CN108389637A - A kind of lead bismuth heap fuel element cladding integrality on-line monitoring system and method - Google Patents
A kind of lead bismuth heap fuel element cladding integrality on-line monitoring system and method Download PDFInfo
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- CN108389637A CN108389637A CN201810123232.4A CN201810123232A CN108389637A CN 108389637 A CN108389637 A CN 108389637A CN 201810123232 A CN201810123232 A CN 201810123232A CN 108389637 A CN108389637 A CN 108389637A
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- lead bismuth
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/002—Detection of leaks
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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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- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
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Abstract
The present invention provides a kind of lead bismuth heap fuel element cladding integrality on-line monitoring system, including：Delayed neutron probe unit monitors and obtains delayed neutron fluence rate data in real time；Feature fission nuclide probe unit monitors and obtains feature fission nuclide radioactive activity data in real time；Back end data centralized processing unit has the function of auto-alarm function and output evaluation conclusion report, receives delayed neutron fluence rate data and feature fission nuclide radioactive activity data, by it compared with preset corresponding threshold value is compared and is provided conclusion.The on-line monitoring system realizes the automation and real time implementation of lead bismuth heap fuel Integrity Assessment；Acquisition data are monitored simultaneously by delayed neutron probe unit and feature fission nuclide probe unit, and are verified through Data Centralized Processing unit, and the reliability of the online Integrity Assessment of lead bismuth heap fuel is greatly improved；It can also be used to instruct the sipping test after shutdown.
Description
Technical field
The present invention relates to reactor leakage monitoring technical field more particularly to a kind of lead bismuth heap fuel element cladding integralities
On-line monitoring system and method.
Background technology
Fuel element cladding is the second in four safety curtain of nuclear power station, undertakes and contains fuel pellet fission product
Task.If fuel element cladding is damaged, fission product will be discharged into primary Ioops coolant by cut, to the peace of nuclear power plant
Row for the national games generates potential impact.Timely and accurately judge whether fuel element cladding damaged in operation, break size and
Damage location has major contribution to the safe operation of nuclear power plant with economical operation.Damaged and shutdown occurs for fuel element cladding
Afterwards, it is necessary to fuel rod clad be carried out to sob leakage experiment, find the fuel assembly of clad failure and replacement.If before sobbing leakage experiment
It can determine that out fuel element cladding breakage and its location, it will be able to sob the suggestion that leakage experiment provides directiveness,
Can be to sob leakage experiment to save the time, so as to shorten Shutdown time.This has the safety and economic operation of nuclear power generating sets important
Meaning.
Domestic in-service nuclear power station is presurized water reactor heap-type at present, has total γ to put the method for fuel element cladding breakage monitoring
Penetrating property activity monitors method, regular sampling method, shutdown sipping test on-line：
1, total gamma activity activity monitors method on-line：This is that a kind of gross activity of a variety of nucleic in the water to primary Ioops exist
The method that line continuously monitors, if breakage occurs for fuel element cladding, the total γ activity monitored is significantly higher.It is this
The advantages of method is can be continuously monitored to the radioactive activity of primary Ioops coolant.
2, regular sampling method（Artificial chemistry samples）：This is a kind of is periodically sampled to primary Ioops coolant and to sample
The method for carrying out radioassay, is the current most common method of nuclear power plant of China.
3, shutdown sipping test：This method is to be divided into online qualitative analysis and offline quantitative point during shutdown discharging
Two kinds of analysis.That damaged leak detection is carried out to the fuel assembly after irradiation in linear location sipping test, when fuel assembly rises to can
After extension sleeve, Xe-133 activity is measured by gamma detector to judge fuel element cladding with the presence or absence of breakage.It is offline quantitative
Sipping test is determined as having damaged fuel assembly just to carry out quantitative analysis, this side in this way for online qualitative detection
Method makes fission gas pressure in fuel rod increase using the temperature for improving fuel assembly surrounding fluid, fission gas（Such as Xe-133）
It will accelerate effusion outward in order to detect.The size for judging fuel element cladding cut that this method can quantify.
Three of the above method is respectively present technological deficiency below：
Always the diagnosis principle of gamma activity activity on-line monitoring method is limited larger, and diagnostic result accuracy is poor, and is susceptible to
The phenomenon that wrong diagnosis；This method carries out result judgement with semiempirical formula rather than mechanistic calculating provides diagnostic result, Wu Fazhun
Really judge the size and fuel consumption of cut.
Regular sampling method needs manually to sample in person to scene, increases personnel's accident risk of exposure, and add people
The uncertainty of diagnostic result is considerably increased for factor of judgment；Secondly this method cannot achieve continuous monitoring, cannot send out in time
Existing breakage, it is long to easily lead to hidden danger retention time.
Shutdown sipping test could carry out after needing shutdown to uncap, and extremely take, and easily extend Shutdown time.
For this purpose, be badly in need of seeking a kind of method can not only connect monitoring fuel element cladding integrality again can objective analysis to paying a home visit
Disconnected result.
However fuel element cladding occur it is damaged after, since the size of involucrum cut, size are different, each characteristic nuclide
（87Br、137I, inert gas and caesium etc.）Physicochemical properties it is different, the amount of the characteristic nuclide released from cut is also different；
Simultaneously unlike presurized water reactor, each characteristic nuclide also occurs that respective chemical reaction, Transport with lead bismuth coolant
It is completely different with presurized water reactor.Our research direction can feature based fission nuclide and feature delayed neutron radioactivity analyze
The integrality of fuel element cladding realizes that on-line monitoring function and mechanism of calculating provides diagnostic result.
Invention content
Technical problem to be solved by the present invention lies in provide a kind of lead bismuth heap fuel element cladding integrality on-line monitoring
System and method, improves existing monitoring system or method cannot achieve continuous monitoring and the non-mechanistic problem of diagnosis.
In order to solve the above technical problem, the present invention provides a kind of lead bismuth heap fuel element cladding integrality on-line monitorings to be
System, may include：
Delayed neutron probe unit monitors and obtains delayed neutron fluence rate data in real time；
Feature fission nuclide probe unit monitors and obtains feature fission nuclide radioactive activity data in real time；
Back end data centralized processing unit gets delayed neutron fluence rate data and feature fission nuclide radioactivity described in reception
Activity data, by it compared with preset corresponding threshold value is compared and is provided conclusion；
The Back end data centralized processing unit has the function of auto-alarm function and output evaluation conclusion report.
In an alternate embodiment of the invention, the lead bismuth heap fuel element cladding integrality on-line monitoring system accelerates for monitoring
Device drives subcritical fast neutron reactor.
In an alternate embodiment of the invention, the delayed neutron probe unit is installed on the reactor pit of lead bismuth heap according to lead bismuth heap feature
Outside.
In an alternate embodiment of the invention, configured with collimator in the delayed neutron probe unit3He pops one's head in.
In an alternate embodiment of the invention, described with collimator3He alignment probes are in the vertical to pipeline section of lead bismuth process system.
In an alternate embodiment of the invention, the data processing module of the delayed neutron probe unit is to the delayed neutron fluence
Rate data carry out the interference removal of neutron field background.
In an alternate embodiment of the invention, the feature fission nuclide probe unit is installed on the protective cover air draft on lead bismuth heap heap top
At pipeline.
In an alternate embodiment of the invention, it is detected configured with HpGe gamma spectrometer in the feature fission nuclide probe unit
Device.
In an alternate embodiment of the invention, the feature fission nuclide includes inert gas, iodine and cesium element.
In an alternate embodiment of the invention, the Back end data centralized processing unit has data processing, analysis and comparison work(
Energy.
In order to solve the above technical problem, the present invention provides a kind of lead bismuth heap fuel element cladding integrality on-line monitoring sides
Method, step include：
Step 1, the delayed neutron probe unit obtain the delayed neutron fluence rate data in real time；
The feature fission nuclide probe unit obtains the radioactive activity data of the feature fission nuclide in real time；
Step 2, the delayed neutron probe unit carry out neutron field background to the delayed neutron fluence rate data got
Interference removal；
Step 3, the Back end data centralized processing unit are according to the delayed neutron fluence rate data got in real time and in advance
If threshold values compared, judge whether the lead bismuth heap fuel element cladding damaged and provides conclusion one；
The Back end data centralized processing unit is according to the radioactive activity data of the feature fission nuclide got in real time
It is compared with preset threshold values, judges whether the lead bismuth heap fuel element cladding is damaged and provides conclusion two；
When step 4, the conclusion one are breakage with the conclusion two, the Back end data centralized processing unit automatic alarm is simultaneously
To evaluation conclusion report of the master control room output with every specific data；
In the conclusion one and the conclusion two only there are one being damaged when, the Back end data centralized processing unit return information
It requires to carry out manual verification's work to artificial access entrance；
When the conclusion one and the conclusion two are not damaged, the on-line monitoring system is without report output and continues to monitor work
Make.
In summary, the advantageous effect of the embodiment of the present invention is：
In terms of to nuclear reactor leakage monitoring, the automation and real time implementation of lead bismuth heap fuel Integrity Assessment are realized；Pass through
Delayed neutron probe unit and feature fission nuclide probe unit monitor acquisition data simultaneously, and through Data Centralized Processing unit school
It tests, greatly improves the reliability of the online Integrity Assessment of lead bismuth heap fuel；It can also be used to instruct the sipping test after shutdown.
Description of the drawings
In order to more clearly explain the embodiment of the invention or the technical proposal in the existing technology, to embodiment or will show below
There is attached drawing needed in technology description to be briefly described, it should be apparent that, the accompanying drawings in the following description is only this
Invention is not paying creation for those of ordinary skill in the art applied to some embodiments of lead bismuth cooled reactor
Property labour under the premise of, other drawings may also be obtained based on these drawings.
Fig. 1 is a kind of function of one embodiment of lead bismuth heap fuel element cladding integrality on-line monitoring system of the present invention
Structural schematic diagram.
Fig. 2 is a kind of flow chart of one embodiment of lead bismuth heap fuel element cladding Integrity Verification method of the present invention.
Specific implementation mode
The explanation of following embodiment is refer to the attached drawing, can be to the specific embodiment implemented to the example present invention.
The embodiment of the present invention provides a kind of lead bismuth heap fuel element cladding integrality on-line monitoring system, adds for monitoring
Fast device drives subcritical fast neutron reactor.The present embodiment is to use on-line monitoring system monitoring accelerator driving subcritical fast
For neutron reactor, the function and working method of the system is expanded on further.Accelerator Driven Subcritical fast neutron reactor
Using lead bismuth alloy as coolant, primary Ioops coolant system is mainly by primary tank, in-pile component, main pump, main heat exchanger and supervisor
Composition.Fuel assembly uses 4.95%235U degree of enrichment regular hexagon components, cladding materials type are 15-15 Ti, fuel pellet
With involucrum gap filling helium.
The on-line monitoring system of the reactor is monitored as shown in Figure 1, including following functions unit：
Delayed neutron probe unit 1 is installed on according to lead bismuth heap feature on the outside of the reactor pit of lead bismuth heap, and collimator is equipped in unit
's3He alignment probes can be carried out in the vertical to pipeline section of lead bismuth process system by the probe87Br and137I parent nucleus delayed neutrons
The measurement collecting work of fluence rate, data processing module in the delayed neutron probe unit 1 is by collected fluence rate data
After carrying out the interference removal of neutron field background, it is transmitted to Back end data centralized processing unit 3.
Feature fission nuclide probe unit 2 is installed at the protective cover air draft pipeline on lead bismuth heap heap top, the HpGe in unit
Gamma spectrometer detector can carry out feature fission nuclide to the gas being discharged in reactor（Inert gas, iodine, caesium etc.）Radioactivity
Activity measurement, this feature fission nuclide probe unit 2 are transferred to Back end data after the data measured are carried out gamma spectrum analysis
Centralized processing unit 3.
Back end data centralized processing unit 3, have data processing, analysis and comparing function, it can be achieved that the storage of data and
Logic judgment, pre-sets delayed neutron fluence rate in the Back end data centralized processing unit 3 and feature fission nuclide is put
The threshold values of penetrating property activity, once the real time data that prison side system measures online is more than threshold values, Back end data centralized processing is single
Member 3 will automatic alarm, and Real-Time Evaluation analysis report is transferred in the master control room in nuclear power station.
The work flow diagram of above lead bismuth heap fuel element cladding integrality on-line monitoring system is as shown in Figure 2：
Delayed neutron probe unit 1 and feature fission nuclide probe unit 2 in nuclear reactor working condition can in real time to its into
Row monitoring.
Step S1：
Delayed neutron probe unit 1 obtains delayed neutron fluence rate data in real time；
Feature fission nuclide probe unit 2 obtains feature fission nuclide in real time（Inert gas, iodine, caesium etc.）Radioactivity live
Degrees of data.
Step S2：
Delayed neutron probe unit 1 carries out the interference removal of neutron field background to the delayed neutron fluence rate data got.
Step S3：
Back end data centralized processing unit 3 carries out pair according to the delayed neutron fluence rate data that get in real time and preset threshold values
Than whether judgement lead bismuth heap fuel element cladding is damaged and provides conclusion；
Back end data centralized processing unit 3 according to the radioactive activity data of the feature fission nuclide got in real time with it is preset
Threshold values is compared, and whether judgement lead bismuth heap fuel element cladding is damaged and provides conclusion；
Step S4：
The data that two probe units of Back end data centralized processing unit pair obtain mutually are verified, to determine overall merit number
According to.
Specifically, if it is breakage to go out conclusion by delayed neutron fluence rate data judging, pass through feature fission nuclide
It is breakage that radioactive activity data judging, which goes out conclusion also, then from 3 automatic alarm of Back end data centralized processing unit and to master control room
Evaluation conclusion report of the output with every specific data.
If it is not damaged to go out conclusion by delayed neutron fluence rate data judging, pass through the radioactivity of feature fission nuclide
It is breakage that activity data judging, which goes out conclusion,；Or it is breakage to go out conclusion by delayed neutron fluence rate data judging, passes through feature
It is not damaged that the radioactive activity data judging of fission nuclide, which goes out conclusion,；People is then back to by Back end data centralized processing unit 3
Work accesses entrance and carries out manual verification's work.
If it is concluded that being not damaged, then output report and do not continue to monitor.
By above description it is found that the beneficial effects of the present invention are：Realize oneself of lead bismuth heap fuel Integrity Assessment
Dynamicization and real time implementation；Acquisition data are monitored simultaneously by delayed neutron probe unit and feature fission nuclide probe unit, and are passed through
Data Centralized Processing unit verifies, and greatly improves the reliability of the online Integrity Assessment of lead bismuth heap fuel；It can also be used to instruct
Sipping test after shutdown.
Above disclosed is only the preferred embodiment that the present invention is applied to lead bismuth cooled reactor, certainly cannot be with
This limits the interest field of the present invention, therefore equivalent changes made in accordance with the claims of the present invention, still belongs to the present invention and is covered
Range.
Claims (10)
1. a kind of lead bismuth heap fuel element cladding integrality on-line monitoring system, the fuel element for lead bismuth cooled reactor is broken
Damage and leak supervision, which is characterized in that including：
Delayed neutron probe unit monitors and obtains delayed neutron fluence rate data in real time；
Feature fission nuclide probe unit monitors and obtains feature fission nuclide radioactive activity data in real time；
Back end data centralized processing unit gets delayed neutron fluence rate data and feature fission nuclide radioactivity described in reception
Activity data, by it compared with preset corresponding threshold value is compared and is provided conclusion；
The Back end data centralized processing unit has the function of auto-alarm function and output evaluation conclusion report.
2. lead bismuth heap fuel element cladding integrality on-line monitoring system according to claim 1, which is characterized in that described
Lead bismuth heap fuel element cladding integrality on-line monitoring system drives subcritical fast neutron reactor for monitoring accelerator.
3. lead bismuth heap fuel element cladding integrality on-line monitoring system according to claim 1, which is characterized in that described
Delayed neutron probe unit is installed on according to lead bismuth heap feature on the outside of the reactor pit of lead bismuth heap.
4. lead bismuth heap fuel element cladding integrality on-line monitoring system according to claim 3, which is characterized in that described
Configured with collimator in delayed neutron probe unit3He pops one's head in.
5. lead bismuth heap fuel element cladding integrality on-line monitoring system according to claim 4, which is characterized in that described
With collimator3He alignment probes are in the vertical to pipeline section of lead bismuth process system.
6. lead bismuth heap fuel element cladding integrality on-line monitoring system according to claim 1, which is characterized in that described
The data processing module of delayed neutron probe unit carries out the interference removal of neutron field background to the delayed neutron fluence rate data.
7. lead bismuth heap fuel element cladding integrality on-line monitoring system according to claim 1, which is characterized in that described
Feature fission nuclide probe unit is installed at the protective cover air draft pipeline on lead bismuth heap heap top.
8. lead bismuth heap fuel element cladding integrality on-line monitoring system according to claim 7, which is characterized in that described
HpGe gamma spectrometer detector is configured in feature fission nuclide probe unit；The feature fission nuclide includes indifferent gas
Body, iodine and cesium element.
9. lead bismuth heap fuel element cladding integrality on-line monitoring system according to claim 1, which is characterized in that described
Back end data centralized processing unit has data processing, analysis and comparing function.
10. a kind of lead bismuth heap fuel element cladding integrality on-line monitoring method：
Step 1, the delayed neutron probe unit obtain the delayed neutron fluence rate data in real time；
The feature fission nuclide probe unit obtains the radioactive activity data of the feature fission nuclide in real time；
Step 2, the delayed neutron probe unit carry out neutron field background to the delayed neutron fluence rate data got
Interference removal；
Step 3, the Back end data centralized processing unit are according to the delayed neutron fluence rate data got in real time and in advance
If threshold values compared, judge whether the lead bismuth heap fuel element cladding damaged and provides conclusion one；
The Back end data centralized processing unit is according to the radioactive activity data of the feature fission nuclide got in real time
It is compared with preset threshold values, judges whether the lead bismuth heap fuel element cladding is damaged and provides conclusion two；
When step 4, the conclusion one are breakage with the conclusion two, the Back end data centralized processing unit automatic alarm is simultaneously
To evaluation conclusion report of the master control room output with every specific data；
In the conclusion one and the conclusion two only there are one being damaged when, the Back end data centralized processing unit return information
It requires to carry out manual verification's work to artificial access entrance；
When the conclusion one and the conclusion two are not damaged, the on-line monitoring system is without report output and continues to monitor work
Make.
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Application publication date: 20180810 |