure test method in one embodiment of the present application;
FIG. 2 is a flow chart of a method of simulating a primary circuit water pressure test of a nuclear power plant in one embodiment of the present application;
FIG. 3 is a flow chart of a simulation of a state of a circuit in a full range simulator of a nuclear power plant while compacting water based on operational instructions in one embodiment of the present application;
FIG. 4 is a flow chart of a method of simulating a primary circuit water pressure test of a nuclear power plant in a preferred embodiment of the present application;
FIG. 5 is a schematic diagram of a simulated nuclear power plant primary circuit hydraulic test system in accordance with one embodiment of the present application;
FIG. 6 is a schematic structural diagram of a computer device according to one 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 and illustrated below with reference to the accompanying drawings and examples. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the present application. All other embodiments, which can be made by one of ordinary skill in the art without undue burden on the person of ordinary skill in the art based on the embodiments provided herein, are intended to be within the scope of the present application. Moreover, it should be appreciated that while such a development effort might be complex and lengthy, it would nevertheless be a routine undertaking of design, fabrication, or manufacture for those of ordinary skill having the benefit of this disclosure, and thus should not be construed as having the benefit of this disclosure.
Reference in the specification to "an embodiment" means that a particular feature, structure, or characteristic described in connection with the embodiment may be included in at least one embodiment of the application. The appearances of such phrases in various places in the specification are not necessarily all referring to the same embodiment, nor are separate or alternative embodiments mutually exclusive of other embodiments. It is to be expressly and implicitly understood by those of ordinary skill in the art that the embodiments described herein can be combined with other embodiments without conflict.
Unless defined otherwise, technical or scientific terms used herein should be given the ordinary meaning as understood by one of ordinary skill in the art to which this application belongs. Reference to "a," "an," "the," and similar terms herein do not denote a limitation of quantity, but rather denote the singular or plural. The terms "comprising," "including," "having," and any variations thereof, are intended to cover a non-exclusive inclusion; for example, a process, method, system, article, or apparatus that comprises a list of steps or modules (elements) is not limited to only those steps or elements but may include other steps or elements not expressly listed or inherent to such process, method, article, or apparatus. The terms "connected," "coupled," and the like in this application are not limited to physical or mechanical connections, but may include electrical connections, whether direct or indirect. The term "plurality" as used herein means greater than or equal to two. "and/or" describes an association relationship of an association object, meaning that there may be three relationships, e.g., "a and/or B" may mean: a exists alone, A and B exist together, and B exists alone. The terms "first," "second," "third," and the like, as used herein, are merely distinguishing between similar objects and not representing a particular ordering of objects.
The primary circuit hydraulic test method for simulating the nuclear power station is applied to a full-range simulator of the nuclear power station. As shown in FIG. 1, the full-range simulator of the nuclear power station consists of a main control room, a teaching console, a main machine room, a remote console and an emergency system. In the running process of the analog machine system, an operator performs operation related to running through an operator, buttons, a switch and the like, starts or stops certain equipment and increases or decreases the load of certain equipment. The signals generated by the operation enter the simulation computer system, the simulation computer system utilizes model software to carry out operation or logic judgment according to the change of the signals, and then the results are sent to display equipment on a simulation control panel table to display the dynamic change of relevant parameters in the starting, running and stopping processes of the whole nuclear power unit.
The embodiment provides a method for simulating a primary circuit water pressure test of a nuclear power station, which is applied to a full-range simulator of the nuclear power station, and fig. 2 is a flow chart of the method for simulating the primary circuit water pressure test of the nuclear power station according to one embodiment of the application, as shown in fig. 2, and the flow chart comprises the following steps:
and S21, receiving a correction instruction, correcting the simulated hydrostatic test pump, and adjusting the flow of the corrected simulated hydrostatic test pump to a preset minimum flow.
Specifically, during an actual primary circuit hydrostatic test, the hydrostatic test pump is used to raise the primary circuit pressure to the highest test pressure. On a full-range simulator of a nuclear power plant, a hydrostatic test pump is used for simplifying the simulation, and is only a pump with constant flow. In the process of simulating the primary circuit water pressure test of the nuclear power station, when the primary circuit pressure reaches the highest test pressure, if the flow of the water pressure test pump continuously pressurizes the primary circuit water supply, the highest test pressure can be exceeded, so that the simulation test cannot be normally carried out.
According to the method, the simulation hydrostatic test pump of the existing simulator is corrected by the correction instruction through the logic operation tool of the simulator, so that the simulation hydrostatic test pump has the function of adjusting the flow to the preset minimum flow. When the circuit pressure reaches the highest test pressure, the flow of the hydrostatic test pump is adjusted to the preset minimum flow, and the preset minimum flow can compensate the normal pressure relief of the circuit, so that the circuit pressure is not continuously increased.
And S22, receiving an initial state adjustment instruction, and discharging the simulated core waste heat until the simulated core waste heat is smaller than a preset waste heat threshold.
Specifically, the actual primary loop hydraulic test requires the reactor to be in a discharge mode, however, the existing full-range simulator has no fuel-free mode, and the heat of the simulated reactor core causes the simulated primary loop temperature to increase through the simulated RRA (residual heat removal system), so that the simulated primary loop is abnormally increased, and the pressure range of the simulated primary loop hydraulic test is quickly exceeded. Therefore, before the simulated primary loop hydraulic test is developed, an initial state adjustment instruction is received and used for discharging the waste heat of the simulated reactor core, the waste heat of the simulated reactor core is reduced below a preset waste heat threshold value, and an initial state meeting the requirement of the simulated primary loop hydraulic test is established.
Step S23, receiving an operation instruction, and simulating a state of the primary circuit in the full-range simulator of the nuclear power station during the compaction based on the operation instruction.
Specifically, after finishing the correction of the hydrostatic test pump and establishing the initial state of the simulated primary circuit hydrostatic test, an operation instruction is received, wherein the operation instruction comprises the operation of a main pump, the hydrostatic test pump, an RRA (waste heat discharging system), an RCV (chemical and volume control system) and other simulated nuclear power systems, and is used for indicating a specific exercise step of the simulated primary circuit hydrostatic test, and the simulated primary circuit hydrostatic test is realized on a full-range simulator of the nuclear power plant.
S21-S23 are carried out, a correction instruction is received, the simulated hydrostatic test pump is corrected, and the corrected flow of the simulated hydrostatic test pump can be adjusted to be the preset minimum flow; receiving an initial state adjustment instruction, and discharging the simulated core waste heat until the simulated core waste heat is smaller than a preset waste heat threshold; and receiving an operation instruction, and simulating a state of the primary circuit in the full-range simulator of the nuclear power station during the compaction based on the operation instruction. According to the full-range simulation machine, the functions of the existing full-range simulation machine are expanded through correction of the simulated water pressure test pump and adjustment of the simulated core waste heat, and smooth implementation of the primary circuit water pressure test on the full-range simulation machine can be achieved.
In an embodiment, step S22: receiving an initial state adjustment instruction, and discharging the simulated core waste heat until the simulated core waste heat is smaller than a preset waste heat threshold, wherein the method specifically comprises the following steps:
step S221, receiving an initial state adjustment command, and adjusting the total core decay heat to the lower limit value of the full-range simulator, thereby reducing the fission product decay heat.
And step S222, operating the simulated RRA system to discharge the simulated core waste heat until the simulated core waste heat is smaller than a preset waste heat threshold.
Specifically, the waste heat of the simulated core includes three parts: 1) Delayed neutron cracking heat; 2) Decay heat of the fission product; 3) Sensible heat of the core. Because the number of delayed neutrons is small, the cracking heat of the delayed neutrons can be ignored in the range of tens of CPS; the largest proportion of the waste heat of the simulated core is decay heat of the fission products.
Regarding decay heat of the fission product, a corresponding variable (as shown in table 1 below) is found in the simulated core, and radhptt is adjusted to the lower limit of the full-range simulator, so that half-life of the fission product is reduced and decay heat of the fission product quickly approaches zero.
Table 1: analog reactor core variable meter
Core sensible heat may be carried out through an RRA (residual heat removal system). By increasing the power of RRA (waste heat removal system), the surplus heat of the reactor core is taken out as soon as possible. The preset waste heat threshold value is used for judging whether the simulated reactor core meets the requirement of the simulated primary circuit water pressure test, waste heat of the simulated reactor core is reduced through the operation until the waste heat of the simulated reactor core is smaller than the preset waste heat threshold value, and then the simulated reactor core is determined to meet the initial state of the reactor core required by the simulated primary circuit water pressure test.
Steps S221 to S222 described above reduce the fission product decay heat by adjusting the total core decay heat to the lower limit of the full-range simulator; and (3) discharging the simulated core waste heat by operating the simulated RRA (waste heat discharging system) until the simulated core waste heat is smaller than a preset waste heat threshold value, so that a core initial state meeting the requirement of the simulated primary circuit hydraulic test is established.
In an embodiment, step S23: receiving an operation instruction, and simulating a state of the primary circuit in the full-range simulator of the nuclear power station during water compaction based on the operation instruction, wherein the method specifically comprises the following steps of:
step S231, receiving an operation instruction, and adjusting and simulating the initial temperature of a loop to reach a target temperature;
specifically, by receiving the operation command, the initial temperature of the analog loop is adjusted to the target temperature. The simulated primary pump is started to simulate the temperature rise of a primary loop, the target temperature can be set to be 87+/-2 ℃, and the primary pump is stopped after the target temperature is reached; the initial problem of simulating a loop can also be set directly by a full-range simulator to a target temperature, which can be set to 89 ℃.
After simulating that the initial temperature of a loop reaches the target temperature, the passage between the RRA (waste heat removal system) and the loop system is isolated in consideration of the operation temperature limit of the RRA (waste heat removal system).
It should be noted that, when the method of heating up by using the simulated main pump is adopted, after the target temperature is reached, the main pump and the passage of the isolated RRA (waste heat discharging system) should be stopped at the same time, so as to ensure that the pressure of the primary circuit is stable and the temperature does not fluctuate.
Step S232, pressurizing a simulated primary circuit until the simulated primary circuit water pressure reaches a test water pressure target value;
specifically, after the initial temperature of the simulated primary circuit reaches the target temperature, the pressure of the simulated primary circuit is increased in order to simulate the primary circuit, and the primary circuit water pressure value is increased in a stepwise manner until the target water pressure value is tested.
In an embodiment, the step S232 specifically includes:
s2321, simulating loop pressurization by using a simulated RCV system until the simulated loop water pressure reaches a second water pressure target value;
specifically, the primary circuit is pressurized by simulating the up-and-down flow control in an RCV (chemical and volumetric control) system until the simulated primary circuit hydraulic pressure reaches a second hydraulic target value, which may be 16.5mpa.g.
S2322, the corrected simulated hydrostatic test pump is used for simulating loop pressurization until the simulated loop hydraulic pressure reaches the test hydraulic pressure target value.
After the simulated RCV (chemical and volume control) system is used to boost the simulated primary circuit water pressure to the second water pressure target value, the charge circuit and the normal bleed circuit in the simulated RCV (chemical and volume control) system are isolated and the excess bleed circuit in the simulated RCV (chemical and volume control) system is commissioned.
And (3) using the corrected simulated water pressure test pump, injecting water into the simulated primary circuit through the shaft seal until the simulated primary circuit water pressure reaches a test water pressure target value, wherein the test water pressure target value can be 20.6mpa.
Through steps S2321-S2322, the effect of simulating the primary circuit pressurization is achieved through the simulated RCV system and the corrected simulated hydrostatic test pump.
Step S233, when the simulated primary circuit water pressure reaches the target value of the test water pressure, the flow of the corrected simulated water pressure test pump is adjusted to the preset minimum flow, and the simulated primary circuit water pressure is stabilized to be the target value of the test water pressure;
specifically, when the simulated primary circuit water pressure reaches the test water pressure target value, the corrected simulated water pressure test pump flow is adjusted to the preset minimum flow, the preset minimum flow can compensate the normal pressure relief of the primary circuit, meanwhile, the primary circuit pressure cannot be caused to continuously rise, and at the moment, the simulated primary circuit water pressure is stabilized at the test water pressure target value.
Step S234, the circuit is depressurized until the simulated circuit water pressure reaches the first water pressure target value.
Specifically, after the operation of stabilizing the simulated primary circuit water pressure at the test water pressure target value is completed, the simulated primary circuit pressure reducing operation is started, and the simulated primary circuit water pressure is reduced to the first water pressure target value.
In an embodiment, the step S234 specifically includes:
s2341, stopping the corrected simulated hydraulic test pump, and simulating a loop to naturally reduce the pressure to a second hydraulic target value;
specifically, the simulated hydraulic test pump after shutdown correction gradually reduces the water pressure of the simulated first loop due to the normal pressure relief of the simulated first loop, and waits for the simulated first loop to naturally reduce the water pressure to a second water pressure target value, wherein the second water pressure target value can be 16.5mpa.
S2342, the simulated RCV system is operated to simulate a loop depressurization until the simulated loop hydraulic pressure reaches the first hydraulic pressure target value.
Specifically, after the simulation of the natural depressurization of the primary circuit to the second water pressure target value, the charging circuit and the normal discharging circuit in the simulated RCV (chemical and volume control) system are put into operation, the surplus discharging circuit in the simulated RCV (chemical and volume control) system is isolated, the pressure of the primary circuit is reduced by the simulated RCV (chemical and volume control) system until the simulated primary circuit water pressure reaches the first water pressure target value, which may be 2.7mpa.g.
After the simulated first-circuit water pressure reaches the first water pressure target value, a passage connected with an RRA (waste heat discharging system) is connected, and the simulated first-circuit water pressure test is ended.
Through steps S2341-S2342, the effect of simulating the primary circuit depressurization is achieved through the simulated RCV system and the corrected simulated hydrostatic test pump.
Step S231-S234, by receiving the operation instruction, adjusting and simulating the initial temperature of a loop to reach the target temperature; pressurizing the simulated primary circuit until the simulated primary circuit water pressure reaches a test water pressure target value; when the simulated primary circuit water pressure reaches the test water pressure target value, the corrected simulated water pressure test pump flow is adjusted to the preset minimum flow, and the simulated primary circuit water pressure is stabilized to be the test water pressure target value; in order to simulate the depressurization of the primary loop until the simulated primary loop water pressure reaches the first water pressure target value, the effect of simulating the state of the primary loop water compaction in the full-range simulator of the nuclear power station is realized.
In one embodiment, the simulated nuclear power plant primary circuit water pressure test method further comprises:
step S24, receiving a fault simulation instruction and simulating a fault scene;
step S25, a fault handling instruction is received, and an analog fault scene is handled.
Specifically, in the training process of the actual simulator, in order to strengthen the training and exercise effect, the instructor can randomly simulate abnormal working conditions, and the instructor is required to quickly control the primary loop pressure and stabilize. Tables 3 and 4 show some of the fault lists, and the faults listed in table 3 may be simulated when the simulated primary circuit water pressure reaches the test target value (the simulated primary circuit water pressure is highest and the working condition is worst), or may be performed at other stages of the simulated primary circuit water pressure test.
Further, for the faults in table 3, there is a preset corresponding fault handling list for the operator to operate, and the faults listed in table 4 are not operable by the preset corresponding fault handling list, so as to help test the reaction capability of the operator. By simulating the faults listed in table 4, the pressure change of a loop can be simulated through the exercise of a full-range simulator, the pressure curve data is recorded, and a corresponding plan is subsequently formulated.
Table 3: simulation drilling fault list for primary circuit water pressure test
| Abnormal shutdown of running charging pump |
| RCV leakage anomaly isolation |
| Often, the main variation is switched to auxiliary power supply |
| Abnormal opening of RCV046VP |
| RIS124VP is abnormally opened |
| Excess residual leakage loop anomaly isolation |
| Overvoltage protection signal action RIS011PO shutdown |
Table 4: expected fault list for primary circuit water pressure test simulation exercise
It should be noted that, in the process of simulating the primary circuit hydraulic test of the nuclear power station, other various faults and corresponding fault treatment sheets can be set, which is not limited in this application.
S24-S25, receiving a simulated fault instruction and simulating a fault scene; and receiving a fault handling instruction, and handling the simulated fault scene, so that the training effect of the simulated primary circuit hydraulic test can be better realized.
In one embodiment, the simulated nuclear power plant primary circuit water pressure test method further comprises:
and step S26, performing an overpressure protection action based on the overpressure protection logic and the simulated primary circuit water pressure, wherein the overpressure protection logic is used for indicating the simulated primary circuit water pressure alarm value and the overpressure protection action corresponding to the water pressure alarm value.
Specifically, in the process of simulating the primary circuit water pressure test, when the primary circuit water pressure reaches certain alarm values, the full-range simulation machine executes the overpressure protection action for alarming and prompting according to preset overpressure protection logic. Table 5 illustrates a part of the overpressure protection actions, and it should be noted that other multiple hydraulic pressure alarm values and corresponding overpressure protection actions may also be set during the simulation of the first-circuit hydraulic pressure test, which is not limited in this application.
Table 5: overpressure protection action
| Effective protection | Alarm value for water pressure | Related actions |
| RIS124VP off | 17.2MPA,21.1MPA | Automatic closing RIS124VP |
| In-situ 001LA lamp | 16.8MPA,20.74MPA | Temporary alarm |
| RIS011PO | 20.78MPA | Shut down pump cuts off power supply |
In an embodiment, step S26 further includes: and acquiring a state and an overpressure protection action during primary circuit water compaction in the full-range simulator of the nuclear power station, generating a simulation picture and displaying the simulation picture.
Specifically, the state and the overpressure protection action during the primary circuit hydraulic compaction in the full-range simulator of the nuclear power station are obtained, and the simulation picture of the primary circuit hydraulic test is designed and simulated by utilizing the logic operation tool of the simulator, so that the operation condition and the corresponding protection action of the primary circuit hydraulic test can be intuitively represented and simulated.
The following describes and illustrates the embodiments of the present application by way of preferred embodiments, and fig. 4 is a flow chart of a method of simulating a primary loop hydraulic test of a nuclear power plant in accordance with the preferred embodiments of the present application. As shown in fig. 4, the simulated nuclear power station primary circuit water pressure test method comprises the following steps:
step S401, receiving a correction instruction, correcting the simulated hydrostatic test pump, and adjusting the flow of the corrected simulated hydrostatic test pump to a preset minimum flow.
Step S402, receiving an initial state adjustment command, and adjusting the total core decay heat to the lower limit value of the full-range simulator, thereby reducing the fission product decay heat.
And S403, operating the simulated RRA system to discharge the simulated core waste heat until the simulated core waste heat is smaller than a waste heat threshold.
Step S404, receiving the operation command, and adjusting and simulating the initial temperature of a loop to reach the target temperature.
Starting a simulated main pump to simulate the temperature rise of a loop, setting the target temperature to be 87+/-2 ℃, and stopping the main pump after the target temperature is reached; or the initial problem of simulating a loop is directly set to be a target temperature by a full-range simulator, and the target temperature is set to be 89 ℃.
When the simulated loop temperature is less than 50 ℃, the temperature rising rate is less than or equal to 14 ℃/h; when the simulated primary loop temperature is greater than 50 ℃, the temperature rising rate is less than or equal to 28 ℃/h;
after the simulated-loop initial temperature reaches the target temperature, the path between the RRA (waste heat removal system) and the simulated-loop system is isolated.
If the method of simulating the main pump to raise the temperature is adopted, after the target temperature is reached, the main pump and the passage of the isolating RRA (waste heat discharging system) should be stopped at the same time so as to ensure that the pressure of a primary circuit is stable and the temperature has no fluctuation.
In step S405, the first bleed orifice plate of the normal bleed circuit of the simulated RCV (chemical and volume control) system is closed by pumping up the simulated primary circuit to 8MPa.
In the process of closing the first leakage orifice plate, the pressure stability of the simulation loop is ensured, and a simulator instructor can gradually close the manual isolation valve of the simulation leakage orifice plate according to the requirement of an operator (the recommended control closing time is about 8-10 minutes).
In step S406, the second down hole plate of the normal down hole loop of the simulated RCV (chemical and volume control) system is closed by pumping up the simulated primary loop to 10MPa.
The same requirement as the first down-leakage orifice plate is closed, and the pressure stability of the simulation loop is ensured in the process of closing the second down-leakage orifice plate.
In step S407, the simulated primary pump is started to raise the temperature of the simulated primary loop to the target temperature by pumping the simulated primary loop to raise the pressure to 14.5mpa.g in the simulated RCV (chemical and volume control) system, so as to ensure the stability of the simulated primary loop temperature.
Attention is paid to pressure control and attention to starting the simulated main pump when starting the simulated main pump
In step S408, the simulated primary pump is shut down by pumping up the simulated primary circuit to 15.4mpa.g in the simulated RCV (chemical and volumetric control) system.
When the simulation main pump is stopped, the pressure stability of the simulation primary loop is ensured;
step S409, the last down-hole plate is closed and put into operation through the left down-hole plate by pumping up the simulated primary circuit in the simulated RCV (chemical and volume control) system to boost the pressure to 16.5mpa.g, isolating the up-charge circuit and the normal down-hole circuit in the simulated RCV (chemical and volume control) system.
Because closing the last lower vent plate has a great influence on simulating the loop pressure, the field personnel and the master personnel are matched well. The instructor can gradually close the manual isolation valve of the simulated lower drain board according to the requirement of the operator, and the instructor can simulate communication failure with the main control during the period, the valve closing speed can be neglected, and the control of the pressure by the operator is practiced. Empirical values: the time required for closing the last lower drain board isolation valve on site is about 20 minutes, and the exercise can be controlled according to 10 minutes.
In step S410, the corrected simulated hydrostatic test pump is used for filling water into the simulated primary circuit through the shaft seal until the simulated primary circuit water pressure reaches 20.6mpa.g.
And S411, adjusting the flow of the corrected simulated hydrostatic test pump to a preset minimum flow, stably simulating the primary circuit water pressure to be 20.6mpa.g, and simulating different fault scenes.
The instructor simulates a fault scenario, requiring the operator to be able to quickly control and stabilize the loop pressure, the simulator may not be able to simulate pressures greater than 20mpa.g, in which case 19.9mpa.g is the highest pressure.
In step S412, the simulated hydrostatic test pump after the shutdown correction simulates a loop to naturally reduce the pressure to 16.5mpa.g.
In step S413, the charging circuit and the normal discharging circuit in the simulated RCV (chemical and volumetric control) system are put into operation, isolating the remaining discharging circuits.
Because the first lower drain hole plate of the normal drain loop is opened, the pressure of the analog primary loop is greatly affected, and the field personnel and the master personnel are matched well. The instructor can gradually open the manual isolation valve of the simulated lower drain board according to the requirement of the operator, and the instructor can simulate communication failure with the master control personnel during the period, so that the valve opening speed can be neglected, and the control of the pressure by the operator is practiced. Empirical values: the time required to open the last lower vent panel isolation valve in the field is about 20 minutes.
In step S414, the loop is depressurized by simulating the RCV system until the simulated loop water pressure reaches 2.7mpa.g. And (3) connecting a passage of the simulation RRA (waste heat discharge system), and ending the simulation primary circuit water pressure test.
It should be noted that the steps illustrated in the above-described flow or flow diagrams of the figures may be performed in a computer system, such as a set of computer-executable instructions, and that, although a logical order is illustrated in the flow diagrams, in some cases, the steps illustrated or described may be performed in an order other than that illustrated herein.
The embodiment also provides a primary circuit hydraulic test system for simulating the nuclear power station, which is applied to a full-range simulator of the nuclear power station, and the full-range simulator is used for simulating the operation of the nuclear power station. The system is used to implement the foregoing embodiments and preferred embodiments, and is not described in detail. The terms "module," "unit," "sub-unit," and the like as used below may refer to a combination of software and/or hardware that performs a predetermined function. While the system described in the following embodiments is preferably implemented in software, implementation of hardware, or a combination of software and hardware, is also possible and contemplated.
FIG. 5 is a schematic structural diagram of a loop hydraulic test system for simulating a nuclear power plant according to one embodiment of the present application, as shown in FIG. 5, the system comprising:
the test pump correction module 52 is configured to receive a correction instruction, correct the simulated hydraulic test pump, and adjust the flow of the corrected simulated hydraulic test pump to a preset minimum flow;
the initial state adjustment module 54 is configured to receive an initial state adjustment instruction, and discharge the simulated core waste heat until the simulated core waste heat is less than a preset waste heat threshold;
and an operation module 56, configured to receive an operation instruction, and simulate a state of the first circuit in the full-range simulator of the nuclear power plant during compaction based on the operation instruction.
In one embodiment, the initial state adjustment module 54 is configured to receive initial state adjustment instructions to adjust the total core decay heat to a lower limit of the full range simulator to reduce fission product decay heat; and operating the simulated RRA system to discharge the simulated core waste heat until the simulated core waste heat is smaller than a preset waste heat threshold.
In one embodiment, the operation module 56 is configured to receive an operation command, and adjust and simulate a loop initial temperature to reach a target temperature; pressurizing the simulated primary circuit until the simulated primary circuit water pressure reaches a test water pressure target value; when the simulated primary circuit water pressure reaches the test water pressure target value, the corrected simulated water pressure test pump flow is adjusted to the preset minimum flow, and the simulated primary circuit water pressure is stabilized to be the test water pressure target value; to simulate a circuit depressurization until the simulated circuit hydraulic pressure reaches a first hydraulic pressure target value.
In one embodiment, the operation module 56 is configured to simulate a circuit boost using the simulated RCV system until the simulated circuit hydraulic pressure reaches the second hydraulic pressure target value; and simulating the loop pressurization by using the corrected simulated hydrostatic test pump until the simulated loop hydraulic pressure reaches the test hydraulic pressure target value.
In one embodiment, the operation module 56 is configured to simulate the simulated hydrostatic test pump after the shutdown correction, and simulate a natural depressurization of a loop to a second hydrostatic target value; operating the simulated RCV system to simulate a loop depressurization until the simulated loop hydraulic pressure reaches the first hydraulic pressure target value
In an embodiment, further comprising:
the fault simulation module is used for receiving a fault simulation instruction and simulating a fault scene;
the fault handling module is used for receiving the fault handling instruction and handling the simulation fault scene.
In an embodiment, further comprising:
and the over-pressure protection module is used for executing over-pressure protection actions based on over-pressure protection logic and the simulated primary circuit water pressure, and the over-pressure protection logic is used for indicating the simulated primary circuit water pressure alarm value and the over-pressure protection actions corresponding to the water pressure alarm value.
In an embodiment, further comprising:
and the display module is used for acquiring the state of the primary circuit in the full-range simulator of the nuclear power station during the water compaction and the overpressure protection action, generating a simulation picture and displaying the simulation picture.
In one embodiment, a computer device is provided, comprising a memory and a processor, the memory having stored therein a computer program, the processor when executing the computer program performing the steps of any one of the above embodiments of the simulated nuclear power plant loop hydraulic test method.
Those skilled in the art will appreciate that implementing all or part of the above described methods may be accomplished by way of a computer program stored on a non-transitory computer readable storage medium, which when executed, may comprise the steps of the embodiments of the methods described above. Any reference to memory, storage, database, or other medium used in embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, or the like. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory. By way of illustration, and not limitation, RAM can be in the form of a variety of forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), and the like.
The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The above examples merely represent a few embodiments of the present application, which are described in more detail and are not to be construed as limiting the scope of the invention. It should be noted that it would be apparent to those skilled in the art that various modifications and improvements could be made without departing from the spirit of the present application, which would be within the scope of the present application. Accordingly, the scope of protection of the present application is to be determined by the claims appended hereto.
Claims (9)
1. A method for simulating a primary circuit water pressure test of a nuclear power plant, which is applied to a full-range simulator of the nuclear power plant, wherein the full-range simulator of the nuclear power plant is used for simulating the operation of the nuclear power plant, and is characterized by comprising the following steps:
receiving a correction instruction, correcting the simulated hydraulic test pump, and adjusting the flow of the corrected simulated hydraulic test pump to a preset minimum flow;
receiving an initial state adjustment instruction, and discharging the simulated core waste heat until the simulated core waste heat is smaller than a preset waste heat threshold;
receiving an operation instruction, and simulating a state of a primary circuit in the full-range simulator of the nuclear power station during water compaction based on the operation instruction;
the receiving the operation instruction, and based on the operation instruction, simulating the state of the first-circuit water compaction in the full-range simulator of the nuclear power station comprises:
receiving the operation instruction, and adjusting and simulating the initial temperature of a loop to reach the target temperature;
pressurizing the simulation primary loop until the simulation primary loop water pressure reaches a test water pressure target value;
when the simulated primary circuit water pressure reaches the test water pressure target value, adjusting the flow of the corrected simulated water pressure test pump to the preset minimum flow, and stabilizing the simulated primary circuit water pressure to the test water pressure target value;
and reducing the pressure of the analog primary circuit until the analog primary circuit water pressure reaches a first water pressure target value.
2. The method of testing the primary circuit water pressure of the simulated nuclear power plant according to claim 1, wherein the receiving the initial state adjustment command and discharging the simulated core waste heat until the simulated core waste heat is less than a preset waste heat threshold comprises:
receiving the initial state adjustment instruction, and adjusting the total reactor core decay heat to be the lower limit value of the full-range simulator so as to reduce the fission product decay heat;
and operating a simulated RRA system to discharge the simulated core waste heat until the simulated core waste heat is smaller than the preset waste heat threshold, wherein the RRA system is a waste heat discharge system.
3. A simulated nuclear power plant primary circuit hydraulic pressure testing method as claimed in claim 1, wherein said pressurizing said simulated primary circuit until said simulated primary circuit hydraulic pressure reaches a test hydraulic pressure target value comprises:
pressurizing the simulated primary circuit by using a simulated RCV system until the simulated primary circuit water pressure reaches a second water pressure target value, wherein the RCV system is a chemical and volume control system;
and pressurizing the simulated primary loop by using the corrected simulated hydrostatic test pump until the simulated primary loop hydraulic pressure reaches the test hydraulic pressure target value.
4. A simulated nuclear power plant primary circuit hydraulic pressure testing method as claimed in claim 1, wherein said depressurizing said simulated primary circuit until said simulated primary circuit hydraulic pressure reaches a first hydraulic pressure target value comprises:
stopping the corrected simulated hydraulic test pump, and naturally reducing the pressure of the simulated primary loop to a second hydraulic target value;
operating a simulated RCV system to depressurize the simulated primary circuit until the simulated primary circuit water pressure reaches the first water pressure target value, wherein the RCV system is a chemical and volumetric control system.
5. A simulated nuclear power plant primary circuit water pressure testing method as claimed in claim 1, said method further comprising:
receiving a fault simulation instruction and simulating a fault scene;
and receiving a fault handling instruction, and handling the simulated fault scene.
6. A simulated nuclear power plant primary circuit water pressure testing method as claimed in claim 1, said method further comprising:
and performing an overpressure protection action based on the overpressure protection logic and the simulated primary circuit water pressure, wherein the overpressure protection logic is used for indicating the simulated primary circuit water pressure alarm value and the overpressure protection action corresponding to the water pressure alarm value.
7. A simulated nuclear power plant primary circuit water pressure testing method as claimed in claim 6, said method further comprising:
and acquiring a state and an overpressure protection action during primary circuit water compaction in the full-range simulator of the nuclear power station, generating a simulation picture and displaying the simulation picture.
8. A loop hydraulic test system for simulating a nuclear power plant, which is applied to a full-range simulator of the nuclear power plant, wherein the full-range simulator is used for simulating the operation of the nuclear power plant, and the loop hydraulic test system is characterized by comprising:
test pump correction module: the device is used for receiving a correction instruction, correcting the simulated hydrostatic test pump, and adjusting the flow of the corrected simulated hydrostatic test pump to a preset minimum flow;
the initial state adjustment module: the device is used for receiving the initial state adjustment instruction, and discharging the simulated reactor core waste heat until the simulated reactor core waste heat is smaller than a preset waste heat threshold;
and an operation module: the system is used for receiving an operation instruction, and simulating a state of a primary circuit in the full-range simulator of the nuclear power station during water compaction based on the operation instruction;
the operation module is specifically used for receiving the operation instruction and adjusting and simulating the initial temperature of a loop to reach the target temperature; pressurizing the simulation primary loop until the simulation primary loop water pressure reaches a test water pressure target value; when the simulated primary circuit water pressure reaches the test water pressure target value, adjusting the flow of the corrected simulated water pressure test pump to the preset minimum flow, and stabilizing the simulated primary circuit water pressure to the test water pressure target value; and reducing the pressure of the analog primary circuit until the analog primary circuit water pressure reaches a first water pressure target value.
9. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor, when executing the computer program, implements the steps of the method of any of claims 1 to 7.
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