CN114242274A - Protection system - Google Patents
Protection system Download PDFInfo
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- CN114242274A CN114242274A CN202111370526.5A CN202111370526A CN114242274A CN 114242274 A CN114242274 A CN 114242274A CN 202111370526 A CN202111370526 A CN 202111370526A CN 114242274 A CN114242274 A CN 114242274A
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- 238000001514 detection method Methods 0.000 claims abstract description 42
- 238000007781 pre-processing Methods 0.000 claims abstract description 30
- 230000004907 flux Effects 0.000 claims abstract description 20
- 238000005259 measurement Methods 0.000 claims abstract description 14
- 238000000034 method Methods 0.000 claims abstract description 14
- 230000008569 process Effects 0.000 claims abstract description 14
- 230000005540 biological transmission Effects 0.000 claims description 21
- 230000003287 optical effect Effects 0.000 claims description 13
- 238000004891 communication Methods 0.000 claims description 10
- 238000004364 calculation method Methods 0.000 claims description 9
- 238000001914 filtration Methods 0.000 claims description 9
- 238000004519 manufacturing process Methods 0.000 abstract description 5
- 238000012423 maintenance Methods 0.000 abstract description 4
- 239000013307 optical fiber Substances 0.000 description 3
- 230000008439 repair process Effects 0.000 description 3
- 230000008901 benefit Effects 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000007246 mechanism Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000005192 partition Methods 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 238000000638 solvent extraction Methods 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000005856 abnormality Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000012937 correction Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000003111 delayed effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/36—Control circuits
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/108—Measuring reactor flux
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
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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 relates to a protection system for DNBR/LPD protection of a reactor, comprising: the preprocessing cabinet is used for preprocessing detection signals of the neutron flux detectors and generating detection output information; the upper computer is used for periodically generating calibration state reactor core state information according to the detection output information received from the pretreatment cabinet and the measurement information of the primary and secondary loop process instrument received from the nuclear power plant DCS; the lower computer is used for generating a DNBR/LPD protection signal according to the detection output information received from the pretreatment cabinet, the measurement information of the primary and secondary loop process instrument received from the nuclear power plant DCS system and the calibration state core state information periodically received from the upper computer; the pretreatment equipment cabinet and the lower computer are respectively safety-level equipment, and the upper computer is non-safety-level equipment. By implementing the technical scheme of the invention, the daily maintenance and the daily maintenance of the equipment are more convenient, and the manufacturing cost of the protection system and the difficulty of safe examination and passing are reduced.
Description
Technical Field
The invention relates to the field of nuclear power design, in particular to a protection system.
Background
In order to ensure the safety of the reactor, the maximum heat flux density of the surface of the fuel assembly is required to be less than the critical heat flux density in the design, so that DNBR (Departure from nuclear Boiling Ratio) is introduced. Meanwhile, to avoid the core Linear Power Density from being too high, LPD (Linear Power Density) was introduced.
At present, when DNBR and LPD protection functions are realized, processing of detection signals, calculation of intermediate signals and generation of protection signals are all performed in one cabinet device, so that the cabinet device is large in size and complex in structure, and inconvenient to daily repair and maintain, and the cabinet device is connected with a neutron flux detector and a nuclear power plant DCS (Distributed Control System) so that the requirement on safety level is high (belonging to safety level devices), so that the manufacturing cost of the cabinet device is greatly increased, and the difficulty of passing safety examination of the device is also improved.
Disclosure of Invention
The invention aims to solve the technical problem of providing a protection system aiming at the defects of large volume, complex structure and high manufacturing cost in the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows: constructing a protection system for DNBR/LPD protection of a reactor comprising:
the pretreatment cabinet is connected with the neutron flux detectors and is used for pretreating detection signals of the neutron flux detectors and generating detection output information;
the upper computer is connected with the pretreatment machine cabinet and the nuclear power plant DCS and is used for periodically generating calibration state reactor core state information according to the detection output information received from the pretreatment machine cabinet and the measurement information of the primary and secondary loop process instrument received from the nuclear power plant DCS;
the lower computer is used for generating a DNBR/LPD protection signal according to the detection output information received from the pretreatment cabinet, the measurement information of a secondary loop process instrument received from the nuclear power plant DCS system and the calibration state core state information periodically received from the upper computer;
the pretreatment equipment cabinet and the lower computer are respectively security level equipment, and the upper computer is non-security level equipment.
Preferably, the number of the upper computers is two, and the two upper computers are mutually hot standby.
Preferably, the number of the pretreatment cabinets is multiple, and the multiple pretreatment cabinets are arranged in a partitioning mode independently.
Preferably, the number of the pretreatment cabinets is four, and each pretreatment cabinet is connected with 10 or 11 neutron flux detectors.
Preferably, the upper computer comprises a first DVD read-write optical drive and/or a first USB interface, and is used for periodically writing the generated calibration state core state information into the placed optical disc and/or the inserted USB disk;
the lower computer comprises a second DVD read-write optical drive and/or a second USB interface and is used for regularly reading the calibration state reactor core state information from the placed optical disk and/or the inserted U disk.
Preferably, a pluggable transmission line is connected between the lower computer and the upper computer, and when the calibration state reactor core state information needs to be transmitted, the transmission line between the lower computer and the upper computer is in a connection state; and when the calibration state core state information does not need to be transmitted, the transmission line between the lower computer and the upper computer is in a disconnected state.
Preferably, the lower computer is connected with the nuclear power plant DCS system and the pretreatment cabinet through hard wiring respectively.
Preferably, the preprocessing cabinet comprises:
the acquisition module is used for acquiring detection signals of the neutron flux detectors in real time;
the filtering module is connected with the acquisition module and is used for filtering invalid signals in the acquired signals;
the compensation module is connected with the filtering module and is used for carrying out delay compensation on the acquired signal after the invalid signal is filtered;
the calculation module is connected with the compensation module and is used for calculating the accumulated charge of the electrode current of the signal after the delay compensation;
the state generating module is used for generating a state signal according to the current running state of the software and hardware;
and the transmission module is connected with the acquisition module, the compensation module, the calculation module and the state generation module and is used for generating detection output information according to the acquisition signal, the delay compensation signal, the accumulated charge and the state signal and transmitting the detection output information.
Preferably, the transmission module is a network communication module, and the preprocessing cabinet is connected with the upper computer through a communication network.
Preferably, the lower computer comprises:
the output module is used for outputting the detection output information received from the preprocessing cabinet;
the alarm module is used for giving an alarm when judging the abnormity according to the detection output information;
and the protection module is used for generating a DNBR/LPD protection signal according to the detection output information received from the pretreatment cabinet, the measurement information of a secondary loop process instrument received from the nuclear power plant DCS system and the calibration state core state information periodically received from the upper computer.
In the technical scheme provided by the invention, the protection system for realizing the DNBR/LPD protection function of the reactor is reasonably divided into the following functions: a preprocessor cabinet for preprocessing the detection signal; the upper computer is used for calculating the intermediate signal; the lower computer which generates the protection signal is more convenient for daily maintenance and repair of the equipment, and the manufacturing cost of the protection system and the difficulty of safe examination and passing are reduced because the pretreatment cabinet and the lower computer are safe-level equipment and the upper computer is non-safe-level equipment.
Drawings
In order to illustrate the embodiments of the invention more clearly, the drawings that are needed in the description of the embodiments will be briefly described below, it being apparent that the drawings in the following description are only some embodiments of the invention, and that other drawings may be derived from those drawings by a person skilled in the art without inventive effort. In the drawings:
fig. 1 is a logical structure diagram of a first embodiment of the protection system of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Fig. 1 is a logical structure diagram of a protection system 100 according to a first embodiment of the present invention, which is used for DNBR/LPD protection of a reactor and is connected to a nuclear power plant DCS system, wherein the nuclear power plant DCS system is connected to a control rod drive mechanism for implementing a reactor shutdown function, and is a safety level device, and in addition, it can provide measurement information of a two-loop process instrument, such as a main pump rotation speed, a cold leg temperature, a regulator pressure, a power signal, a control rod position, and the like.
Referring to fig. 1, the protection system 100 of this embodiment includes: the preprocessing unit 10, the upper computer 20 and the lower computer 30, wherein the preprocessing unit 10 is connected to the neutron flux detectors, and is configured to preprocess the detection signals of the neutron flux detectors and generate detection output information, and the detection output information includes: signal pole current, compensation pole current, cabinet state, accumulated charge, SPND state signal, etc.; the host computer 20 is connected with the pretreatment cabinet 10 and the nuclear power plant DCS system respectively, and is used for regularly generating calibration state reactor core state information according to the detection output information received from the pretreatment cabinet 10 and the measurement information of the secondary loop process instrument received from the nuclear power plant DCS system, wherein the measurement information of the secondary loop process instrument comprises: the rotating speed of the main pump, the temperature of a cold section, the pressure of a voltage stabilizer, a power signal, the position of a control rod and the like; the lower computer 30 is used for generating DNBR/LPD protection signals according to the detection output information received from the pretreatment machine cabinet 10, the measurement information of a secondary loop process instrument received from the nuclear power plant DCS system and the calibration state reactor core state information periodically received from the upper computer, and the DNBR/LPD protection signals are sent to the control rod driving mechanism through the nuclear power plant DCS system and used for realizing shutdown control. The preprocessing unit 10 and the lower unit 30 are security level devices, and the upper unit 20 is a non-security level device.
In the technical scheme of the embodiment, the protection system for realizing the DNBR/LPD protection function of the reactor is divided into the following reasonable functions: a pretreatment cabinet for preprocessing the detection signal; the upper computer is used for calculating the intermediate signal; the lower computer which generates the protection signal is more convenient for daily maintenance and repair of the equipment, and the manufacturing cost of the protection system and the difficulty of safe examination and passing are reduced because the pretreatment cabinet and the lower computer are safe-level equipment and the upper computer is non-safe-level equipment.
Further, in an optional embodiment, the number of the upper computers is two, and the two upper computers are mutually in hot standby. Specifically, the upper computer receives detection output information (including variables such as signal pole current, compensation pole current, cabinet state and accumulated charge) from the pretreatment cabinet, receives measurement information of a two-loop process instrument from the nuclear power plant DCS system, realizes functions such as core flux map calculation and burnup correction coefficient calculation, and provides calibration state core state information required by a protection algorithm for the lower computer at regular intervals (for example, 7 days).
Furthermore, the number of the pretreatment cabinets is multiple, and the multiple pretreatment cabinets are arranged in a partitioning mode independently. In a specific embodiment, the number of the preprocessing cabinets is four, each preprocessing cabinet is connected with 10 or 11 neutron flux detectors, specifically, the preprocessing cabinets are arranged in 4 independent electrical partitions, each independent electrical partition comprises one preprocessing cabinet, each preprocessing cabinet collects 10 or 11 SPND current signals of the neutron flux detectors, and after preprocessing, the signals are respectively output to an upper computer and a lower computer.
In one embodiment, the preprocessing cabinet comprises, connected in sequence: the neutron flux monitoring system comprises an acquisition module, a filtering module, a compensation module, a calculation module, a state generation module and a transmission module, wherein the acquisition module is used for acquiring detection signals of a plurality of neutron flux detectors in real time; the filtering module is used for filtering invalid signals in the acquired signals; the compensation module is used for carrying out time delay compensation on the acquired signal after the invalid signal is filtered; the calculation module is used for calculating the accumulated charge of the electrode current of the signal after the delay compensation; the state generating module is used for generating a state signal according to the current running state of the software and hardware of the state generating module; and the transmission module is used for generating detection output information according to the acquisition signal, the delay compensation signal, the accumulated charge and the state signal and transmitting the detection output information.
In this embodiment, the pre-processing of the detection signal of neutron flux is carried out in a pre-processing cabinet. The preprocessing cabinet conditions and collects the detection signals, removes invalid signals and then carries out delay compensation on the signals through a delay compensation algorithm. The preprocessor cabinet also calculates the accumulated charge of the pole current of the signal after the delay compensation. In addition, the preprocessing cabinet also outputs a state signal for representing whether the signal preprocessing channel fails or not, and the failure needs to represent the fault of the signal acquisition loop and the influence of the fault of the cabinet software and hardware.
In a specific embodiment, the lower computer comprises an output module, an alarm module and a protection module, wherein the output module is used for outputting the detection output information received from the preprocessing cabinet; the alarm module is used for alarming when the abnormality is judged according to the detection output information; the protection module is used for generating a DNBR/LPD protection signal according to the detection output information received from the pretreatment equipment cabinet, the measurement information of a secondary loop process instrument received from the nuclear power plant DCS system and the calibration state core state information periodically received from the upper computer, specifically, after the periodically updated calibration state core state parameters are obtained from the upper computer, the power distribution of the core is reconstructed through a power mapping algorithm by combining the calibration state core state parameters and the signals and the state signals after delay processing, the maximum LPD value and the minimum DNBR value of the core are calculated in real time according to the reconstructed core power distribution, and then the LPD and DNBR protection functions are realized by combining the LPD setting value and the DNBR setting value.
In this embodiment, the lower computer receives the delayed signal and the status signal from the preprocessing cabinet, and can identify and alarm the abnormal signal, and finally, the operator manually judges whether the detection signal is valid and manually updates the status signal.
In one embodiment, the transmission module of the preprocessing cabinet is a network communication module, and the preprocessing cabinet is connected with the upper computer through a communication network, for example, a security level communication network ModBus is adopted for data transmission. In the embodiment, because the network transmission has the advantage of high transmission precision, the network communication can be adopted between the preprocessing cabinet and the upper computer.
Further, this protection system still includes the gateway of setting between preliminary treatment rack and host computer, and the gateway is used for realizing the one-way communication between preliminary treatment rack and the host computer, promptly, restricts data and can only pass through the gateway from preliminary treatment rack to the host computer, and the data of host computer can't pass to preliminary treatment rack.
Furthermore, the pretreatment equipment cabinet is connected with the upper computer through a single optical fiber, on one hand, the influence of electromagnetic interference can be reduced by using optical fiber communication, and on the other hand, only the optical fiber for sending data is equipped, so that only sending and receiving are physically carried out, the effect of safety isolation is achieved, and the data of the upper computer of a non-safety level can not flow into the equipment cabinet of a safety level.
In one embodiment, the lower computer is connected with the nuclear power plant DCS system and the preprocessing cabinet through hard wiring respectively. In this embodiment, a hard-wired connection is used between the two security level devices, since hard-wired connections have the advantages of fast response and high reliability.
In a specific embodiment, the upper computer comprises a first DVD read-write optical drive and/or a first USB interface, and is used for periodically writing the generated calibration state core state information into the placed optical disc and/or the inserted USB disk; the lower computer comprises a second DVD read-write optical drive and/or a second USB interface and is used for regularly reading the calibration state reactor core state information from the placed optical disk and/or the inserted U disk. In the embodiment, the operator adopts the medium such as the optical disk and/or the U disk to manually update the data, and the overall safety of the protection system is ensured on the basis of ensuring the integrity of the transmission signal. In another embodiment, a pluggable transmission line is connected between the lower computer and the upper computer, and when the calibration state reactor core state information needs to be transmitted, the transmission line between the lower computer and the upper computer is in a connection state; and when the calibration state core state information does not need to be transmitted, the transmission line between the lower computer and the upper computer is in a disconnected state. In the embodiment, the lower computer and the upper computer adopt the offline signal interface, so that the overall safety of the protection system is ensured on the basis of ensuring the integrity of the transmission signal.
The above description is only a preferred embodiment of the present invention and is not intended to limit the present invention, and various modifications and changes may be made by those skilled in the art. Any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the scope of the claims of the present invention.
Claims (10)
1. A protection system for DNBR/LPD protection of a reactor, comprising:
the pretreatment cabinet is connected with the neutron flux detectors and is used for pretreating detection signals of the neutron flux detectors and generating detection output information;
the upper computer is connected with the pretreatment machine cabinet and the nuclear power plant DCS and is used for periodically generating calibration state reactor core state information according to the detection output information received from the pretreatment machine cabinet and the measurement information of the primary and secondary loop process instrument received from the nuclear power plant DCS;
the lower computer is used for generating a DNBR/LPD protection signal according to the detection output information received from the pretreatment cabinet, the measurement information of a secondary loop process instrument received from the nuclear power plant DCS system and the calibration state core state information periodically received from the upper computer;
the pretreatment equipment cabinet and the lower computer are respectively security level equipment, and the upper computer is non-security level equipment.
2. The protection system according to claim 1, wherein the number of the upper computers is two, and the two upper computers are mutually hot standby.
3. The protection system of claim 1, wherein said preconditioner is plural in number and the plural preconditioners are independently zoned.
4. The protection system according to claim 3, wherein said preconditioners are four in number and each preconditioner is connected to 10 or 11 neutron flux detectors.
5. The protection system according to claim 1, wherein the upper computer comprises a first DVD read-write optical drive and/or a first USB interface, and is configured to periodically write the generated calibration state core state information into the inserted optical disc and/or the inserted USB disk;
the lower computer comprises a second DVD read-write optical drive and/or a second USB interface and is used for regularly reading the calibration state reactor core state information from the placed optical disk and/or the inserted U disk.
6. The protection system according to claim 1, wherein a pluggable transmission line is connected between the lower computer and the upper computer, and when the calibration state core state information needs to be transmitted, the transmission line between the lower computer and the upper computer is in a connection state; and when the calibration state core state information does not need to be transmitted, the transmission line between the lower computer and the upper computer is in a disconnected state.
7. The protection system of claim 1, wherein the lower computer is connected with the nuclear power plant DCS system and the pretreatment cabinet through hard wiring.
8. The protection system of claim 1, wherein said preconditioner cabinet comprises:
the acquisition module is used for acquiring detection signals of the neutron flux detectors in real time;
the filtering module is connected with the acquisition module and is used for filtering invalid signals in the acquired signals;
the compensation module is connected with the filtering module and is used for carrying out delay compensation on the acquired signal after the invalid signal is filtered;
the calculation module is connected with the compensation module and is used for calculating the accumulated charge of the electrode current of the signal after the delay compensation;
the state generating module is used for generating a state signal according to the current running state of the software and hardware;
and the transmission module is connected with the acquisition module, the compensation module, the calculation module and the state generation module and is used for generating detection output information according to the acquisition signal, the delay compensation signal, the accumulated charge and the state signal and transmitting the detection output information.
9. The protection system of claim 8, wherein the transmission module is a network communication module, and the preprocessing cabinet is connected with the upper computer through a communication network.
10. The protection system according to claim 1, wherein the lower computer comprises:
the output module is used for outputting the detection output information received from the preprocessing cabinet;
the alarm module is used for giving an alarm when judging the abnormity according to the detection output information;
and the protection module is used for generating a DNBR/LPD protection signal according to the detection output information received from the pretreatment cabinet, the measurement information of a secondary loop process instrument received from the nuclear power plant DCS system and the calibration state core state information periodically received from the upper computer.
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| CN202111370526.5A CN114242274A (en) | 2021-11-18 | 2021-11-18 | Protection system |
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| CN202111370526.5A CN114242274A (en) | 2021-11-18 | 2021-11-18 | Protection system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115641973A (en) * | 2022-09-09 | 2023-01-24 | 中国核动力研究设计院 | Verification system and method for reactor core neutron flux measurement system |
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2021
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