CN106384611A - Nuclear power station rod control system test device and method - Google Patents

Nuclear power station rod control system test device and method Download PDF

Info

Publication number
CN106384611A
CN106384611A CN201611002214.8A CN201611002214A CN106384611A CN 106384611 A CN106384611 A CN 106384611A CN 201611002214 A CN201611002214 A CN 201611002214A CN 106384611 A CN106384611 A CN 106384611A
Authority
CN
China
Prior art keywords
signal
rod
interface
cabinet
telecommunication
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
CN201611002214.8A
Other languages
Chinese (zh)
Other versions
CN106384611B (en
Inventor
邵帅
张军
关济实
李强
刘美军
李蕊
娄毅
张明亮
杜晓光
沙洪伟
王斌
常新彩
刘岩
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Beijing Branch China Nuclear Power Technology Research Institute
China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
Original Assignee
Beijing Branch China Nuclear Power Technology Research Institute
China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Beijing Branch China Nuclear Power Technology Research Institute, China General Nuclear Power Corp, CGN Power Co Ltd, Daya Bay Nuclear Power Operations and Management Co Ltd, Guangdong Nuclear Power Joint Venture Co Ltd, Lingao Nuclear Power Co Ltd filed Critical Beijing Branch China Nuclear Power Technology Research Institute
Priority to CN201611002214.8A priority Critical patent/CN106384611B/en
Publication of CN106384611A publication Critical patent/CN106384611A/en
Application granted granted Critical
Publication of CN106384611B publication Critical patent/CN106384611B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/102Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain the sensitive element being part of a fuel element or a fuel assembly
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/112Measuring temperature
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/12Sensitive element forming part of control element
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention relates to a nuclear power station rod control system test device and method. The device comprises a power supply system, KVM equipment, an industrial personal computer, a data collecting system, an interface machine case, microphone equipment and a printer, wherein the power supply system is electrically connected with the industrial personal computer, the KVM equipment and the interface machine case; the KVM equipment, the data collecting system and the printer are respectively connected with the industrial personal computer through electric signals; the interface machine case is provided with an isolation module and an interface board in mutual connection; the isolation module is connected with the data collection system through electric signals; the interface board is connected with the microphone equipment through electric signals; the microphone equipment is arranged on the control rod driving mechanism of the rod control system; the interface board is also connected with the power supply cabinet of the rod control system through electric signals. The device and the method provided by the invention have the advantages that the problems of test work process complexity, data analysis difficulty and the like due to no special test device in the prior art can be solved; the operation reliability of the rod control system is effectively improved.

Description

Nuclear power station rod control system test device and method
Technical field
The present invention relates to nuclear power station rod control system field tests and in particular to a kind of nuclear power station rod control system test device and Method.
Background technology
The startup of nuclear power station, shutdown, power adjustments, flattening and emergency episode shutdown, be both needed to by control rod Lai Realize, be then that CRDM realizes by rod control system by CRDM to the control of control rod.No matter to nuclear power plant Security consideration, or to consider in terms of economic benefit, control rod, drive mechanism and rod control system are all the keys of the design overall situation Property visual plant, improve rod control system operational reliability significant.
In order to improve the operational reliability of rod control system, during nuclear power station overhaul, need to rod control system (i.e. RGL system) Carry out CRDM (CRDM) noise record ripple, excellent bit port is identified and other necessary functional tests again, but at present Do not have special assay device that above-mentioned functions are tested in prior art.Lead to test job process loaded down with trivial details, test after point Analysis difficulty data, to test job or even whole nuclear power station overhaul be smoothed out impact.
Content of the invention
It is an object of the invention to provide a kind of nuclear power station rod control system test device, to solve in prior art because not having The problems such as test job process that special assay device is brought is loaded down with trivial details, analytical data is difficult, improves rod control system simultaneously Operational reliability.Additionally, the present invention accordingly proposes a kind of nuclear power station rod control system method of testing.
In order to realize above goal of the invention, a kind of nuclear power station rod control system test device proposed by the present invention includes power supply system System, KVM equipment, industrial computer, data collecting system, interface cabinet, microphone apparatus and printer;Described electric power system not with Industrial computer, KVM equipment, interface cabinet are powered connection;Described KVM equipment, data collecting system and printer respectively with industry control Dynamoelectric signal connects;Described interface cabinet has interconnective isolation module and interface board;Described isolation module and data are adopted The collecting system signal of telecommunication connects;Described interface board is connected with the described microphone apparatus signal of telecommunication, and described microphone apparatus are installed on rod To gather the noise signal hooking pawl action on the CRDM of control system, transmit after isolation module isolation and adopt to data Collecting system;Described interface board is also connected with the power cabinet signal of telecommunication of rod control system, is sent to control rod with correspondingly received power cabinet The stationary coil of drive mechanism, moving coil and lifting coil electric current clock signal, through isolation module isolation after transmit to Data collecting system;Described industrial computer calculates corresponding according to the next noise signal of data collecting system transmission and electric current clock signal Hook pawl movement time and action current, and it is qualified to judge whether to make comparisons with standard value, and judged result is by described KVM equipment Export or by described printer printout.
In the further scheme of the present invention, also excellent position monitor unit cabinet, the control with rod control system respectively of described interface board Logic cabinet and the rod position measurement cabinet signal of telecommunication connect, and are surveyed with receiving excellent bit scan signal, excellent bit instruction signal and excellent position respectively Amount signal, transmits to data collecting system after isolation module isolation;Described industrial computer comes according to data collecting system transmission Excellent bit scan signal, excellent bit instruction signal and rod position measurement signal, judge control rod measurement position and the control rod location of instruction Whether in default error, judged result is exported by described KVM equipment or by described printer printout.
In the further scheme of the present invention, also include rosette, be connected to described isolation module and data collecting system it Between.
In the further scheme of the present invention, described data collecting system includes the analog acquisition plate for collection voltages signal Card and the digital collection board for gathering digital signal;Described isolation module includes analog signal isolating module and digital signal Isolation module;Described analog acquisition board is connected with analog signal isolating modular telecommunications number, described digital collection board with numeral Signal isolation modular telecommunications number connect;Described analog signal isolating module is used for isolating described noise signal and electric current sequential letter Number;Described digital signal isolation module is used for isolating described rod bit scan signal, excellent bit instruction signal and rod position measurement signal.
In the further scheme of the present invention, also include connecting cabinet;Described connection cabinet includes the first adapter, the second company Connect device, the 3rd adapter, the 4th adapter and the 5th adapter;First adapter is connected with the described microphone apparatus signal of telecommunication; Second adapter is used for being connected with the described rod position monitor unit cabinet signal of telecommunication;3rd adapter is used for and described control logic cabinet electricity Signal connects;4th adapter is used for being connected with the described rod position measurement cabinet signal of telecommunication;5th adapter is used for and described power cabinet The signal of telecommunication connects;
The interface board of described interface cabinet includes:Input first interface, input second interface, input the 3rd interface With input the 4th interface and corresponding outfan first interface, outfan second interface, outfan the 3rd interface and output Hold the 4th interface;Input first interface is connected with the described first adapter signal of telecommunication;Input second interface and the described 5th The adapter signal of telecommunication electrically connects;Input the 3rd interface is electrically connected with described 4th adapter;Input the 4th interface with described Second adapter and the 3rd adapter signal of telecommunication connect;
Outfan first interface and outfan second interface are by described rosette and the described analog acquisition board signal of telecommunication Connect;Outfan the 3rd interface and outfan the 4th interface are by described rosette with the described digital collection board signal of telecommunication even Connect.
In the further scheme of the present invention, described digital signal isolation module is solid-state relay.
In the further scheme of the present invention, described electric power system includes control panel and power case;Described control panel There is the start button being connected with the power case signal of telecommunication, stop button and scram button.
A kind of corresponding nuclear power station rod control system method of testing proposing of the present invention, using the nuclear power station rod of any of the above-described scheme Control opening machine system test device, and include CRDM noise record ripple method of testing;Described CRDM noise Record ripple method of testing comprises the following steps:
A1, being provided a user with by operation interface in configuration file mode can test bar group;
A2, according to user instruction from tested coupon group accordingly can be selected test bar group, and the bag of receiving user's input Include excellent position initial step length, power station title, train unit, user name, temperature and pressure in interior information;
A3, vertical CRDM test data file is set up based on power station title, train unit and tested coupon Folder;
A4, collection include hooking the noise signal of pawl action, and when stationary coil, moving coil, the electric current of lifting coil Sequential signal is in interior signal data;
A5, according to noise signal and corresponding electric current clock signal calculate corresponding hook pawl movement time and action current, And it is qualified to judge whether to make comparisons with standard value;
A6, described CRDM test data file folder in set up respective file to store the signal collecting Data and judged result, and output display or printout.
In the further scheme of the present invention, also include excellent bit port characterization test method again;Described rod bit port is identified again Method of testing comprises the following steps:
B1, the inclusion power station title of receive user setting, train unit, tested rod group, user name, temperature and pressure exist Interior information;
B2, vertical rod bit port characterization test data file again is set up based on power station title, train unit and tested coupon Folder;
B3, the excellent bit scan signal of acquisition rod position monitor unit cabinet are to identify the corresponding ear of maize of current measuring stick position signal Group;And the excellent bit instruction signal of acquisition controlling logic cabinet and the rod position measurement signal of rod position measurement cabinet;
B4, judge that according to excellent bit instruction signal and rod position measurement signal control rod measurement position and the control rod location of instruction are No in default error;
B5, set up respective file with memory stick bit instruction signal in characterization test data folder again in described rod bit port Data, rod position measurement signal data and judged result, and output display or printout.
In the further scheme of the present invention, also include current test method;Connect cabinet also tested with power cabinet respectively Shunting card in frame, isolation amplify card and select the control card signal of telecommunication to connect;Described current test method includes following step Suddenly:
C1, the inclusion power station title of receive user setting, train unit, tested frame, user name, temperature and pressure exist Interior information;
C2, testing current data folder is set up based on power station title, train unit and tested frame;
C3, gather respectively from the tested frame of the power cabinet of rod control system zero current, half electric current, under three kinds of states of total current Shunting card voltage signal, isolation amplify card voltage signal and select control card voltage signal;
C4, judge described shunting card voltage signal, isolation amplify card voltage signal and select control card voltage signal be No in preset range;
C5, set up in described testing current data folder respective file with shunt card voltage signal data, isolation put Kilocalorie voltage signal data and selection control card voltage signal data and judged result, and output display or printout.
The present invention at least possesses following beneficial effect:
1st, solve that in prior art, the test job process that special assay device is brought is loaded down with trivial details, analytical data because not having Difficult the problems such as, is so that the test job of rod control system or even whole nuclear power station overhaul are smooth.
2nd, easy to operate, effectively increase the operational reliability of rod control system.
Brief description
Fig. 1 is the nuclear power station rod control system test device structured flowchart that embodiment one proposes.
Fig. 2 is CRDM noise record ripple test in the nuclear power station rod control system method of testing that embodiment two proposes Method flow schematic diagram.
Fig. 3 is excellent bit port characterization test method flow again in the nuclear power station rod control system method of testing that embodiment three proposes Schematic diagram.
Fig. 4 is current test method schematic flow sheet in the nuclear power station rod control system method of testing that example IV proposes.
Specific embodiment
For the ease of it will be appreciated by those skilled in the art that carrying out further to the present invention below in conjunction with accompanying drawing and embodiment Description.
Embodiment one
Refer to Fig. 1, the nuclear power station rod control system test device that embodiment one proposes, agent structure includes electric power system 10th, KVM equipment 20, industrial computer 30, data collecting system 40, interface cabinet 50, microphone apparatus 60 and printer 70;Described Electric power system 10 is not with industrial computer 30, KVM equipment 20, interface cabinet 50 for electrically connecting;Described KVM equipment 20, data acquisition system System 40 and printer 70 are connected with industrial computer 30 signal of telecommunication respectively;Described interface cabinet 50 has interconnective isolation module 51 and interface board 52;Described isolation module 51 is connected with data collecting system 40 signal of telecommunication, to meet the electric ring of scene complexity Border requires, and prevents foreign current voltge surge from board is caused damage;Described interface board 52 and described microphone apparatus 60 telecommunications Number connect, described microphone apparatus 60 be installed on the CRDM of rod control system (not shown) with gather hook pawl move The noise signal made, transmits to data collecting system 40 after isolation module 51 isolation;Described interface board 52 is gone back and rod control system The power cabinet signal of telecommunication connect, sent with correspondingly received power cabinet to the stationary coil (SG) of CRDM, portable cord Circle (MG) and the electric current clock signal of lifting coil (LC), transmit to data collecting system 40 after isolation module 51 isolation; Described industrial computer 30 calculates the corresponding pawl that hooks according to the next noise signal of data collecting system 40 transmission and electric current clock signal and moves Make time and action current, and it be qualified to judge whether to make comparisons with standard value, judged result exported by described KVM equipment 20 or By the printout of described printer 70.
Therefore, the nuclear power station rod control system test device that the present embodiment proposes can be applicable to the control rod of rod control system RGL In the record ripple test of drive mechanism noise, whether normal with the work that checks CRDM.In further scheme, this reality Apply example and apply also for the excellent bit port of rod control system again in characterization test, to check RCC assembly (RCCA) in low speed shape In insertion and lifting process under state, whether control rod measurement position is consistent with the control rod location of instruction.
In described further scheme, interface board 52 also excellent position monitor unit cabinet, the control logic cabinet with rod control system respectively And the rod position measurement cabinet signal of telecommunication connects, to receive excellent bit scan signal, excellent bit instruction signal and rod position measurement signal respectively, Transmit to data collecting system 40 after isolation module 51 isolation;Described industrial computer 30 comes according to data collecting system 40 transmission Excellent bit scan signal, excellent bit instruction signal and rod position measurement signal, judge control rod measurement position and the control rod location of instruction Whether in default error, judged result is exported by described KVM equipment 20 or by the printout of described printer 70.
In preferred version, also include rosette 80, be connected between described isolation module 51 and data collecting system 40.
In the present embodiment, described data collecting system 40 specifically may include the analog acquisition board for collection voltages signal With the digital collection board for gathering digital signal;Described isolation module 51 specifically may include analog signal isolating module sum Word signal isolation module;Described analog acquisition board is connected with analog signal isolating modular telecommunications number, described digital collection board It is connected with the digital signal isolation module signal of telecommunication;When described analog signal isolating module is used for isolating described noise signal and electric current Sequential signal;Described digital signal isolation module is used for isolating described rod bit scan signal, excellent bit instruction signal and rod position measurement Signal.
In preferred version, also can further include to connect cabinet (not shown);Described connection cabinet includes the first connection Device, the second adapter, the 3rd adapter, the 4th adapter and the 5th adapter;First adapter and described microphone apparatus 60 The signal of telecommunication connects;Second adapter is used for being connected with the described rod position monitor unit cabinet signal of telecommunication;3rd adapter be used for described The control logic cabinet signal of telecommunication connects;4th adapter is used for being connected with the described rod position measurement cabinet signal of telecommunication;5th adapter is used for It is connected with the described power cabinet signal of telecommunication.The interface board 52 of described interface cabinet 50 includes:Input first interface, input second Interface, input the 3rd interface and input the 4th interface and corresponding outfan first interface, outfan second interface, defeated Go out end the 3rd interface and outfan the 4th interface;Input first interface is connected with the described first adapter signal of telecommunication;Input Second interface is electrically connected with the described 5th adapter signal of telecommunication;Input the 3rd interface is electrically connected with described 4th adapter;Defeated Enter end the 4th interface to be connected with described second adapter and the 3rd adapter signal of telecommunication.Outfan first interface and outfan second Interface is connected with the described analog acquisition board signal of telecommunication by described rosette;Outfan the 3rd interface and outfan the 4th interface It is connected with the described digital collection board signal of telecommunication by described rosette.
In the present embodiment, described digital signal isolation module can be specifically solid-state relay.Described electric power system 10 is wrapped Include control panel and power case;Described control panel has the start button being connected with the power case signal of telecommunication, stop button And scram button.
The nuclear power station rod control system test device that embodiment one proposes drives except the control rod that can be applicable to rod control system Mechanism's noise record the excellent bit port of ripple test and rod control system again in characterization test outside, will connect cabinet respectively with power cabinet in In tested frame, the shunting card of (for outputing voltage signal to stationary coil, moving coil and lifting coil), isolation are put Kilocalorie and the selection control card signal of telecommunication connect, and apply also in the frame testing current of rod control system.
Embodiment two
Refer to Fig. 2, embodiment two is a kind of nuclear power station rod control system test side realizing on the basis of embodiment one Method, it specifically includes CRDM noise record ripple method of testing;Described CRDM noise records ripple test side Method comprises the following steps:
S100, being provided a user with by operation interface in configuration file mode can test bar group.
S200, according to user instruction from can select tested coupon group accordingly test bar group, and receiving user's input Information including excellent position initial step length, power station title, train unit, user name, temperature and pressure.
S300, vertical CRDM test data literary composition is set up based on power station title, train unit and tested coupon Part presss from both sides.
S400, collection include hooking the noise signal of pawl action, and stationary coil, moving coil, the electric current of lifting coil Clock signal is in interior signal data.
S500, calculated according to noise signal and corresponding electric current clock signal and corresponding hook pawl movement time and action electricity Stream, and it is qualified to judge whether to make comparisons with standard value.
S600, described CRDM test data file folder in set up respective file to store the letter collecting Number and judged result, and output display or printout.
The CRDM noise record ripple method of testing purpose of embodiment two is to check CRDM Whether (i.e. CRDM) be working properly, and the signal that need to gather includes hooking the noise signal of pawl action, and stationary coil, portable cord Circle, the electric current clock signal of lifting coil.Wherein, electric current clock signal can amplify card voltage output by collection isolation and characterize Current signal, the voltage that it amplifies card output with corresponding isolation is consistent, is multiple proportion, therefore can gather isolation and amplify card electricity Pressure output characterizes current signal.The exercise data of one rod group of test every time.During rod withdrawal, excellent position scope is 0~232 step;Plunger When, excellent position scope is 232~0 steps.Control rod maximum rate be 72 steps/point.
Test when, the operation interface of KVM equipment will show can test bar group selection button, and rod position initially walk The input frame of the information such as length, power station title, train unit, user name, temperature and pressure supplies user input.Then according to selection Can test bar group gather 8 road microphone signals (i.e. noise signal), 8 road stationary coil (SG) electric current clock signals, 8 tunnels move Coil (MG) electric current clock signal and 8 tunnels lifting coil (LC) electric current clock signal.According to presetting, sample frequency is 1kHz, Collection maximum 60 minutes persistent period, collection after 60 minutes is automatically stopped.
Data during test, is managed according to the file with power station _ unit as title.For example:D:\Result\ CRDM [power station title] _ [train unit] _ [excellent group].
Once test generates a data file, and file designation form is:CRDM_ [excellent group] _ [control rod] _ [date] _ [time] .tdms.Wherein, date format is YYYYMMDD;Time format is HHMMSS.For example:D:\Result\CDRM\ SITExxx_1_SD\crdm_SD_G07_20141215_155436.tdms.
Embodiment three
Refer to Fig. 3, the nuclear power station rod control system method of testing that embodiment three proposes, on the basis of embodiment two, is also wrapped Include excellent bit port characterization test method again;Characterization test method comprises the following steps described rod bit port again:
L100, the inclusion power station title of receive user setting, train unit, tested rod group, user name, temperature and pressure In interior information.
L200, vertical rod bit port characterization test data literary composition again is set up based on power station title, train unit and tested coupon Part presss from both sides.
L300, the excellent bit scan signal of acquisition rod position monitor unit cabinet are to identify the corresponding ear of maize of current measuring stick position signal Group;And the excellent bit instruction signal of acquisition controlling logic cabinet and the rod position measurement signal of rod position measurement cabinet.
L400, control rod measurement position and the control rod location of instruction are judged according to excellent bit instruction signal and rod position measurement signal Whether in default error.
L500, set up respective file again in characterization test data folder in described rod bit port and believed with memory stick bit instruction Number, rod position measurement signal data and judged result, and output display or printout.
Characterization test method purpose is for checking RCC assembly (RCCA) in low speed to the excellent bit port of embodiment three again In insertion and lifting process under state, whether control rod measurement position is consistent with the control rod location of instruction.Control rod measurement position Control rod position should be made controlled in the range of certain error with the control rod location of instruction.Excellent position control instruction is transferred to one every time Four clusters in individual ear of maize group.Excellent position monitor unit cabinet can send the scanning letter of measuring stick position in order to rod position measurement cabinet Number, this signal continues more than 30ms and just can be received confirmation by rod position measurement cabinet, can take at excellent position monitor unit cabinet rear terminal row , the different terminal of every group of rod correspondence;After rod position measurement cabinet receives rod group scanning signal, excellent position signal can be transmitted excellent position and monitor Two ETOR cards of unit cabinet, each excellent group has 4 fasces, and the 1st fasces of all rod groups constitutes bus 1, and the 2nd fasces constitutes bus 2, the 3rd fasces constitutes bus 3, and the 4th fasces constitutes bus 4, and the rod group only receiving excellent bit scan signal and confirming just can handle To in respective bus, excellent position information is sent in the form of 5 Gray codes excellent position information transmission, and this lining bar position monitor unit cabinet will Receive the measuring stick position of one group of rod every time and store.Excellent position information can also obtain at the monitor unit cabinet terminal block of excellent position. The gaging hole of terminal block is the circular hole that diameter is slightly larger than 4mm.
In test, the operation interface of KVM equipment will show power station title, train unit, tested excellent group, user name, The configuration information such as temperature and pressure supplies user setup.The excellent bit scan signal of the tested rod group measuring stick subgroup based on setting, Excellent bit instruction signal and rod position measurement signal.In testing, carry out successively by rod group, the number of 8 control rods can be recorded simultaneously According to:16 road ear of maize group rod bit scan signals, for identifying the corresponding ear of maize group of current measuring stick position signal;20 road rod position measurement letters Number, 4 (every subgroup rod number) * 5 (often excellent position is represented by 5 Gray codes);12 road rod bit instruction signals.Each collecting thread be only capable of into One rod group test of row, can be rod withdrawal or plunger test.The acquiescence rod speed of rod withdrawal and plunger process is 6 steps/minute, Big stick-means of intimidation speed is 10 steps/minute.According to default, sample frequency 20Hz of excellent bit instruction signal and rod position measurement signal, collection is Big 120 minutes persistent period, collection after 120 minutes is automatically stopped.
Data during test is managed according to the file with power station _ unit as title.For example:D:\Result\ Position [power station title] _ [train unit] _ [excellent group].
Once test generates a data file, and file designation form is:Position_ [excellent group] _ [date] _ [when Between] .tdms.Wherein, date format is YYYYMMDD;Time format is HHMMSS.For example:D:\Result\Position\ SITExxx_1_SD\Position_SD_20141215_155436.tdms.
Example IV
Refer to Fig. 4, the nuclear power station rod control system method of testing that example IV proposes, on the basis of embodiment three, is also wrapped Include current test method;First by connect cabinet respectively with frame tested in power cabinet on shunting card, isolation amplify card and select After selecting the connection of the control card signal of telecommunication, execute following steps:
M100, the inclusion power station title of receive user setting, train unit, tested frame, user name, temperature and pressure In interior information.
M200, testing current data folder is set up based on power station title, train unit and tested frame.
M300, gather zero current, half electric current, three kinds of states of total current from the tested frame of the power cabinet of rod control system respectively Under shunting card voltage signal, isolation amplify card voltage signal and select control card voltage signal.
M400, judge described shunting card voltage signal, isolation amplify card voltage signal and select control card voltage signal Whether in preset range.
M500, set up in described testing current data folder respective file with store shunting card voltage signal data, Isolation is amplified card voltage signal data and is selected control card voltage signal data and judged result, and output display or print defeated Go out.
Need to test corresponding frame in example IV and be respectively collection SHUNT card when zero current, half electric current, total current and (divide Stream card) four road voltage signals, isolation amplify card four road voltage signals, select control card two-way voltage signal, and automatic decision.Example As whether correctly detection and isolation amplifies the amplification blocking output, judge to select the voltage signal that control card selects whether correct. Actually also achieve the judgement of electric current based on the judgement on voltage.
Test when, the operation interface of KVM equipment will show power station title, train unit, tested frame, user name, The configuration information such as temperature and pressure supplies user setup.Then gather zero from the tested frame of rod control system respectively according to setting Shunting card voltage signal under electric current, half electric current, three kinds of states of total current, isolation amplify card voltage signal and select control card Voltage signal.According to default, signal sampling frequencies 1kHz, collection maximum 60 minutes persistent period, gather after 60 minutes and automatically stop Only.
Data during test, is managed according to the file with power station _ unit as title.For example:D:\Result\ Current [power station title] _ [train unit] _ [frame].
Once test generates a data file, and file designation form is:Current_ [frame] _ [date] _ [time] .tdms.Wherein, date format is YYYYMMDD;Time format is HHMMSS.For example:D:\Result\Current\ SITExxx_1_JJ\Current_JJ_20141215_155436.tdms.
Embodiment described above only have expressed the several embodiments of the present invention, and its description is more concrete and detailed, but simultaneously Therefore the restriction to the scope of the claims of the present invention can not be interpreted as.It should be pointed out that for those of ordinary skill in the art For, without departing from the inventive concept of the premise, some deformation can also be made and improve, these broadly fall into the guarantor of the present invention Shield scope.Therefore, the protection domain of patent of the present invention should be defined by claims.

Claims (10)

1. a kind of nuclear power station rod control system test device is it is characterised in that include electric power system, KVM equipment, industrial computer, data Acquisition system, interface cabinet, microphone apparatus and printer;Described electric power system is not and industrial computer, KVM equipment, interface message processor (IMP) Case is for electrical connection;Described KVM equipment, data collecting system and printer are connected with industry control dynamoelectric signal respectively;Described interface Cabinet has interconnective isolation module and interface board;Described isolation module is connected with the data collecting system signal of telecommunication;Described Interface board is connected with the described microphone apparatus signal of telecommunication, and described microphone apparatus are installed on the CRDM of rod control system On with gather hook pawl action noise signal, through isolation module isolation after transmit to data collecting system;Described interface board also with The power cabinet signal of telecommunication of rod control system connects, and is sent with correspondingly received power cabinet to the stationary coil of CRDM, shifting Moving winding and the electric current clock signal of lifting coil, transmit to data collecting system after isolation module isolation;Described industry control Machine calculates corresponding hook pawl movement time and action according to the next noise signal of data collecting system transmission and electric current clock signal Electric current, and it is qualified to judge whether to make comparisons with standard value, judged result is exported or beaten by described printer by described KVM equipment Print output.
2. nuclear power station rod control system test device according to claim 1 it is characterised in that described interface board also respectively with The excellent position monitor unit cabinet of rod control system, control logic cabinet and the rod position measurement cabinet signal of telecommunication connect, and are swept with receiving excellent position respectively Retouch signal, excellent bit instruction signal and rod position measurement signal, transmit to data collecting system after isolation module isolation;Described work Excellent bit scan signal, excellent bit instruction signal and rod position measurement signal that control machine comes according to data collecting system transmission, judge control Whether with the control rod location of instruction in default error, judged result is exported or by institute the excellent measurement position of system by described KVM equipment State printer printout.
3. nuclear power station rod control system test device according to claim 1 and 2, it is characterised in that also including rosette, connects It is connected between described isolation module and data collecting system.
4. nuclear power station rod control system test device according to claim 3 is it is characterised in that described data collecting system bag Include the digital collection board for the analog acquisition board of collection voltages signal with for gathering digital signal;Described isolation module Including analog signal isolating module and digital signal isolation module;Described analog acquisition board and analog signal isolating modular telecommunications Number connect, described digital collection board is connected with the digital signal isolation module signal of telecommunication;Described analog signal isolating module is used for Isolate described noise signal and electric current clock signal;Described digital signal isolation module be used for isolating described rod bit scan signal, Excellent bit instruction signal and rod position measurement signal.
5. nuclear power station rod control system test device according to claim 4 is it is characterised in that also include connecting cabinet;Institute State connection cabinet and include the first adapter, the second adapter, the 3rd adapter, the 4th adapter and the 5th adapter;First even Connect device to be connected with the described microphone apparatus signal of telecommunication;Second adapter is used for being connected with the described rod position monitor unit cabinet signal of telecommunication; 3rd adapter is used for being connected with the described control logic cabinet signal of telecommunication;4th adapter is used for and the described rod position measurement cabinet signal of telecommunication Connect;5th adapter is used for being connected with the described power cabinet signal of telecommunication;
The interface board of described interface cabinet includes:Input first interface, input second interface, input the 3rd interface and defeated Enter end the 4th interface and corresponding outfan first interface, outfan second interface, outfan the 3rd interface and outfan the Four interfaces;Input first interface is connected with the described first adapter signal of telecommunication;Input second interface is connected with the described 5th The device signal of telecommunication electrically connects;Input the 3rd interface is electrically connected with described 4th adapter;Input the 4th interface and described second Adapter and the 3rd adapter signal of telecommunication connect;
Outfan first interface and outfan second interface are connected with the described analog acquisition board signal of telecommunication by described rosette; Outfan the 3rd interface and outfan the 4th interface are connected with the described digital collection board signal of telecommunication by described rosette.
6. nuclear power station rod control system test device according to claim 5 is it is characterised in that described digital signal isolation mode Block is solid-state relay.
7. nuclear power station rod control system test device according to claim 5 is it is characterised in that described electric power system includes controlling Panel processed and power case;Described control panel have the start button being connected with the power case signal of telecommunication, stop button and Scram button.
8. a kind of nuclear power station rod control system method of testing is it is characterised in that adopt the nuclear power described in any one of claim 5 to 7 Stand rod control system test device, and include CRDM noise record ripple method of testing;Described CRDM Noise record ripple method of testing comprises the following steps:
A1, being provided a user with by operation interface in configuration file mode can test bar group;
A2, according to user instruction from tested coupon group accordingly, and the inclusion rod of receiving user's input can be selected test bar group Position initial step length, power station title, train unit, user name, temperature and pressure are in interior information;
A3, vertical CRDM test data file folder is set up based on power station title, train unit and tested coupon;
A4, collection include hooking the noise signal of pawl action, and the electric current sequential letter of stationary coil, moving coil, lifting coil Number in interior signal data;
A5, according to noise signal and corresponding electric current clock signal calculate corresponding hook pawl movement time and action current, and with Standard value is made comparisons qualified to judge whether;
A6, described CRDM test data file folder in set up respective file to store the signal data collecting And judged result, and output display or printout.
9. nuclear power station rod control system method of testing according to claim 8 is reflected it is characterised in that also including excellent bit port again Location survey method for testing;Characterization test method comprises the following steps described rod bit port again:
B1, the including including power station title, train unit, tested excellent group, user name, temperature and pressure of receive user setting Information;
B2, vertical rod bit port characterization test data folder again is set up based on power station title, train unit and tested coupon;
B3, the excellent bit scan signal of acquisition rod position monitor unit cabinet are to identify the corresponding ear of maize group of current measuring stick position signal;And The excellent bit instruction signal of acquisition controlling logic cabinet and the rod position measurement signal of rod position measurement cabinet;
B4, judge that according to excellent bit instruction signal and rod position measurement signal whether control rod measurement position and the control rod location of instruction exist In default error;
B5, set up respective file with memory stick bit instruction signal number in characterization test data folder again in described rod bit port According to, rod position measurement signal data and judged result, and output display or printout.
10. nuclear power station rod control system method of testing according to claim 9 is it is characterised in that also include testing current side Method;Connect cabinet also respectively with frame tested in power cabinet on shunting card, isolation amplify card and select the control card signal of telecommunication Connect;Described current test method comprises the following steps:
C1, receive user setting including power station title, train unit, tested frame, user name, temperature and pressure Information;
C2, testing current data folder is set up based on power station title, train unit and tested frame;
C3, gather respectively from the tested frame of the power cabinet of rod control system zero current, half electric current, under three kinds of states of total current point Stream card voltage signal, isolation amplify card voltage signal and select control card voltage signal;
C4, judge that described shunting card voltage signal, isolation amplify card voltage signal and select control card voltage signal whether to exist In preset range;
C5, set up in described testing current data folder respective file with store shunting card voltage signal data, isolation put Kilocalorie voltage signal data and selection control card voltage signal data and judged result, and output display or printout.
CN201611002214.8A 2016-11-14 2016-11-14 Nuclear power station rod control system test device and method Active CN106384611B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201611002214.8A CN106384611B (en) 2016-11-14 2016-11-14 Nuclear power station rod control system test device and method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201611002214.8A CN106384611B (en) 2016-11-14 2016-11-14 Nuclear power station rod control system test device and method

Publications (2)

Publication Number Publication Date
CN106384611A true CN106384611A (en) 2017-02-08
CN106384611B CN106384611B (en) 2017-12-26

Family

ID=57958985

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201611002214.8A Active CN106384611B (en) 2016-11-14 2016-11-14 Nuclear power station rod control system test device and method

Country Status (1)

Country Link
CN (1) CN106384611B (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108375946A (en) * 2018-03-22 2018-08-07 北京奔驰汽车有限公司 A kind of information spy device and industrial control system
CN108548952A (en) * 2018-05-11 2018-09-18 中国核动力研究设计院 A kind of reactor control rod driving mechanism current monitoring system
CN110415844A (en) * 2019-06-21 2019-11-05 杭州安脉盛智能技术有限公司 Control rod drive mechanism performance estimating method and system based on movement crucial sequential of fault
WO2020186776A1 (en) * 2019-03-15 2020-09-24 中广核核电运营有限公司 Nuclear power plant reactor control rod addressing apparatus and method
CN112102977A (en) * 2020-09-04 2020-12-18 兰州空间技术物理研究所 Nuclear reactor safety rod performance test system

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002267789A (en) * 2001-03-12 2002-09-18 Mitsubishi Heavy Ind Ltd Device for analyzing operating state of control rod drive mechanism
CN104751919A (en) * 2015-03-03 2015-07-01 山东美核自动化科技有限公司 Rod position display system for nuclear power control rod and anti-jamming display method for nuclear power control rod
CN105929266A (en) * 2016-04-18 2016-09-07 中广核核电运营有限公司 Nuclear power plant first generation electronic actuator electronic card sensitive component testing system and method

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002267789A (en) * 2001-03-12 2002-09-18 Mitsubishi Heavy Ind Ltd Device for analyzing operating state of control rod drive mechanism
CN104751919A (en) * 2015-03-03 2015-07-01 山东美核自动化科技有限公司 Rod position display system for nuclear power control rod and anti-jamming display method for nuclear power control rod
CN105929266A (en) * 2016-04-18 2016-09-07 中广核核电运营有限公司 Nuclear power plant first generation electronic actuator electronic card sensitive component testing system and method

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
王斌 等: "《基于LabVIEW的CRDM噪声录波试验台设计》", 《现代电子技术》 *

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108375946A (en) * 2018-03-22 2018-08-07 北京奔驰汽车有限公司 A kind of information spy device and industrial control system
CN108548952A (en) * 2018-05-11 2018-09-18 中国核动力研究设计院 A kind of reactor control rod driving mechanism current monitoring system
WO2020186776A1 (en) * 2019-03-15 2020-09-24 中广核核电运营有限公司 Nuclear power plant reactor control rod addressing apparatus and method
CN110415844A (en) * 2019-06-21 2019-11-05 杭州安脉盛智能技术有限公司 Control rod drive mechanism performance estimating method and system based on movement crucial sequential of fault
CN110415844B (en) * 2019-06-21 2021-06-01 杭州安脉盛智能技术有限公司 Performance evaluation method and system for control rod driving mechanism based on action key time sequence
CN112102977A (en) * 2020-09-04 2020-12-18 兰州空间技术物理研究所 Nuclear reactor safety rod performance test system

Also Published As

Publication number Publication date
CN106384611B (en) 2017-12-26

Similar Documents

Publication Publication Date Title
CN106384611B (en) Nuclear power station rod control system test device and method
CN108922641B (en) Periodic test device and method for high-temperature reactor nuclear power station protection system
CN103163398B (en) Nuclear power station Berea panel reliability detection system and method
CN101269771B (en) Detection system for elevator
CN110356441B (en) System, method and device for locomotive signal vehicle-mounted equipment on-board detection operation
CN108152738A (en) Motor work condition inspection method and its device
CN206363768U (en) Nuclear power station rod control system test device
GB2480524A (en) Portable USB electrocardiograph system and method
CN208459847U (en) A kind of elevator control cabinet test device
CN100549707C (en) A kind of cable detecting device and scan method thereof
CN106059090A (en) Prompt system based on scheduling automation system and work method thereof
CN100535815C (en) Operation instruction system, operation instruction device, operation instruction program storage medium, and operation instruction method
CN202050507U (en) Video display testing system
CN201319049Y (en) High-tension current mutual-inductor transformation ratio tester
CN201548456U (en) Automatic measurement and control system for vertical tensile stress relaxation testing machine
CN105373057B (en) A kind of bridge pad long-distance monitoring method and system
CN108361020A (en) Underground drill rig diagnosis protective device and method based on virtual instrument
CN109655101A (en) A kind of torque rotary speed intelligent observing and controlling system and test method
CN112881888A (en) Testing device and method for VGA interface protection circuit of server display card
CN106707155A (en) Small-capacity contactor acting characteristic test system and method
KR100496126B1 (en) coil current monitoring system for control element drive mechanism control system and methods thereof
CN204359885U (en) Electronic combination automatically testing parameters diagnostic equipment
CN207764369U (en) A kind of intelligent electric energy meter sampling full-automatic result of performance test judges system
CN109669094A (en) The detection device and method of signal wire in a kind of display screen
CN110837015A (en) Portable remote measurement test device for field operation and maintenance and working method thereof

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant