CN202735877U - Nuclear power plant digital control rod control system based on field programmable gate array (FPGA) and digital signal processing (DSP) controller - Google Patents
Nuclear power plant digital control rod control system based on field programmable gate array (FPGA) and digital signal processing (DSP) controller Download PDFInfo
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- CN202735877U CN202735877U CN2012202273688U CN201220227368U CN202735877U CN 202735877 U CN202735877 U CN 202735877U CN 2012202273688 U CN2012202273688 U CN 2012202273688U CN 201220227368 U CN201220227368 U CN 201220227368U CN 202735877 U CN202735877 U CN 202735877U
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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
- G21C7/12—Means for moving control elements to desired position
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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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- 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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- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model relates to the technical field of the current digital control of control rod driving mechanisms, and particularly discloses a nuclear power plant digital control rod control system based on a field programmable gate array (FPGA) and a digital signal processing (DSP) controller. In the system, a control module controls the current which is input to a driving mechanism coil by driving a pulse amplification module control coil power supply circuit; a power line on the upper end of the coil power supply circuit is connected with the control module through a three-phase voltage acquisition module; a line on the lower end of the coil power supply circuit, which supplies current to the driving mechanism coil is connected with the control module through a current sensor, and the current signal of the driving mechanism coil, which is acquired by the current sensor is fed back to the control module; the control module is also communicated with an external control module through an external interface module; and the control module is communicated with a memory module which is used for storing the control parameters of the control module. According to the system, the structure is compact, the reliability is high, the debugging and the maintenance are easy, and steady current can be supplied to nuclear power plant control rod driving mechanisms with different levels of power.
Description
Technical field
The utility model belongs to nuclear power plant control rod drive mechanisms (CRD) current digital control technology field, is specifically related to a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller.
Background technology
The reliability service of control rod drive mechanisms (CRD) is the key factor that guarantees nuclear plant safety and economy.Say in essence, control rod drive mechanisms (CRD) is a class electromagnetism hoisting apparatus, needs corresponding electric supply installation to provide continuously adjustable electric current for its operation.Nuclear power plant's control rod control system can provide the electric current that meets the demands to control rod drive mechanisms (CRD), the principle of work of its control system is: receive from the control signal of up-stream system and the current feedback signal of driving mechanism, according to these control signals, current feedback signal and the electric current sequential that sets in advance generate thyristor control utmost point driving pulse makes rectification circuit produce the electric current supply control rod drive mechanisms (CRD) that meets the demands, the mechanical part of control rod drive mechanisms (CRD) is in order action under magneticaction, and then drive the control rod action, finally finish nuclear power plant's nuclear power adjustments.
The mimic channel that original control rod control system consists of based on discrete device.Such device space utilization factor is low; Consider less to electromagnetic compatibility; For regulating and the test a large amount of button switch of introducing and potentiometer, cause reliability, stability decreases, debugging and maintenance are inconvenient; In case inconvenience is circuit-forming the most, function is just solidified substantially, almost without any the space of renolation.
Summary of the invention
The purpose of this utility model is to provide a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller, in the control rod control system of solution based on discrete device mimic channel formation, number of devices is many, introduces the decline of a large amount of button switch and reliability that potentiometer causes, stability regulating and testing; And function solidifies, and can not improve the problem of expanded function.
The technical solution of the utility model is as follows: a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller, this control system comprises control module, coil power supply circuit, driving pulse amplification module and current sensor, wherein, control module realizes be input to the control of the electric current of driving mechanism coil through the coil power supply circuit from control rod power supply three-phase supply by driving pulse amplification module control coil feed circuit; Control rod power supply three-phase supply circuit to the coil power supply circuit supply is connected with control module by the three-phase voltage acquisition module; The coil power supply circuit provides to the driving mechanism coil on the circuit of electric current, is connected with control module by current sensor, and the driving mechanism coil current signal of current sensor collection is fed back to control module; Control module also is interconnected by external interface module and external control module, and control module also is interconnected with memory module, is used for storage control module control parameter.
Described control module is comprised of FPGA and DSP.
FPGA in the described control module and DSP can produce drive pulse signal, and by the driving pulse amplification module, the control coil feed circuit export the electric current of driving mechanism coil to.
The mobile control command signal that FPGA in the described control module and DSP provide by external interface module according to the external control module produces the control rod lifting or the lower desired driving mechanism coil of a step of inserting moves the sequential current signal.
FPGA in the described control module and DSP carry out acquisition and processing to the driving mechanism coil current signal by the current sensor input, and after moving the sequential current signal and compare with the driving mechanism coil that requires, adopt pid algorithm that the driving mechanism coil current is carried out closed-loop control, and generation drive pulse signal, by the driving pulse amplification module, the control coil feed circuit are input to the electric current of driving mechanism coil.
Described control module detects by the three-phase voltage signal after the three-phase voltage acquisition module transmission collection, if when the phase of three-phase voltage accident occurring, control module sends failure alarm signal by external interface module to outside control module.
Described control module detects and feeds back to the current signal of control module by current sensor, if the driving mechanism coil current occurs when excessive or too small, control module sends failure alarm signal by external interface module to outside control module.
Described external control module can require mobile sequential current parameters and coil current alarm threshold value parameter by pid algorithm control parameter, the driving mechanism coil that external interface module arranges in the control module.
Described control module is comprised of FPGA and DSP, and wherein, FPGA adopts the CYCLONE II of U.S. ALTERA company series, and model is EP2C20Q24OI8N, and DSP adopts the DSP of American TI Company, and model is TMS320F28335.
Remarkable result of the present utility model is: a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller described in the utility model adopts digitized control mode to realize the control of driving mechanism coil current, promote or insert down desired driving mechanism coil of a step by this digital controller generation control rod and move the sequential current signal, and the driving mechanism coil current signal carried out acquisition and processing, after moving the sequential current signal and compare with the driving mechanism coil that requires, adopt pid algorithm to produce the α pilot angle, and after carrying out synchronously with excellent power supply three-phase supply, produce the electric current that drive pulse signal is controlled the driving mechanism coil, thereby form the closed-loop control of coil current; This digital controller is also realized open phases of three-phase power source, coil current is excessive or the fault such as too small is reported to the police; Can realize in addition the setting of control parameter in the controller by man-machine interface.The control rod control system of relatively present domestic employing simulation fastener, native system has greatly reduced number of devices after adopting digital controller, has improved reliability and the extensibility of equipment.In addition native system by man-machine interface control parameter setting and revise after can provide stable electric current to nuclear power plant's control rod drive mechanisms (CRD) of different brackets power, have good applicability.And control, debug and safeguard by man-machine interface, greatly reduced operator's work and maintenance cost.
Description of drawings
Fig. 1 is a kind of nuclear power plant's Digital Control rod control system structural representation based on FPGA and dsp controller described in the utility model
Among the figure: 1, control module; 2, three-phase voltage acquisition module; 3, coil power supply circuit; 4, external interface module; 5, current sensor; 6, driving pulse amplification module; 7, external control module; 8, memory module.
Embodiment
Below in conjunction with drawings and the specific embodiments the utility model is described in further detail.
As shown in Figure 1, a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller comprises control module 1, coil power supply circuit 3, driving pulse amplification module 6 and current sensor 5; Control module 1 realizes being input to the control of driving mechanism coil current to from the thyristor in the control rod power supply three-phase supply process coil power supply circuit 3 by driving pulse amplification module 6 control coil feed circuit 3; Simultaneously, control rod power supply three-phase supply circuit to the power supply of coil power supply circuit 3 is connected with control module 1 by three-phase voltage acquisition module 2, utilize three-phase voltage acquisition module 2 to send three-phase voltage signal after the step-down to control module 1,1 pair of this signal of control module is processed synchronously, thereby realizes the synchro control of thyristor and control rod power supply three-phase supply in the control module 1 control coil feed circuit 3; Coil power supply circuit 3 provides to the driving mechanism coil on the circuit of electric current, is connected with control module 1 by current sensor 5, and the driving mechanism coil current signal that current sensor 5 is gathered feeds back to control module 1; Control module 1 is comprised of FPGA and DSP, and wherein, FPGA adopts the CYCLONE II of U.S. ALTERA company series, and model is EP2C20Q24OI8N; DSP adopts the DSP of American TI Company, and model is TMS320F28335.Control module 1 also is interconnected by external interface module 4 and external control module 7, and control module 1 also is interconnected with memory module 8, wherein, control module 1 detects by the three-phase voltage signal after the 2 transmission step-downs of three-phase voltage acquisition module, control module 1 detects this signal, when if the phase of three-phase voltage accident occurring, control module 1 sends failure alarm signal by external interface module 4 to outside control module 7; Simultaneously, control module 1 detects and feeds back to the current signal of control module 1 by current sensor 5, if the driving mechanism coil current occurs when excessive or too small, control module 1 sends failure alarm signals by external interface module 4 to outside control module 7.
In a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller described in the utility model, after external control module 7 sends mobile control command by external interface module 4 to control module 1, as promoting or lower slotting order, control module 1 produces lifting according to mobile control command signal or the lower desired driving mechanism coil of a step of inserting moves the sequential current signal as requiring signal, simultaneously, current sensor 5 acquisition stream are sent to control module 1 through the actual current signal of driving mechanism coil as feedback signal, two kinds of current signals are compared control module 1 is interior, its deviation is controlled by pid control algorithm, produce the control signal that is used for the control coil electric current, this control signal through with from the three-phase voltage signal of three-phase voltage acquisition module 2 and after in control module 1, processing synchronously, output as control module 1 sends thyristor trigger pip in the coil power supply circuit 3 to driving pulse amplification module 6, this signal amplifies through the pulse of overdrive pulse amplification module 6 processes the backward coil power supply circuit 3 transmissions thyristor trigger pip corresponding with control rod power supply three-phase supply phase place, behind the thyristor, provide electric current to the driving mechanism coil in the control rod three-phase supply process coil power supply circuit 3.Whole process consists of the coil current control loop of a closed loop.The operator is by control external control module 7, control parameter required in the control module 1 is set, the pid algorithm parameter can be set, the driving mechanism coil requires mobile sequential current parameters, coil current alarm threshold values etc. are by the change control parameter, to be applicable to nuclear power plant's control rod control system of different capacity grade, the setting of these parameters is left in the memory module 8.
Claims (6)
1. nuclear power plant's Digital Control rod control system based on FPGA and dsp controller, it is characterized in that: this control system comprises control module (1), coil power supply circuit (3), driving pulse amplification module (6) and current sensor (5).Wherein, control module (1) realizes be input to the control of the electric current of driving mechanism coil through coil power supply circuit (3) from control rod power supply three-phase supply by driving pulse amplification module (6) control coil feed circuit (3); Control rod power supply three-phase supply circuit to coil power supply circuit (3) power supply is connected with control module (1) by three-phase voltage acquisition module (2) simultaneously; Coil power supply circuit (3) provides to the driving mechanism coil on the circuit of electric current, is connected with control module (1) by current sensor (5), and the driving mechanism coil current signal that current sensor (5) is gathered feeds back to control module (1); Control module (1) also is interconnected by external interface module (4) and external control module (7), and control module (1) also is interconnected with memory module (8), is used for storage control module (1) control parameter.
2. a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller according to claim 1, it is characterized in that: described control module (1) is comprised of FPGA and DSP.
3. a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller according to claim 2, it is characterized in that: FPGA and DSP in the described control module (1) can produce drive pulse signal, by driving pulse amplification module (6), control coil feed circuit (3) export the electric current of driving mechanism coil to.
4. a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller according to claim 2, it is characterized in that: described control module (1) detects by the three-phase voltage signal after three-phase voltage acquisition module (2) the transmission collection, when if the phase of three-phase voltage accident occurring, control module (1) sends failure alarm signal by external interface module (4) to outside control module (7).
5. a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller according to claim 2, it is characterized in that: described control module (1) detects the current signal that is fed back to control module (1) by current sensor (5), if the driving mechanism coil current occurs when excessive or too small, control module (1) sends failure alarm signal by external interface module (4) to outside control module (7).
6. a kind of nuclear power plant's Digital Control rod control system based on FPGA and dsp controller according to claim 2 is characterized in that: described external control module (7) can require mobile sequential current parameters and coil current alarm threshold value parameter by pid algorithm parameter control parameter, the driving mechanism coil that external interface module (4) arrange in the control module (1).
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012202273688U CN202735877U (en) | 2012-05-17 | 2012-05-17 | Nuclear power plant digital control rod control system based on field programmable gate array (FPGA) and digital signal processing (DSP) controller |
| PCT/CN2012/077270 WO2013170518A1 (en) | 2012-05-17 | 2012-06-20 | System for controlling nuclear power plant digital control rod based on fpga and dsp controller |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012202273688U CN202735877U (en) | 2012-05-17 | 2012-05-17 | Nuclear power plant digital control rod control system based on field programmable gate array (FPGA) and digital signal processing (DSP) controller |
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| CN202735877U true CN202735877U (en) | 2013-02-13 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN2012202273688U Expired - Lifetime CN202735877U (en) | 2012-05-17 | 2012-05-17 | Nuclear power plant digital control rod control system based on field programmable gate array (FPGA) and digital signal processing (DSP) controller |
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| Country | Link |
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| CN (1) | CN202735877U (en) |
| WO (1) | WO2013170518A1 (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104332187A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Control method for driving mechanisms of nuclear power station |
| CN104616705A (en) * | 2015-01-09 | 2015-05-13 | 中科华核电技术研究院有限公司 | Control system for reactor control rods |
| CN104898069A (en) * | 2014-03-06 | 2015-09-09 | 江苏核电有限公司 | Control rod driving mechanism AC power supply module test device |
| CN106462137A (en) * | 2013-12-20 | 2017-02-22 | 西屋电气有限责任公司 | A system and method for securing an industrial control system |
| CN107045896A (en) * | 2016-02-05 | 2017-08-15 | 中国船舶重工集团公司第七�三研究所 | A kind of controllable energy storage device of order and energy storage method |
| CN107256728A (en) * | 2017-05-22 | 2017-10-17 | 福建福清核电有限公司 | A kind of nuclear power plant's Digital Control rod current monitoring fastener based on FPGA |
| CN111489838A (en) * | 2019-01-25 | 2020-08-04 | 中国核动力研究设计院 | Control rod driving mechanism power supply based on P L C + FPGA/DSP + IGBT control framework |
| CN112181035A (en) * | 2020-09-30 | 2021-01-05 | 中国核动力研究设计院 | Segmented accurate control method for control current of nuclear power station driving mechanism |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| US5999583A (en) * | 1996-04-29 | 1999-12-07 | Westinghouse Electric Company Llc | Method and apparatus for control rod drive mechanism analysis using coil current signals |
| BR0313132A (en) * | 2002-07-31 | 2005-07-05 | Sydkraft Ab | Electric machine |
| US7505545B2 (en) * | 2004-06-24 | 2009-03-17 | Korea Electro Technology Research Institute | Method for recognizing step movement sequence of control rod drive mechanism of nuclear reactor |
| CN101067976B (en) * | 2006-09-15 | 2010-05-19 | 核电秦山联营有限公司 | Pressurized water reactor nuclear power station control bar driving mechanism on-line monitoring and fault diagnosing method |
| FR2910688A1 (en) * | 2006-12-21 | 2008-06-27 | Data Systems & Solutions Soc P | CONTROL SYSTEM FOR NUCLEAR REACTOR BAR CONTROL MECHANISMS. |
| CN101685679B (en) * | 2008-09-27 | 2012-05-16 | 中国核动力研究设计院 | System for monitoring loosening part of nuclear reactor and coolant system |
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2012
- 2012-05-17 CN CN2012202273688U patent/CN202735877U/en not_active Expired - Lifetime
- 2012-06-20 WO PCT/CN2012/077270 patent/WO2013170518A1/en active Application Filing
Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104332187A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Control method for driving mechanisms of nuclear power station |
| CN106462137A (en) * | 2013-12-20 | 2017-02-22 | 西屋电气有限责任公司 | A system and method for securing an industrial control system |
| CN106462137B (en) * | 2013-12-20 | 2019-04-30 | 西屋电气有限责任公司 | System and method for ensureing industrial control system |
| CN104898069A (en) * | 2014-03-06 | 2015-09-09 | 江苏核电有限公司 | Control rod driving mechanism AC power supply module test device |
| WO2016110171A1 (en) * | 2015-01-09 | 2016-07-14 | 中广核研究院有限公司 | Reactor control rod control system |
| CN104616705B (en) * | 2015-01-09 | 2017-08-29 | 中广核研究院有限公司 | Reactor control rod control system |
| CN104616705A (en) * | 2015-01-09 | 2015-05-13 | 中科华核电技术研究院有限公司 | Control system for reactor control rods |
| CN107045896A (en) * | 2016-02-05 | 2017-08-15 | 中国船舶重工集团公司第七�三研究所 | A kind of controllable energy storage device of order and energy storage method |
| CN107045896B (en) * | 2016-02-05 | 2018-12-28 | 中国船舶重工集团公司第七一三研究所 | A kind of controllable energy storage device of sequence and energy storage method |
| CN107256728A (en) * | 2017-05-22 | 2017-10-17 | 福建福清核电有限公司 | A kind of nuclear power plant's Digital Control rod current monitoring fastener based on FPGA |
| CN111489838A (en) * | 2019-01-25 | 2020-08-04 | 中国核动力研究设计院 | Control rod driving mechanism power supply based on P L C + FPGA/DSP + IGBT control framework |
| CN111489838B (en) * | 2019-01-25 | 2022-07-26 | 中国核动力研究设计院 | Control rod driving mechanism power supply based on PLC + FPGA/DSP + IGBT control framework |
| CN112181035A (en) * | 2020-09-30 | 2021-01-05 | 中国核动力研究设计院 | Segmented accurate control method for control current of nuclear power station driving mechanism |
| CN112181035B (en) * | 2020-09-30 | 2022-02-11 | 中国核动力研究设计院 | Segmented accurate control method for control current of nuclear power station driving mechanism |
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| Publication number | Publication date |
|---|---|
| WO2013170518A1 (en) | 2013-11-21 |
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Granted publication date: 20130213 |
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