CN211375848U - Control training device of nuclear power station system - Google Patents
Control training device of nuclear power station system Download PDFInfo
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- CN211375848U CN211375848U CN201922139323.XU CN201922139323U CN211375848U CN 211375848 U CN211375848 U CN 211375848U CN 201922139323 U CN201922139323 U CN 201922139323U CN 211375848 U CN211375848 U CN 211375848U
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Abstract
The application discloses control trainer of nuclear power station system, including nuclear power station analog system, wherein, nuclear power station analog system includes: the system comprises a spent fuel pool, at least one cooling loop connected with the spent fuel pool, a pressure gauge arranged on the cooling loop, a purification loop connected with the spent fuel pool and a water tank connected with the spent fuel pool; after the control equipment generates the forcing signal, when the field equipment in the nuclear power plant simulation system is maintained, the working state of the field equipment in the control equipment is locked, and the normal work of the actual nuclear power plant system cannot be influenced by the change of the working state of the field equipment. Because the nuclear power station simulation system different from the actual nuclear power station system is constructed, after the forced signal is generated on the control equipment, the operation of the field equipment can not influence the normal work of the actual nuclear power station system, and therefore the simulated nuclear power station simulation system can be combined with the working scene of the simulated nuclear power station system to train the behavior specifications of technicians.
Description
Technical Field
The utility model belongs to the nuclear power station field especially relates to a control trainer of nuclear power station system.
Background
Human errors are an important factor threatening the safety of nuclear power plant systems, and the proportion of events caused by human errors in a nuclear power plant exceeds 85%. According to the nuclear power plant management regulations, a set of strict behavior specifications should be observed in the field working process to avoid the occurrence of signal forcing errors, wrong-going intervals and other events.
In order to enable technicians to comply with established behavior norms when operating a nuclear power plant system, and therefore avoid occurrence of events such as industrial safety, misoperation, wrong interval and the like, the technicians need to be trained in the behavior norms.
Because the nuclear power station system cannot be operated at will in the normal operation process, in the training process of behavior specifications of technical personnel, the technical personnel can only be trained according to the established behavior specifications and cannot be combined with the scene of the actual nuclear power station system, so that the behavior specifications are difficult to convert and apply to the actual scene even if being learned, and the training effect of the behavior specifications is reduced. Technical personnel are difficult to apply behavior specifications to meet requirements of the technical personnel in actual working scenes, and the probability of human errors of the nuclear power station system is improved.
SUMMERY OF THE UTILITY MODEL
In view of this, the utility model aims at providing a control trainer of nuclear power station system to overcome and to have now can not combine actual scene to carry out the problem that is difficult to practice the transformation of action standard to actual scene that the action standard training leads to the technical staff, improve the nuclear power station system and have the probability of human error.
Therefore, the utility model discloses a following technical scheme:
a control training apparatus for a nuclear power plant system, comprising:
a nuclear power plant simulation system; wherein, nuclear power station analog system includes: the system comprises a spent fuel pool, at least one cooling loop connected with the spent fuel pool, a pressure gauge arranged on the cooling loop, a purification loop connected with the spent fuel pool and a water tank connected with the spent fuel pool;
the control equipment is connected with the nuclear power station simulation system; the control device is configured to generate a forcing signal.
The above apparatus, preferably, the cooling circuit includes:
a heat exchange model;
the first end of the heat exchange model is connected with the first end of the cooling pump;
the second end of the heat exchange model is connected with the input end of the spent fuel pool;
the second end of the cooling pump is connected with the first end of the manual valve;
the second end of the manual valve is connected with the first end of the electric valve;
and the second end of the electric valve is connected with the output end of the spent fuel pool.
In the above apparatus, preferably, two pressure gauges are provided on each cooling circuit;
the input end of the first pressure gauge is connected with the first end of the manual valve and the second end of the cooling pump respectively;
and the input end of the second pressure gauge is connected with the first end of the cooling pump.
The above apparatus, preferably, further comprises:
a pressure switch;
the pressure switch is connected with the input end of the first pressure gauge.
The above apparatus, preferably, further comprises:
the control power box is respectively connected with the cooling loop and the purification loop; the control power box is internally provided with a terminal strip and a wiring, wherein the wiring is respectively connected with the cooling loop and the purification loop.
To sum up, the utility model discloses a control trainer of nuclear power station system, including the nuclear power station analog system, wherein, the nuclear power station analog system includes: the system comprises a spent fuel pool, at least one cooling loop connected with the spent fuel pool, a pressure gauge arranged on the cooling loop, a purification loop connected with the spent fuel pool and a water tank connected with the spent fuel pool; after the control equipment generates the forcing signal, when the field equipment in the nuclear power plant simulation system is maintained, the working state of the field equipment in the control equipment is locked, and the normal work of the actual nuclear power plant system cannot be influenced by the change of the working state of the field equipment. Because a nuclear power station simulation system different from an actual nuclear power station system is constructed, after a forcing signal is generated on control equipment, the operation of field equipment cannot influence the normal work of the actual nuclear power station system, so that the training of behavior specifications can be carried out on technicians by combining the simulated working scene of the nuclear power station system, the technicians can apply the learned behavior specifications to the actual working scene, and the probability of events of the nuclear power station system caused by human errors is reduced.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings required to be used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the provided drawings without creative efforts.
Fig. 1 is a schematic structural diagram of a control training device of a nuclear power plant system according to an embodiment of the present invention;
fig. 2 is a schematic structural diagram of a nuclear power station simulation system in a control training device of a nuclear power station system disclosed in the second embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be described clearly and completely with reference to the accompanying drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative work belong to the protection scope of the present invention.
Example one
The embodiment of the utility model discloses a control training device of a nuclear power station system, referring to fig. 1, the control training device of the nuclear power station system comprises a nuclear power station simulation system 1;
the nuclear power plant simulation system 1 includes: the system comprises a spent fuel pool 11, at least one cooling loop 12 connected with the spent fuel pool, a pressure gauge LP arranged on the cooling loop, a purification loop 13 connected with the spent fuel pool and a water tank 14 connected with the spent fuel pool;
a control device 2 connected to the nuclear power plant simulation system 1; the control device 2 is used to generate the forcing signal.
In this embodiment, the control device 2 provides a user interaction interface, which is the same as a user interaction interface in an actual nuclear power plant system, and the user interaction interface displays an association control relationship between each component device on the nuclear power plant simulation system 1, a control relationship of each component inside each device, and a signal display capable of indicating a current state of each device.
In the maintenance work, in order to avoid the change of the equipment working state caused by operating the nuclear power station simulation system 1, the corresponding protection logic action is generated through the control equipment 2, and the normal operation of the whole nuclear power station system is further influenced. Before maintenance work, a user can operate and generate a forcing signal corresponding to a field device in the nuclear power plant simulation system through a user interaction interface provided by the control device 2, lock the working state of the field device in the nuclear power plant simulation system 1 in the control device 2, and then perform operation or maintenance on the field device. Because the working state of the field device is locked, the working state of the field device is not changed due to field operation, and the control device 2 is prevented from generating protection logic actions by mistake.
Compared with the training process of the specific implementation mode for executing the forced operation on the technical staff in the prior art, in order to avoid influencing the normal operation of the nuclear power plant system, a real forced signal to the field equipment of the nuclear power plant system cannot be generated, so that the technical staff cannot operate in actual combat, and the problem of wrong interval is easy to occur.
In this embodiment, the control device 2 may train a technician in an instrumentation and control professional to perform a specific implementation manner of the forced operation, generate a simulated forced signal by using the user interaction interface provided by the control device 2, and after the forced signal is generated for the field device, even if the working state of the field device changes, the working state of the field device in the control device 2 remains unchanged. The influence on the working state of the field equipment when the field equipment is operated is avoided, so that the working state of the field equipment in the control equipment 2 is changed along with the influence on the normal operation of the whole nuclear power station system.
After the forced signal is generated, no influence is caused on the actual operation of the nuclear power station system, and the problem of wrong interval in the subsequent actual working process can be avoided because technicians can operate in actual combat.
To sum up, the control training device of nuclear power station system that this application discloses, including the nuclear power station analog system, wherein, the nuclear power station analog system includes: the system comprises a spent fuel pool, at least one cooling loop connected with the spent fuel pool, a pressure gauge arranged on the cooling loop, a purification loop connected with the spent fuel pool and a water tank connected with the spent fuel pool; after the control equipment generates the forcing signal, when the field equipment in the nuclear power plant simulation system is maintained, the working state of the field equipment in the control equipment is locked, and the normal work of the actual nuclear power plant system cannot be influenced by the change of the working state of the field equipment. Because a nuclear power station simulation system different from an actual nuclear power station system is constructed, after a forcing signal is generated on control equipment, the operation of field equipment cannot influence the normal work of the actual nuclear power station system, so that the training of behavior specifications can be carried out on technicians by combining the simulated working scene of the nuclear power station system, the technicians can apply the learned behavior specifications to the actual working scene, and the probability of events of the nuclear power station system caused by human errors is reduced.
Example two
Referring to fig. 2, in the second embodiment, the nuclear power plant simulation system for controlling the training apparatus includes three cooling circuits, each cooling circuit includes:
a heat exchange model;
the first end of the heat exchange model is connected with the first end of the cooling pump;
the second end of the heat exchange model is connected with the input end of the spent fuel pool;
the second end of the cooling pump is connected with the first end of the manual valve;
the second end of the manual valve is connected with the first end of the electric valve;
and the second end of the electric valve is connected with the output end of the spent fuel pool.
Specifically, referring to fig. 2, a schematic structural diagram of the nuclear power plant simulation system 1 in the present embodiment is shown;
the system comprises three cooling loops which are arranged in parallel, wherein the first cooling loop comprises a manual butterfly valve 003VB, a cooling pump 001PO, a check valve 005VB, a manual butterfly valve 007VB, a manual gate valve 009VB and a heat exchange model 001RF which are sequentially connected, wherein the heat exchange model is called as a heat exchanger in an actual nuclear power station system; the second cooling loop comprises a manual butterfly valve 002VB, a cooling pump 002PO, a check valve 004VB, a manual butterfly valve 006VB, a manual gate valve 008VB and a heat exchange model 002RF which are connected in sequence; the third cooling loop includes a manual butterfly valve 023VB, a cooling pump 006PO, a check valve 912VB, a manual butterfly valve 913VB, a manual gate valve 918VB and a heat exchange model 003RF connected in sequence.
Manual butterfly valves connected with inlet ends of the cooling pump 001PO, the cooling pump 002PO and the cooling pump 006PO are connected in parallel in the three cooling loops and connected with an electric gate valve 165VB, and a manual butterfly valve 018VB is connected between the manual butterfly valve 007VB in the first cooling loop and the manual butterfly valve 006VB in the second cooling loop; and a manual butterfly valve 920VB is connected between the manual butterfly valve 007VB in the first cooling circuit and the manual butterfly valve 913VB in the third cooling circuit.
Each cooling loop is provided with two pressure gauges, wherein the pressure gauges are local pressure gauges. Wherein, the manometer is the manometer of different models.
A pressure gauge 029LP is connected between the manual butterfly valve 003VB and the cooling pump 001PO on the first cooling loop, and the input end of the pressure gauge 029LP is respectively connected with the first end of the manual butterfly valve 003VB and the second end of the cooling pump 001 PO; another pressure gauge 031LP is connected between the cooling pump 001PO and the check valve 005VB, and an input end of the pressure gauge 031LP is connected with a first end of the cooling pump 001PO and one end of the check valve 005VB connected with the cooling pump 001PO respectively; a pressure switch 027SP can be further arranged between the manual butterfly valve 003VB and the cooling pump 001PO, and one end of the pressure switch 027SP is respectively connected with the first end of the manual butterfly valve 003VB and the second end of the cooling pump 001 PO;
a pressure gauge 030LP is connected between the manual butterfly valve 002VB and the cooling pump 002PO on the second cooling loop, and the input end of the pressure gauge 030LP is respectively connected with the first end of the manual butterfly valve 002VB and the second end of the cooling pump 002 PO; another pressure gauge 032LP is connected between the cooling pump 002PO and the check valve 004VB, and the input end of the pressure gauge 032LP is respectively connected with the first end of the cooling pump 002PO and one end of the check valve 004VB, which is connected with the cooling pump 002 PO; wherein, a pressure switch 028SP can be arranged between the manual butterfly valve 002VB and the cooling pump 002PO, and one end of the pressure switch 028SP is respectively connected with the first end of the manual butterfly valve 002VB and the second end of the cooling pump 002 PO;
a pressure gauge 039LP is connected between the manual butterfly valve 023VB and the cooling pump 006PO on the third cooling loop, and the input end of the pressure gauge 039LP is respectively connected with the first end of the manual butterfly valve 023VB and the second end of the cooling pump 006 PO; another pressure gauge 041LP is connected between the cooling pump 006PO and the check valve 912VB, and an input end of the pressure gauge 041LP is respectively connected with the first end of the cooling pump 006PO and one end of the check valve 912VB connected with the cooling pump 006 PO; wherein, can also set up pressure switch 040SP between manual butterfly valve 023VB and cooling pump 006PO, pressure switch 040 SP's one end respectively with manual butterfly valve 023 VB's first end, the second end of cooling pump 006PO is connected.
In this embodiment, through set up pressure switch and manometer respectively on three cooling circuit on the nuclear power station analog system, after generating the compulsory signal through controlgear 2, even operating pressure switch and manometer, the operating condition of pressure switch and manometer can not change among the controlgear 2, utilizes to suppress equipment and checks the pressure switch and the manometer that set up on the nuclear power station analog system to training technical staff standardizes the action of check-up operation. And the normal work of the actual nuclear power station system is not influenced.
Optionally, in this embodiment, the control training device further includes:
the control power box is respectively connected with the cooling loop and the purification loop; the control power box is internally provided with a terminal strip and a wiring, wherein the wiring is respectively connected with the cooling circuit and the purification circuit and used for supplying power to each connected device.
Through setting up the control power supply box and setting up terminal row and wiring in the control power supply box, can have corresponding training of realizing the operation of taking out stitches to the technical staff of instrument control, electrical profession, for example the training of taking out stitches skill and relation of connection. Training from preparation of a work document to execution on site is achieved.
By utilizing the control training device disclosed by the embodiment, typical operations executed by instrument control professionals in an actual nuclear power station system are simulated, for example, a forcing signal is generated, instruments such as a pressure gauge and the like are verified after the forcing signal is generated, and the disconnection operation of the wiring of each field device is realized, so that the training of behavior specifications of the instrument control professionals is realized, and the human errors such as disconnection errors, forcing signal errors and wrong interval intervals in instrument control are avoided.
By using the control training device disclosed by the embodiment, the actual working process of the nuclear power station is combined, and complete behavior specification training is carried out, including the training of contents such as ticket taking, meeting before work, using procedures, three-section type communication, monitoring operation, star self-checking, questioning attitude, mistake-proofing interval, mistake-proofing collision-proofing, foreign matter proofing, professional operation and the like.
The embodiments in the present specification are described in a progressive manner, each embodiment focuses on differences from other embodiments, and the same and similar parts among the embodiments are referred to each other.
The foregoing is only a preferred embodiment of the present invention, and it should be noted that, for those skilled in the art, a plurality of modifications and decorations can be made without departing from the principle of the present invention, and these modifications and decorations should also be regarded as the protection scope of the present invention.
Claims (5)
1. A control training device for a nuclear power plant system, comprising:
a nuclear power plant simulation system; wherein, nuclear power station analog system includes: the system comprises a spent fuel pool, at least one cooling loop connected with the spent fuel pool, a pressure gauge arranged on the cooling loop, a purification loop connected with the spent fuel pool and a water tank connected with the spent fuel pool;
the control equipment is connected with the nuclear power station simulation system; the control device is configured to generate a forcing signal.
2. The control training device of claim 1, wherein the cooling circuit comprises:
a heat exchange model;
the first end of the heat exchange model is connected with the first end of the cooling pump;
the second end of the heat exchange model is connected with the input end of the spent fuel pool;
the second end of the cooling pump is connected with the first end of the manual valve;
the second end of the manual valve is connected with the first end of the electric valve;
and the second end of the electric valve is connected with the output end of the spent fuel pool.
3. The control training device according to claim 2, wherein two pressure gauges are provided on each cooling circuit;
the input end of the first pressure gauge is connected with the first end of the manual valve and the second end of the cooling pump respectively;
and the input end of the second pressure gauge is connected with the first end of the cooling pump.
4. The control training device according to claim 3, further comprising:
a pressure switch;
the pressure switch is connected with the input end of the first pressure gauge.
5. The control training device according to claim 4, further comprising:
the control power box is respectively connected with the cooling loop and the purification loop; the control power box is internally provided with a terminal strip and a wiring, wherein the wiring is respectively connected with the cooling loop and the purification loop.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201922139323.XU CN211375848U (en) | 2019-12-03 | 2019-12-03 | Control training device of nuclear power station system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201922139323.XU CN211375848U (en) | 2019-12-03 | 2019-12-03 | Control training device of nuclear power station system |
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| CN211375848U true CN211375848U (en) | 2020-08-28 |
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| CN201922139323.XU Active CN211375848U (en) | 2019-12-03 | 2019-12-03 | Control training device of nuclear power station system |
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